IAEA Safety Standards
for protecting people and the environment

IAEA Safety Standards Series No. GSR Part 3

Radiation Protection and
Safety of Radiation Sources:
International Basic
Safety Standards
Jointly sponsored by
EC, FAO, IAEA, ILO, OECD/NEA, PAHO, UNEP, WHO

PAHO

WHO
PAHO

WHO

http://ec.europa.eu/dgs/communication/services/visual_identity/index_en.htm

General Safety Requirements Part 3
No. GSR Part 3

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IAEA SAFETY STANDARDS AND RELATED PUBLICATIONSIAEA SAFETY STANDARDSUnder the terms of Article III of its Statute, the IAEA is authorized to establish or adopt
standards of safety for protection of health and minimization of danger to life and property, andto provide for the application of these standards.
The publications by means of which the IAEA establishes standards are issued in the
IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport
safety and waste safety. The publication categories in the series are Safety Fundamentals,
Safety Requirements and Safety Guides.
Information on the IAEA’s safety standards programme is available on the IAEA Internet
site
http://www-ns.iaea.org/standards/
The site provides the texts in English of published and draft safety standards. The texts
of safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety
Glossary and a status report for safety standards under development are also available. For
further information, please contact the IAEA at: Vienna International Centre, PO Box 100,
1400 Vienna, Austria.
All users of IAEA safety standards are invited to inform the IAEA of experience in theiruse (e.g. as a basis for national regulations, for safety reviews and for training courses) for the
purpose of ensuring that they continue to meet users’ needs. Information may be provided via
the IAEA Internet site or by post, as above, or by email to Ofﬁcial.Mail@iaea.org.
RELATED PUBLICATIONSThe IAEA provides for the application of the standards and, under the terms of Articles III
and VIII.C of its Statute, makes available and fosters the exchange of information relating
to peaceful nuclear activities and serves as an intermediary among its Member States for thispurpose.
Reports on safety in nuclear activities are issued as Safety Reports, which provide
practical examples and detailed methods that can be used in support of the safety standards.
Other safety related IAEA publications are issued as Emergency Preparedness andResponse publications, Radiological Assessment Reports, the International Nuclear Safety
Group’s INSAG Reports, Technical Reports and TECDOCs. The IAEA also issues reports
on radiological accidents, training manuals and practical manuals, and other special safety
related publications.
Security related publications are issued in the IAEA Nuclear Security Series.
The IAEA Nuclear Energy Series comprises informational publications to encourage
and assist research on, and the development and practical application of, nuclear energy forpeaceful purposes. It includes reports and guides on the status of and advances in technology,
and on experience, good practices and practical examples in the areas of nuclear power, thenuclear fuel cycle, radioactive waste management and decommissioning.

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RADIATION PROTECTION AND
SAFETY OF RADIATION SOURCES:INTERNATIONAL BASIC
SAFETY STANDARDSThe following States are Members of the International Atomic Energy Agency:
AFGHANISTANALBANIA
ALGERIAANGOLA
ARGENTINA
ARMENIA
AUSTRALIA
AUSTRIAAZERBAIJAN
BAHAMAS
BAHRAINBANGLADESH
BELARUSBELGIUM
BELIZEBENIN
BOLIVIABOSNIA AND HERZEGOVINABOTSWANABRAZILBRUNEI DARUSSALAM
BULGARIA
BURKINA FASO
BURUNDICAMBODIACAMEROONCANADACENTRAL AFRICAN
REPUBLIC
CHAD
CHILE
CHINA
COLOMBIACONGOCOSTA RICA
CÔTE D’IVOIRECROATIACUBACYPRUSCZECH REPUBLIC
DEMOCRATIC REPUBLIC
OF THE CONGO
DENMARKDOMINICADOMINICAN REPUBLICECUADOREGYPTEL SALVADORERITREAESTONIAETHIOPIAFIJI
FINLANDFRANCEGABONGEORGIAGERMANYGHANA
GREECEGUATEMALAHAITI
HOLY SEE
HONDURASHUNGARYICELAND
INDIA
INDONESIA
IRAN, ISLAMIC REPUBLIC OFIRAQIRELANDISRAELITALY
JAMAICAJAPANJORDANKAZAKHSTANKENYAKOREA, REPUBLIC OFKUWAITKYRGYZSTANLAO PEOPLE’S DEMOCRATIC
REPUBLICLATVIALEBANONLESOTHO
LIBERIA
LIBYA
LIECHTENSTEIN
LITHUANIALUXEMBOURG
MADAGASCARMALAWI
MALAYSIAMALI
MALTA
MARSHALL ISLANDS
MAURITANIA
MAURITIUS
MEXICOMONACOMONGOLIAMONTENEGRO
MOROCCOMOZAMBIQUE
MYANMAR
NAMIBIANEPAL
NETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAYOMANPAKISTAN
PALAU
PANAMAPAPUA NEW GUINEAPARAGUAYPERU
PHILIPPINESPOLANDPORTUGALQATARREPUBLIC OF MOLDOVAROMANIARUSSIAN FEDERATIONRWANDASAN MARINOSAUDI ARABIASENEGALSERBIASEYCHELLESSIERRA LEONESINGAPORESLOVAKIASLOVENIA
SOUTH AFRICASPAIN
SRI LANKASUDAN
SWAZILANDSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTAJIKISTANTHAILANDTHE FORMER YUGOSLAVREPUBLIC OF MACEDONIATOGOTRINIDAD AND TOBAGOTUNISIA
TURKEYUGANDAUKRAINE
UNITED ARAB EMIRATESUNITED KINGDOM OFGREAT BRITAIN ANDNORTHERN IRELAND
UNITED REPUBLICOF TANZANIAUNITED STATES OF AMERICAURUGUAYUZBEKISTANVENEZUELAVIET NAMYEMEN
ZAMBIA
ZIMBABWE

The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the
IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The
Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge thecontribution of atomic energy to peace, health and prosperity throughout the world’’.

IAEA SAFETY STANDARDS SERIES No. GSR Part 3

RADIATION PROTECTION AND
SAFETY OF RADIATION SOURCES:INTERNATIONAL BASIC
SAFETY STANDARDSGENERAL SAFETY REQUIREMENTS
JOINTLY SPONSORED BY:EUROPEAN COMMISSION,
FOOD AND AGRICULTURE ORGANIZATION OF
THE UNITED NATIONS,INTERNATIONAL ATOMIC ENERGY AGENCY,
INTERNATIONAL LABOUR ORGANIZATION,OECD NUCLEAR ENERGY AGENCY,
PAN AMERICAN HEALTH ORGANIZATION,
UNITED NATIONS ENVIRONMENT PROGRAMME,WORLD HEALTH ORGANIZATIONThis publication includes a CD-ROM containing the IAEA Safety Glossary:
2007 Edition (2007) and the Fundamental Safety Principles (2006),
each in Arabic, Chinese, English, French, Russian and Spanish versions.
The CD-ROM is also available for purchase separately.
See: http://www-pub.iaea.org/MTCD/publications/publications.asp
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, 2014

COPYRIGHT NOTICEAll IAEA scientific and technical publications are protected by the terms of
the Universal Copyright Convention as adopted in 1952 (Berne) and as revisedin 1972 (Paris). The copyright has since been extended by the World Intellectual
Property Organization (Geneva) to include electronic and virtual intellectual
property. Permission to use whole or parts of texts contained in IAEA publicationsin printed or electronic form must be obtained and is usually subject to royalty
agreements. Proposals for non-commercial reproductions and translations arewelcomed and considered on a case-by-case basis. Enquiries should be addressedto the IAEA Publishing Section at:
Marketing and Sales Unit, Publishing Section
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fax: +43 1 2600 29302
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email: sales.publications@iaea.org
http://www.iaea.org/books© IAEA, 2014
Printed by the IAEA in Austria
July 2014
STI/PUB/1578
https://doi.org/10.61092/iaea.u2pu-60vm

IAEA Library Cataloguing in Publication Data
Radiation protection and safety of radiation sources : international basic safety
standards. — Vienna : International Atomic Energy Agency, 2014.
p. ; 24 cm. — (IAEA safety standards series, ISSN 1020–525X ;no. GSR Part 3)
STI/PUB/1578
ISBN 978–92–0–135310–8
Includes bibliographical references.
1. Radiation — Safety measures — Standards. 2. Radioactive substances —Safety measures — Standards. 3. Radiation — Dosage Standards. I. International
Atomic Energy Agency. II. Series.
IAEAL

14–00900

FOREWORD
by Yukiya Amano
Director General
The IAEA’s Statute authorizes the Agency to “establish or adopt…
standards of safety for protection of health and minimization of danger to life andproperty” — standards that the IAEA must use in its own operations, and which
States can apply by means of their regulatory provisions for nuclear and radiation
safety. The IAEA does this in consultation with the competent organs of theUnited Nations and with the specialized agencies concerned. A comprehensive
set of high quality standards under regular review is a key element of a stable andsustainable global safety regime, as is the IAEA’s assistance in their application.
The IAEA commenced its safety standards programme in 1958. The
emphasis placed on quality, fitness for purpose and continuous improvement
has led to the widespread use of the IAEA standards throughout the world. The
Safety Standards Series now includes unified Fundamental Safety Principles,
which represent an international consensus on what must constitute a high levelof protection and safety. With the strong support of the Commission on Safety
Standards, the IAEA is working to promote the global acceptance and use of its
standards.
Standards are only effective if they are properly applied in practice.
The IAEA’s safety services encompass design, siting and engineering safety,
operational safety, radiation safety, safe transport of radioactive material andsafe management of radioactive waste, as well as governmental organization,
regulatory matters and safety culture in organizations. These safety services assist
Member States in the application of the standards and enable valuable experienceand insights to be shared.
Regulating safety is a national responsibility, and many States havedecided to adopt the IAEA’s standards for use in their national regulations. For
parties to the various international safety conventions, IAEA standards provide
a consistent, reliable means of ensuring the effective fulfilment of obligations
under the conventions. The standards are also applied by regulatory bodies andoperators around the world to enhance safety in nuclear power generation and innuclear applications in medicine, industry, agriculture and research.
Safety is not an end in itself but a prerequisite for the purpose of theprotection of people in all States and of the environment — now and in the
future. The risks associated with ionizing radiation must be assessed andcontrolled without unduly limiting the contribution of nuclear energy to equitable
and sustainable development. Governments, regulatory bodies and operators
everywhere must ensure that nuclear material and radiation sources are usedbeneficially, safely and ethically. The IAEA safety standards are designed tofacilitate this, and I encourage all Member States to make use of them.

NOTE BY THE SECRETARIATThe IAEA safety standards reflect an international consensus on what
constitutes a high level of safety for protecting people and the environment fromharmful effects of ionizing radiation. The process of developing, reviewing andestablishing the IAEA standards involves the IAEA Secretariat and all Member
States, many of which are represented on the four IAEA safety standards
committees and the IAEA Commission on Safety Standards.
The IAEA standards, as a key element of the global safety regime, are kept
under regular review by the Secretariat, the safety standards committees andthe Commission on Safety Standards. The Secretariat gathers information on
experience in the application of the IAEA standards and information gained fromthe follow-up of events for the purpose of ensuring that the standards continue
to meet users’ needs. The present publication reflects feedback and experience
accumulated until 2010 and it has been subject to the rigorous review process forstandards.
Lessons that may be learned from studying the accident at the Fukushima
Daiichi nuclear power plant in Japan following the disastrous earthquake andtsunami of 11 March 2011 will be reflected in this IAEA safety standard asrevised and issued in the future.

PREFACE BY THE SPONSORING ORGANIZATIONSESTABLISHMENT OF THE INTERNATIONAL BASIC SAFETY
STANDARDS BY THE IAEA BOARD OF GOVERNORS AND
THEIR APPROVAL BY THE SPONSORING ORGANIZATIONSRadiation Protection and Safety of Radiation Sources: International Basic
Safety Standards are jointly sponsored by the European Commission (EC), theFood and Agriculture Organization of the United Nations (FAO), the IAEA, theInternational Labour Organization (ILO), the OECD Nuclear Energy Agency(OECD/NEA), the Pan American Health Organization (PAHO), the United
Nations Environment Programme (UNEP) and the World Health Organization(WHO) (the Sponsoring Organizations).
The Board of Governors of the IAEA established the draft text in English of
the revised International Basic Safety Standards (hereinafter referred to as ‘theseStandards’) as a standard of the IAEA at its meeting on 12 September 2011.
The Steering Committee for Nuclear Energy, the governing body of the
OECD/NEA, approved these Standards and agreed to jointly sponsor them at its
meeting held on 27–28 October 2011.
The Director General of the FAO confirmed its endorsement andco-sponsorship of these Standards on 29 October 2011.
The Executive Director of UNEP confirmed its support for andco-sponsorship of these Standards by letter addressed to the Director General of
the IAEA dated 12 March 2012.
The ILO’s Governing Body approved publication of these Standards at its
313th Session on 21 March 2012.
The WHO’s Executive Board noted these Standards on 28 May 2012 at its
131st meeting, and this completed the necessary action by WHO as a co-sponsor.
The EC notified endorsement of these Basic Safety Standards on behalf ofthe European Atomic Energy Community (Euratom) by letter addressed to the
Director General of the IAEA dated 14 August 2012.
For PAHO, the 28th Pan American Sanitary Conference endorsed theseStandards on 20 September 2012, and requested PAHO to cooperate with its
member states on their implementation. This completed the authorization process
for joint sponsorship by the Sponsoring Organizations.
The IAEA, on behalf of the Sponsoring Organizations, is hereby issuingthese Standards as General Safety Requirements No. GSR Part 3 in the IAEA
Safety Standards Series. These Standards are to be issued as a final publicationin Arabic, Chinese, English, French, Russian and Spanish. General Safety
Requirements No. GSR Part 3 supersedes General Safety Requirements
No. GSR Part 3 (Interim edition) issued in 2011, which itself superseded theInternational Basic Safety Standards that were issued as IAEA Safety SeriesNo. 115 in February 1996 (hereinafter referred to as the ‘BSS of 1996’) under thejoint sponsorship of the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.
BASIS FOR THESE STANDARDSIn the system of international intergovernmental organizations, thefirst endeavour by the IAEA to establish international standards for radiation
protection and safety was made in the 1950s. The Board of Governors of the
IAEA first approved health and safety measures in March 19601, when it
was stated that “The Agency’s basic safety standards...will be based, to theextent possible, on the recommendations of the International Commission on
Radiological Protection (ICRP)”.
The Board of Governors of the IAEA first approved Basic Safety Standards
in June 1962; they were published by the IAEA as IAEA Safety Series No. 92.
A revised edition was issued in 19673. A third revision was published by the
IAEA as the 1982 Edition of IAEA Safety Series No. 94; this edition was jointly
sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was
International Basic Safety Standards for Protection against Ionizing Radiationand for the Safety of Radiation Sources, published by the IAEA as IAEA Safety
Series No. 115 in February 19965, and jointly sponsored by the FAO, IAEA, ILO,
OECD/NEA, PAHO and the WHO.

1
INTERNATIONAL ATOMIC ENERGY AGENCY, The Agency’s Health and Safety
Measures, INFCIRC/18, IAEA, Vienna (1960); The Agency’s Safety Standards and Measures,
INFCIRC/18/Rev.1, IAEA, Vienna (1976).
2
INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for
Radiation Protection, IAEA Safety Series No. 9, IAEA, Vienna (1962).
3
INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for
Radiation Protection (1967 Edition), IAEA Safety Series No. 9, IAEA, Vienna (1967).
4
INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for
Radiation Protection (1982 Edition), IAEA Safety Series No. 9, IAEA, Vienna (1982).
5
FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS,INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOURORGANISATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTHORGANIZATION, WORLD HEALTH ORGANIZATION, International Basic Safety
Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources,
IAEA Safety Series No. 115, IAEA, Vienna (1996).

These Standards apply the IAEA Safety Fundamentals: Fundamental
Safety Principles (SF-1)6, which includes a statement of the fundamental safety
objective and a unified set of principles representing a common safety philosophy
across all areas of application of the IAEA safety standards. The fundamental
safety objective of protecting people — individually and collectively — andthe environment from harmful effects of ionizing radiation has to be achieved
without unduly limiting the operation of facilities or the conduct of activities thatgive rise to radiation risks.
SF-1 constitutes the basis on which, under the IAEA’s safety standards
programme, these Standards establish requirements for the protection of people
and the environment from harmful effects of ionizing radiation and for the safetyof radiation sources. It also provides the rationale for the IAEA’s wider safety
related programme. SF-1 was jointly sponsored by Euratom, the FAO, ILO,
International Maritime Organization (IMO), OECD/NEA, PAHO, UNEP and the
WHO.
These Standards are published in the IAEA Safety Standards Series, which
includes other related international standards, such as the Regulations for the
Safe Transport of Radioactive Material (the IAEA Transport Regulations (No.
SSR-6)); Governmental, Legal and Regulatory Framework for Safety (General
Safety Requirements No. GSR Part 1); Preparedness and Response for a Nuclear
or Radiological Emergency (No. GS-R-2); The Management System for Facilities
and Activities (No. GS-R-3); Safety Assessment for Facilities and Activities(General Safety Requirements No. GSR Part 4); Predisposal Managementof Radioactive Waste (General Safety Requirements No. GSR Part 5); andDecommissioning of Facilities (General Safety Requirements No. GSR Part 6).
The other Sponsoring Organizations have also produced standards,
codes and guides in their respective spheres of activity. Notably, the ILO hasestablished a Convention concerning the Protection of Workers against Ionising
Radiations, 1960 (No. 115) and a Recommendation concerning the Protectionof Workers against Ionising Radiations, 1960 (No. 114). The ILO has also
issued a code of practice for the radiation protection of workers as well asother relevant publications. The PAHO and the WHO have issued a numberof publications relating to the protection and safety of workers and of patients

6

EUROPEAN ATOMIC ENERGY COMMUNITY, FOOD AND AGRICULTURE
ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGYAGENCY, INTERNATIONAL LABOUR ORGANIZATION, INTERNATIONALMARITIME ORGANIZATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICANHEALTH ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME,WORLD HEALTH ORGANIZATION, Fundamental Safety Principles, IAEA Safety Standards
Series No. SF-1, IAEA, Vienna (2006).

in medical applications of radiation. The FAO and the WHO have established,through the Joint FAO/WHO Codex Alimentarius Commission, guideline levels
for radioactive substances in foodstuffs moving in international trade. The WHO
produces guidelines for drinking water quality that include criteria to assess thesafety of drinking water with respect to its radionuclide content.
The OECD/NEA has issued publications on specific topics relating toradiation protection and safety. Euratom, since 20 February 1959, has adopted
Basic Safety Standards for protection of the health of the general public
and workers against the dangers of ionizing radiation laid down in Council
Directives (Euratom), and regularly updated these in close cooperation with thedevelopment of international standards. The Euratom Standards are binding on
EU member states, and the unique responsibility of Euratom in establishing suchstandards implies that its sponsorship of international standards encourages theirharmonized implementation worldwide without prejudice to Euratom procedures
and legislation.
These Standards are to be applied by the Sponsoring Organizations to theirown operations, and are recommended for use by States and national authorities
and by other international organizations in relation to their own activities.
The application of these standards by EU member states is ensured by the
implementation of binding Euratom legislation.
International conventions and the IAEA safety standards, appropriately
supplemented by industry standards and detailed national requirements, establish
a consistent and comprehensive basis for the proper protection of people and theenvironment from harmful effects of ionizing radiation.
REVISION PROCESS FOR THE INTERNATIONAL BASIC SAFETY
STANDARDS
These Standards reflect continuing efforts over several decades towards
the harmonization of safety standards internationally. The international effort toreview and revise the BSS of 1996 involved hundreds of experts from the member
states of the Sponsoring Organizations and from specialized organizations.
At its meeting in November 2004, the IAEA’s Commission on Safety
Standards requested the IAEA Secretariat to prepare an outline for a possible
review and revision of the BSS of 1996 for presentation at its meeting in
June 2005.
In September 2005, the General Conference of the IAEA, by way ofresolution GC(49)/RES/9A, requested the IAEA Secretariat to undertake a review

of the BSS of 1996. The Inter-Agency Committee for Radiation Safety (IACRS)7
agreed, at its meeting in October 2005, to the establishment of a joint secretariat(hereinafter referred to as the ‘BSS Secretariat’). In December 2005, the IAEA
formally invited representatives of the United Nations and other intergovernmental organizations to jointly coordinate the review and revision of the BSS of1996 through the establishment of the BSS Secretariat. The BSS Secretariat wascoordinated by the IAEA and comprised representatives of the EC, FAO, IAEA,
ICRP, ILO, OECD/NEA, PAHO, UNEP and the WHO.
In September 2006, the Director General of the IAEA reported to the IAEA
General Conference that the review of the BSS of 1996 had concluded that,while there was no major issue necessitating urgent revision, there was a caseto be made for a revision in order to take account of numerous improvementsthat had been suggested. The IAEA General Conference, by way of resolution
GC(50)/RES/10, noted the review of the BSS of 1996 that had been carried out in
response to para. 10 of resolution GC(49)/RES/9, and noted that a revision was
to be coordinated by the BSS Secretariat. Resolution GC(50)/RES/10 also urgedthat the BSS Secretariat carefully consider and justify potential changes, taking
into account their implications for national regulations.
In the fourth quarter of 2006, an outline for the revision of the BSS of 1996
was approved by the four IAEA Safety Standards Committees and was endorsedby the IAEA Commission on Safety Standards. The IAEA Safety Standards
Committees advised the Secretariat that the comprehensive and completecharacter of the BSS of 1996 should be retained in the new edition, whichshould continue to underpin the regulatory infrastructure to control sources andpractices in radiation safety in all areas, including medicine, general industry, thenuclear industry, radioactive waste management and the transport of radioactive
material. They further advised that the new edition should cover the categories ofoccupational exposure, medical exposure and public exposure, and should coverboth normal circumstances of exposure and emergency situations.
The revision of the BSS of 1996 commenced in early 2007 with a seriesof drafting meetings on thematic areas, hosted by the IAEA, ILO, WHO,
OECD/NEA and the PAHO. The draft developed at these meetings provided
the basis for discussions at a technical meeting held in July 2007, with the7
The IACRS provides a forum for the exchange of information between theagencies/organizations on their respective activities related to radiation safety. The IACRS
is composed of members from the EC, FAO, IAEA, ILO, OECD/NEA, PAHO, United
Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) and theWHO. The following non-governmental organizations currently have observer status:International Commission on Radiation Units and Measurements (ICRU), ICRP, International
Electrotechnical Commission, International Radiation Protection Association and International
Organization for Standardization (ISO).

participation of representatives of the Sponsoring Organizations. The technicalmeeting concluded that the new edition of the BSS should follow, to the extent
possible, the new recommendations of the ICRP, including in particular thedesignation of situations of exposure in accordance with ICRP Publication 1038,
i.e. ‘planned exposure situations’, ‘emergency exposure situations’ and ‘existing
exposure situations’.
Further, the technical meeting recommended that the structure of the newedition should be based on the designations of ‘planned exposure situations’,‘emergency exposure situations’ and ‘existing exposure situations’, withcorresponding main sections following a similar layout: occupational exposure,public exposure and (for ‘planned exposure situations’ only) medical exposure.
The technical meeting further recommended that there would also need to be amain section dealing with generic requirements that are applicable in all exposure
situations.
The technical meeting also recommended that the new edition should coverprotection of the environment, to be consistent with the Fundamental Safety
Principles.
The text of this new edition takes into account the findings of UNSCEAR
and also recommendations of the ICRP. The technical meeting noted that sinceboth UNSCEAR and the ICRP had noted that there had been no significant
change in the radiobiology underlying radiation protection in terms of nominal
risk coefficients of dose, the values for dose limits and related quantities in the
new edition would not be changed.
The four IAEA Safety Standards Committees endorsed the decisions madeat the technical meeting regarding the proposed structure of the new edition attheir meetings in late 2007.
In September 2007, the IAEA General Conference, by way of resolution
GC(51)/RES/11, noted the forthcoming publication of the 2007 Recommendationsof the ICRP, and again urged the Secretariat to consider carefully and to justify
any potential changes to the BSS of 1996, while ensuring consistency withICRP recommendations and taking into account the implications for national
regulations and the importance of maintaining stability in international standards.
Further drafting and review meetings with the Sponsoring Organizations
were held from late 2007 to 2009. The IAEA Safety Standards Committees
and groups of experts from some of the Sponsoring Organizations provided
comments on draft texts of the new edition in 2008 and 2009. A further technicalmeeting with the participation of the Sponsoring Organizations was held in
8

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
The 2007 Recommendations of the International Commission on Radiological Protection,
Publication 103, Elsevier (2007).

December 2009 to discuss a statement on radon that was issued by the ICRP in
November 2009, and to assess its implications for the new edition. The technicalmeeting made recommendations on the text for the new edition on exposure due
to radon in dwellings and occupational exposure due to radon.
The draft text of the new edition was submitted for comment to IAEA
Member States on 28 January 2010. Each of the Sponsoring Organizations also
submitted the draft text to its headquarters or to its member states for commentby their respective processes and procedures. More than 1500 comments werereceived from 41 IAEA Member States and from Sponsoring Organizations
by the closing date of 31 May 2010, and these comments were considered in
preparing a revised draft text.
The Nuclear Safety Standards Committee and the Transport Safety
Standards Committee approved the draft text of the new edition at their meetings
in November 2010. The Radiation Safety Standards Committee and the Waste
Safety Standards Committee approved the draft text at their meetings inDecember 2010. The Committees noted that the ICRP was to release a statement
relating to the dose limit for the lens of the eye, which should be taken into
account prior to endorsement by the Commission on Safety Standards of the draft
text of the new edition.
The ICRP, in April 2011, issued a statement on tissue reactions in which it
recommended for occupational exposure a dose limit for equivalent dose to thelens of the eye of 20 mSv in a year, averaged over defined periods of 5 years,
with the dose in no single year exceeding 50 mSv. Previously, this dose limit
had been 150 mSv per year. The Commission on Safety Standards did endorse
the draft text of the new edition at its meeting in May 2011, but requested that
Member States be consulted on the proposed new dose limit for the lens of theeye. Member States were invited to provide comment on the proposed new dose
limit for the lens of the eye by 7 July 2011. Following a recommendation fromthe outgoing and incoming Chairs of the Radiation Safety Standards Committee,
the Chair of the Commission on Safety Standards approved the new dose limit
for the lens of the eye on 12 July 2011.
APPLICATION OF THE INTERNATIONAL BASIC SAFETY STANDARDSIn responding to the Secretariat’s submission to the IAEA Board ofGovernors, GOV/2011/42, the Board, at its meeting on 12 September 2011,
established the draft text in English of the new edition “as an Agency safety
standard — in accordance with Article III.A.6 of the Statute”9 and “authorized
the Director General to promulgate these Safety Requirements…and to issue
9

Statute of the International Atomic Energy Agency, IAEA, Vienna (1990).

them as a Safety Requirements publication in the Safety Standards Series”. The
Board also encouraged Member States “to implement arrangements for meetingthese Safety Requirements”. At its 55th regular session, the IAEA General
Conference, in resolution GC(55)/RES/9, encouraged Member States “to use
safety standards issued by the IAEA in their national regulatory programmes,and noted the need to consider the periodic alignment of national regulations andguidance to internationally established standards and guidance”.
These Standards embody the international benchmark for radiation safety
requirements, with major implications for policy making and decision making.
Their adoption and application will facilitate the application of internationalsafety standards and will make for greater consistency between the arrangementsfor protection and safety of different States. It is, therefore, desirable that all
Member States adopt and apply these requirements. These safety requirements
will be binding on the IAEA in relation to its own operations and they will bebinding on States in relation to operations assisted by the IAEA.
These Standards are also to be applied by the Sponsoring Organizations
to their own operations. They are recommended for use by States and national
authorities and by other international organizations in relation to their own
activities. The application of these Standards by EU member states is ensured by
the implementation of binding Euratom legislation. Other States that are member
states of the other Sponsoring Organizations may adopt the requirements, attheir own discretion, or in accordance with their membership obligations, forapplication to their own activities.
It is recognized that it will take some time to make changes to existing
systems of radiation protection in order to fulfil the requirements fully. The
IAEA Secretariat envisaged that, for the IAEA’s own operations and for those
operations assisted by the IAEA, arrangements needed to be in place to fulfil therequirements within a period of one year from the date of their adoption.
These Standards are intended for application and use by governmental
authorities, including regulatory bodies responsible for authorizing facilities
and activities; by organizations operating nuclear facilities, some mining andraw material processing facilities such as uranium mines, radioactive waste
management facilities, and any other facilities producing or using radiation
sources for industrial, research or medical purposes; by organizations transportingradioactive material; by organizations decommissioning facilities; and by staff
and technical and scientific support organizations supporting such organizations
and authorities.
Member States also subscribe to international conventions relating to
nuclear and radiation related activities conducted within their jurisdiction. The
Convention on Early Notification of a Nuclear Accident, the Convention on
Assistance in the Case of a Nuclear Accident or Radiological Emergency, theConvention on Nuclear Safety, the Joint Convention on the Safety of Spent FuelManagement and on the Safety of Radioactive Waste Management, and the ILO
Convention concerning the Protection of Workers against Ionising Radiations,1960 (No. 115) all place specific obligations on the Contracting Parties. These
Basic Safety Standards and other IAEA safety standards constitute a useful toolfor Contracting Parties to assess their performance under these international
conventions. International conventions and IAEA safety standards, appropriately
supplemented by industry standards and detailed national requirements, establish
a consistent and comprehensive basis for the proper protection of people and theenvironment from harmful effects of ionizing radiation.
These Standards and other IAEA safety standards also support theapplication of the Code of Conduct on the Safety and Security of Radioactive
Sources, the Code of Conduct on the Safety of Research Reactors, and theInternational Health Regulations, an international instrument that is legallybinding on WHO member states.
LEGAL NATURE OF IAEA SAFETY STANDARDSThe statutory basis for the IAEA safety standards is to be found in Article
III.A.6 of the Statute. By virtue of that provision the Agency is authorized:“To establish or adopt, in consultation and, where appropriate, incollaboration with the competent organs of the United Nations and withthe specialized agencies concerned, standards of safety for protection ofhealth and minimization of danger to life and property (including suchstandards for labour conditions), and to provide for the application of thesestandards to its own operations as well as to the operations making use ofmaterials, services, equipment, facilities, and information made available
by the Agency or at its request or under its control or supervision; and toprovide for the application of these standards, at the request of the parties,
to operations under any bilateral or multilateral arrangement, or, at therequest of a State, to any of that State’s activities in the field of atomic
energy.”Pursuant to that authorization, the first step in establishing IAEA safety
standards was taken when the IAEA Board of Governors, on 31 March 1960,
approved the Health and Safety Document: “The Agency’s Safety Standards
and Measures” (INFCIRC/18). Thereafter, various safety standards (e.g. the
BSS and the IAEA Transport Regulations) were established in accordancewith Article III.A.6 and “The Agency’s Safety Standards and Measures”

(INFCIRC/18), which was revised in 1975 and approved by the IAEA Board in
February 1976 (reproduced in INFCIRC/18/Rev.1).
Paragraph 1 of INFCIRC/18/Rev.1 contains the following relevant
definitions:“1.1 “Safety standards” means standards, regulations, rules or codes ofpractice established to protect man and the environment against ionizing
radiation and to minimize danger to life and property.
“1.2 “The Agency’s safety standards” means safety standards establishedby the Agency under the authority of the Board of Governors. Suchstandards comprise:(a) The Agency’s basic safety standards for radiation protection, whichprescribe maximum permissible doses and dose limits;(b) The Agency’s specialized regulations, which are safety prescriptions
relating to particular fields of operation; and(c) The Agency’s codes of practice, which establish for particular activities
the minimum requirements which, in the light of experience and thecurrent state of technology, must be fulfilled to ensure adequate safety.
Codes of practice are, as appropriate, supplemented by safety guides
recommending a procedure or procedures that might be followed in
implementing them.
“1.3 “Safety measure” means any action, condition or procedure to ensure
the observance of safety standards.”
INTERPRETATION OF THE TEXT
A list of definitions that apply for the purposes of these Standards isincluded. The list of definitions includes: definitions of new terms that are notincluded in entries in the IAEA Safety Glossary: Terminology Used in Nuclear
Safety and Radiation Protection (2007 Edition); revised definitions of terms thatare defined in entries in the IAEA Safety Glossary (2007 Edition); and existingterms and their existing definitions from entries in the IAEA Safety Glossary(2007 Edition), included here for ease of reference. The entries for the new terms
and for the revised definitions will be included in the next revision of the IAEA
Safety Glossary and the revised definitions will, thus, supersede the pre-existing
definitions for the purposes of the IAEA safety standards. Further relevant
definitions not included here are provided in the IAEA Safety Glossary. See also:
http://www-ns.iaea.org/standards/safety-glossary.asp

Also included is a CD-ROM containing the IAEA Safety
Glossary (2007 Edition) and the Fundamental Safety Principles(2006), each in Arabic, Chinese, English, French, Russian and Spanish
versions. The CD-ROM is also available for purchase separately. See:
http://www-pub.iaea.org/MTCD/publications/publications.asp
The text of these Standards was developed in drafting and review meetings
and technical meetings which were held in English only. The IAEA Secretariat
made official translations into Arabic, Chinese, French, Russian and Spanishof the draft standard for the purpose of submission of the draft new edition to
the IAEA Board of Governors for approval. The approved text was issued in
November 2011 as a Safety Requirements publication in an Interim Edition in
English only in the IAEA Safety Standards Series. This Interim Edition was
submitted to the other Sponsoring Organizations for their approval. Versionsof the IAEA Secretariat’s official translations of the draft new edition of theseStandards into Arabic, Chinese, French, Russian and Spanish for the IAEA
Board of Governors were included in the Interim Edition on an accompanying
CD-ROM.
The references included herein are to editions that were current as of thetime of establishment of these Standards. Editions that supersede these references
may be adopted under national legislation. In the event that the publications
referenced here are superseded, please refer to the most recent editions. See also:
http://www-ns.iaea.org/standards/
The IAEA Secretariat is to issue this safety standard as a jointly
sponsored IAEA Safety Requirements publication in Arabic, Chinese, French,
Russian and Spanish, as well as in English. Comments and queries on mattersof technical content, terminology and language, and notification of any
apparent errors, omissions or mistranslations, may be submitted by email to
Rad.prot.unit@iaea.org and Safety.Standards@iaea.org, or via the IAEA safety
standards web site, http://www-ns.iaea.org/standards/, for consideration by the
IAEA Secretariat in a future review process.
The IAEA, on behalf of all the Sponsoring Organizations, wishes to express
its sincere appreciation to all those who assisted in the process of reaching
and formulating a consensus, and in the drafting, review and revision of theseStandards.

THE IAEA SAFETY STANDARDSBACKGROUNDRadioactivity is a natural phenomenon and natural sources of radiation arefeatures of the environment. Radiation and radioactive substances have many
beneficial applications, ranging from power generation to uses in medicine,industry and agriculture. The radiation risks to workers and the public and to theenvironment that may arise from these applications have to be assessed and, if
necessary, controlled.
Activities such as the medical uses of radiation, the operation of nuclear
installations, the production, transport and use of radioactive material, and the
management of radioactive waste must therefore be subject to standards of safety.
Regulating safety is a national responsibility. However, radiation risks may
transcend national borders, and international cooperation serves to promote andenhance safety globally by exchanging experience and by improving capabilities
to control hazards, to prevent accidents, to respond to emergencies and to mitigate
any harmful consequences.
States have an obligation of diligence and duty of care, and are expected tofulfil their national and international undertakings and obligations.
International safety standards provide support for States in meeting their
obligations under general principles of international law, such as those relating toenvironmental protection. International safety standards also promote and assure
confidence in safety and facilitate international commerce and trade.
A global nuclear safety regime is in place and is being continuously
improved. IAEA safety standards, which support the implementation of binding
international instruments and national safety infrastructures, are a cornerstoneof this global regime. The IAEA safety standards constitute a useful toolfor contracting parties to assess their performance under these international
conventions.
THE IAEA SAFETY STANDARDSThe status of the IAEA safety standards derives from the IAEA’s Statute,which authorizes the IAEA to establish or adopt, in consultation and, whereappropriate, in collaboration with the competent organs of the United Nations
and with the specialized agencies concerned, standards of safety for protection ofhealth and minimization of danger to life and property, and to provide for theirapplication.

With a view to ensuring the protection of people and the environment
from harmful effects of ionizing radiation, the IAEA safety standards establish
fundamental safety principles, requirements and measures to control the radiation
exposure of people and the release of radioactive material to the environment, torestrict the likelihood of events that might lead to a loss of control over a nuclear
reactor core, nuclear chain reaction, radioactive source or any other source ofradiation, and to mitigate the consequences of such events if they were to occur.
The standards apply to facilities and activities that give rise to radiation risks,
including nuclear installations, the use of radiation and radioactive sources, thetransport of radioactive material and the management of radioactive waste.
Safety measures and security measures1 have in common the aim ofprotecting human life and health and the environment. Safety measures andsecurity measures must be designed and implemented in an integrated mannerso that security measures do not compromise safety and safety measures do notcompromise security.
The IAEA safety standards reflect an international consensus on what
constitutes a high level of safety for protecting people and the environment
from harmful effects of ionizing radiation. They are issued in the IAEA Safety
Standards Series, which has three categories (see Fig. 1).
Safety Fundamentals
Safety Fundamentals present the fundamental safety objective and principles
of protection and safety, and provide the basis for the safety requirements.
Safety Requirements
An integrated and consistent set of Safety Requirements establishes
the requirements that must be met to ensure the protection of people and theenvironment, both now and in the future. The requirements are governed by theobjective and principles of the Safety Fundamentals. If the requirements are notmet, measures must be taken to reach or restore the required level of safety. The
format and style of the requirements facilitate their use for the establishment, in aharmonized manner, of a national regulatory framework. Requirements, including
numbered ‘overarching’ requirements, are expressed as ‘shall’ statements. Manyrequirements are not addressed to a specific party, the implication being that theappropriate parties are responsible for fulfilling them.

1

See also publications issued in the IAEA Nuclear Security Series.

Safety Fundamentals
Fundamental Safety Principles

General Safety Requirements

Specific Safety Requirements

Part 1. Governmental, Legal andRegulatory Framework for Safety

1. Site Evaluation for
Nuclear Installations

Part 2. Leadership and Management
for Safety

2. Safety of Nuclear Power Plants

Part 3. Radiation Protection and
Safety of Radiation Sources

2/1 Design
2/2 Commissioning and Operation

Part 4. Safety Assessment for
Facilities and Activities

3. Safety of Research Reactors

Part 5. Predisposal Managementof Radioactive Waste

4. Safety of Nuclear Fuel
Cycle Facilities

Part 6. Decommissioning andTermination of Activities

5. Safety of Radioactive Waste
Disposal Facilities

Part 7. Emergency Preparedness
and Response

6. Safe Transport ofRadioactive Material

Collection of Safety Guides
FIG. 1. The long term structure of the IAEA Safety Standards Series.

Safety Guides
Safety Guides provide recommendations and guidance on how to comply
with the safety requirements, indicating an international consensus that itis necessary to take the measures recommended (or equivalent alternative
measures). The Safety Guides present international good practices, andincreasingly they reflect best practices, to help users striving to achieve highlevels of safety. The recommendations provided in Safety Guides are expressedas ‘should’ statements.
APPLICATION OF THE IAEA SAFETY STANDARDSThe principal users of safety standards in IAEA Member States are
regulatory bodies and other relevant national authorities. The IAEA safety
standards are also used by co-sponsoring organizations and by many organizations
that design, construct and operate nuclear facilities, as well as organizations
involved in the use of radiation and radioactive sources.

The IAEA safety standards are applicable, as relevant, throughout the entire
lifetime of all facilities and activities — existing and new — utilized for peacefulpurposes and to protective actions to reduce existing radiation risks. They can beused by States as a reference for their national regulations in respect of facilities
and activities.
The IAEA’s Statute makes the safety standards binding on the IAEA in
relation to its own operations and also on States in relation to IAEA assisted
operations.
The IAEA safety standards also form the basis for the IAEA’s safety review
services, and they are used by the IAEA in support of competence building,including the development of educational curricula and training courses.
International conventions contain requirements similar to those in
the IAEA safety standards and make them binding on contracting parties.
The IAEA safety standards, supplemented by international conventions, industry
standards and detailed national requirements, establish a consistent basis forprotecting people and the environment. There will also be some special aspectsof safety that need to be assessed at the national level. For example, many of
the IAEA safety standards, in particular those addressing aspects of safety inplanning or design, are intended to apply primarily to new facilities and activities.
The requirements established in the IAEA safety standards might not be fully
met at some existing facilities that were built to earlier standards. The way inwhich IAEA safety standards are to be applied to such facilities is a decision for
individual States.
The scientific considerations underlying the IAEA safety standards provide
an objective basis for decisions concerning safety; however, decision makers
must also make informed judgements and must determine how best to balance
the benefits of an action or an activity against the associated radiation risks andany other detrimental impacts to which it gives rise.
DEVELOPMENT PROCESS FOR THE IAEA SAFETY STANDARDSThe preparation and review of the safety standards involves the IAEA
Secretariat and four safety standards committees, for nuclear safety (NUSSC),
radiation safety (RASSC), the safety of radioactive waste (WASSC) and thesafe transport of radioactive material (TRANSSC), and a Commission on
Safety Standards (CSS) which oversees the IAEA safety standards programme(see Fig. 2).
All IAEA Member States may nominate experts for the safety standards
committees and may provide comments on draft standards. The membership of
the Commission on Safety Standards is appointed by the Director General andOutline and work plan
prepared by the Secretariat;
review by the safety standards
committees and the CSS

Secretariat andconsultants:
drafting of new or revisionof existing safety standard
Draft

Review bysafety standards
committee(s)DraftMember States
Comments

Final draft

Endorsementby the CSS

FIG. 2. The process for developing a new safety standard or revising an existing standard.

includes senior governmental officials having responsibility for establishingnational standards.
A management system has been established for the processes of planning,developing, reviewing, revising and establishing the IAEA safety standards.
It articulates the mandate of the IAEA, the vision for the future application of
the safety standards, policies and strategies, and corresponding functions andresponsibilities.
INTERACTION WITH OTHER INTERNATIONAL ORGANIZATIONS
The findings of the United Nations Scientific Committee on the Effectsof Atomic Radiation (UNSCEAR) and the recommendations of international
expert bodies, notably the International Commission on Radiological Protection(ICRP), are taken into account in developing the IAEA safety standards. Somesafety standards are developed in cooperation with other bodies in the United
Nations system or other specialized agencies, including the Food and Agriculture
Organization of the United Nations, the United Nations Environment Programme,
the International Labour Organization, the OECD Nuclear Energy Agency, the
Pan American Health Organization and the World Health Organization.
INTERPRETATION OF THE TEXT
Safety related terms are to be understood as defined in the IAEA Safety
Glossary (see http://www-ns.iaea.org/standards/safety-glossary.htm). Otherwise,
words are used with the spellings and meanings assigned to them in the latest
edition of The Concise Oxford Dictionary. For Safety Guides, the English versionof the text is the authoritative version.
The background and context of each standard in the IAEA Safety
Standards Series and its objective, scope and structure are explained in Section 1,
Introduction, of each publication.
Material for which there is no appropriate place in the body text
(e.g. material that is subsidiary to or separate from the body text, is included
in support of statements in the body text, or describes methods of calculation,
procedures or limits and conditions) may be presented in appendices or annexes.
An appendix, if included, is considered to form an integral part of thesafety standard. Material in an appendix has the same status as the body text,
and the IAEA assumes authorship of it. Annexes and footnotes to the main text,
if included, are used to provide practical examples or additional information or
explanation. Annexes and footnotes are not integral parts of the main text. Annex
material published by the IAEA is not necessarily issued under its authorship;
material under other authorship may be presented in annexes to the safety
standards. Extraneous material presented in annexes is excerpted and adapted asnecessary to be generally useful.

CONTENTS
1.

2.

3.

INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1

Background (1.1–1.37) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Objective (1.38). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Scope (1.39–1.46). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Structure (1.47–1.55). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1
14
14
15

GENERAL REQUIREMENTS FOR PROTECTION AND
SAFETY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

18

Definitions (2.1). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Interpretation (2.2). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Resolution of conflicts (2.3–2.5). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Entry into force (2.6–2.7) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Application of the principles of radiation protection (2.8–2.12). . . . . .
Requirement 1: Application of the principles ofradiation protection (2.8–2.12). . . . . . . . . . . . . . . . . . . . . . . . . . . .
Responsibilities of the government (2.13–2.28). . . . . . . . . . . . . . . . . .
Requirement 2: Establishment of a legal and regulatory
framework (2.13–2.28). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Responsibilities of the regulatory body (2.29–2.38). . . . . . . . . . . . . . .
Requirement 3: Responsibilities of the regulatory body
(2.29–2.38). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Responsibilities for protection and safety (2.39–2.46). . . . . . . . . . . . .
Requirement 4: Responsibilities for protection and safety(2.39–2.46). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Management requirements (2.47–2.52). . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 5: Management for protection and safety(2.47–2.52). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

18
18
18
18
19

27

PLANNED EXPOSURE SITUATIONS. . . . . . . . . . . . . . . . . . . . . . . .

29

Scope (3.1–3.4). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Generic requirements (3.5–3.67). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 6: Graded approach (3.6). . . . . . . . . . . . . . . . . . . . . . .
Requirement 7: Notification and authorization (3.7–3.9). . . . . . . . .
Requirement 8: Exemption and clearance (3.10–3.12). . . . . . . . . . .

29
31
31
31
33

19
20
20
23
23
25
25
27

Requirement 9: Responsibilities of registrants andlicensees in planned exposure situations (3.13–3.15). . . . . . . . . . .
Requirement 10: Justification of practices (3.16–3.21). . . . . . . . . . .
Requirement 11: Optimization of protection and safety(3.22–3.25). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 12: Dose limits (3.26–3.28). . . . . . . . . . . . . . . . . . . . .
Requirement 13: Safety assessment (3.29–3.36). . . . . . . . . . . . . . . .
Requirement 14: Monitoring for verification of compliance(3.37–3.38). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 15: Prevention and mitigation of accidents(3.39–3.44). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 16: Investigations and feedback of
information on operating experience (3.45–3.48) . . . . . . . . . . . . .
Requirement 17: Radiation generators and radioactive sources(3.49–3.60). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 18: Human imaging using radiation for
purposes other than medical diagnosis, medical treatment
or biomedical research (3.61–3.67) . . . . . . . . . . . . . . . . . . . . . . . .
Occupational exposure (3.68–3.116). . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 19: Responsibilities of the regulatory bodyspecific to occupational exposure (3.69–3.72). . . . . . . . . . . . . . . .
Requirement 20: Requirements for monitoring andrecording of occupational exposures (3.73). . . . . . . . . . . . . . . . . .
Requirement 21: Responsibilities of employers, registrants andlicensees for the protection of workers (3.74–3.82). . . . . . . . . . . .
Requirement 22: Compliance by workers (3.83–3.84). . . . . . . . . . .
Requirement 23: Cooperation between employers andregistrants and licensees (3.85–3.87). . . . . . . . . . . . . . . . . . . . . . .
Requirement 24: Arrangements under the radiation protection
programme (3.88–3.98) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 25: Assessment of occupational exposure andworkers’ health surveillance (3.99–3.109). . . . . . . . . . . . . . . . . . .
Requirement 26: Information, instruction and training (3.110). . . . .
Requirement 27: Conditions of service (3.111–3.112) . . . . . . . . . . .
Requirement 28: Special arrangements for protection andsafety for female workers and for persons under 18 yearsof age undergoing training (3.113–3.116). . . . . . . . . . . . . . . . . . .
Public exposure (3.117–3.144) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 29: Responsibilities of the government andthe regulatory body specific to public exposure(3.118–3.124). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

33
35
36
37
38
40
41
44
45
47
49
50
50
51
53
54
55
58
61
61
62
63
63

4.

Requirement 30: Responsibilities of relevant parties specific topublic exposure (3.125–3.130). . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 31: Radioactive waste and discharges(3.131–3.134). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 32: Monitoring and reporting (3.135–3.137). . . . . . . .
Requirement 33: Consumer products (3.138–3.144). . . . . . . . . . . . .
Medical exposure (3.145–3.185). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 34: Responsibilities of the government specificto medical exposure (3.147–3.149) . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 35: Responsibilities of the regulatory bodyspecific to medical exposure (3.150) . . . . . . . . . . . . . . . . . . . . . . .
Requirement 36: Responsibilities of registrants and licensees
specific to medical exposure (3.151–3.154). . . . . . . . . . . . . . . . . .
Requirement 37: Justification of medical exposures(3.155–3.161). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 38: Optimization of protection and safety(3.162–3.174). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 39: Pregnant or breast-feeding female patients(3.175–3.177). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 40: Release of patients after radionuclide therapy(3.178). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 41: Unintended and accidental medical exposures(3.179–3.181). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 42: Reviews and records (3.182–3.185). . . . . . . . . . . .

84
85

EMERGENCY EXPOSURE SITUATIONS. . . . . . . . . . . . . . . . . . . . .

87

Scope (4.1). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Generic requirements (4.2–4.6). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 43: Emergency management system (4.2–4.6) . . . . . .
Public exposure (4.7–4.11) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 44: Preparedness and response for an emergency(4.7–4.11). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Exposure of emergency workers (4.12–4.19). . . . . . . . . . . . . . . . . . . .
Requirement 45: Arrangements for controlling the exposure of
emergency workers (4.12–4.19). . . . . . . . . . . . . . . . . . . . . . . . . . .
Transition from an emergency exposure situation to an existing
exposure situation (4.20–4.21). . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 46: Arrangements for the transition froman emergency exposure situation to an existing exposure
situation (4.20–4.21). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

87
87
87
88

65
68
69
71
73
73
74
75
77
78
82
83

88
90
90
92
92

5.

EXISTING EXPOSURE SITUATIONS. . . . . . . . . . . . . . . . . . . . . . . .

92

Scope (5.1). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Generic requirements (5.2–5.5). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 47: Responsibilities of the government specificto existing exposure situations (5.2–5.5) . . . . . . . . . . . . . . . . . . . .
Public exposure (5.6–5.23) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 48: Justification for protective actions andoptimization of protection and safety (5.7–5.9). . . . . . . . . . . . . . .
Requirement 49: Responsibilities for remediation of areas withresidual radioactive material (5.10–5.18). . . . . . . . . . . . . . . . . . . .
Requirement 50: Public exposure due to radon indoors(5.19–5.21). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 51: Exposure due to radionuclides incommodities (5.22–5.23) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Occupational exposure (5.24–5.33). . . . . . . . . . . . . . . . . . . . . . . . . . . .
Requirement 52: Exposure in workplaces (5.25–5.33). . . . . . . . . . .

92
93

101
101
101

SCHEDULE I:EXEMPTION AND CLEARANCE. . . . . . . . . . . . . . . . .

105

SCHEDULE II:

CATEGORIES FOR SEALED SOURCES USEDIN COMMON PRACTICES . . . . . . . . . . . . . . . . . . . . . .

129

SCHEDULE III: DOSE LIMITS FOR PLANNED EXPOSURESITUATIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

132

SCHEDULE IV: CRITERIA FOR USE IN EMERGENCY
PREPAREDNESS AND RESPONSE . . . . . . . . . . . . . . .

371

REFERENCES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

375

ANNEX: GENERIC CRITERIA FOR PROTECTIVE ACTIONSAND OTHER RESPONSE ACTIONS TO REDUCE
THE RISK OF STOCHASTIC EFFECTS . . . . . . . . . . . . . . . . . .

379

DEFINITIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
CONTRIBUTORS TO DRAFTING AND REVIEW. . . . . . . . . . . . . . . . . . .

381
427

93
95
95
96
99

1. INTRODUCTIONBACKGROUND
1.1. This General Safety Requirements publication, IAEA Safety Standards
Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources:
International Basic Safety Standards (hereinafter referred to as ‘these Standards’),is issued in the IAEA Safety Standards Series. It supersedes International Basic
Safety Standards for Protection against Ionizing Radiation and for the Safetyof Radiation Sources issued in 1996 (the ‘BSS of 1996’)1. Section 1 does notinclude requirements, but explains the context, concepts and principles for therequirements, which are established in Sections 2–5 and in the schedules.
1.2. Radioactivity is a natural phenomenon and natural sources of radiation
are features of the environment. Radiation2 and radioactive material may also
be of artificial origin and they have many beneficial applications, including
uses in medicine, industry, agriculture and research as well as for nuclear power
generation. The radiation risks to people and the environment that may arise
from the use of radiation and radioactive material must be assessed and must be
controlled by means of the application of standards of safety3.
1.3. Exposure of human tissues or organs to radiation can induce the death ofcells on a scale that can be extensive enough to impair the function of the exposed
tissue or organ. Effects of this type, which are called ‘deterministic effects’, areclinically observable in an individual only if the radiation dose exceeds a certain
threshold level. Above this threshold level of dose, a deterministic effect is more
severe for a higher dose.

1
FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS,INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOURORGANISATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTHORGANIZATION, WORLD HEALTH ORGANIZATION, International Basic Safety
Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources,
IAEA Safety Series No. 115, IAEA, Vienna (1996).
2
The term ‘radiation’ in the context of these Standards means ionizing radiation.
3
Obligations expressed as ‘must’ statements in Section 1 are quoted from theFundamental Safety Principles [1].

1

1.4. Exposure to radiation can also induce the non-lethal transformation of cells,
which may still retain their capacity for cell division. The human body’s immune
system is very effective at detecting and destroying abnormal cells. However,there is a possibility that the non-lethal transformation of a cell could lead, aftera latency period, to cancer in the individual exposed, if the cell is a somaticcell; or such a transformation of a cell could lead to hereditary effects, if thecell is a germ cell. Such effects are called ‘stochastic’ effects. For the purposesof these Standards, it is assumed that the probability of the eventual occurrenceof a stochastic effect is proportional to the dose received, with no threshold.
The ‘detriment-adjusted nominal risk coefficient of dose’, which includes therisks of all cancers and the risks of hereditary effects, is 5% per sievert [2]. Thisrisk coefficient may need to be adjusted as new scientific knowledge becomes
available.
1.5. The requirements established in these Standards are governed by theobjectives, concepts and principles of the Fundamental Safety Principles [1].
These Standards draw upon information derived from the experience of Statesin applying the requirements of the BSS of 19964, and from experience in many
States in the use of radiation and nuclear techniques. These Standards draw upon
extensive research and development work by national and international scientificand engineering organizations on the health effects of radiation exposure and on
measures and techniques for the safe design and use of radiation sources. These
Standards also take account of the findings of the United Nations ScientificCommittee on the Effects of Atomic Radiation (UNSCEAR) [3] and the
Recommendations of the International Commission on Radiological Protection(ICRP) [2]. As scientific considerations are only part of the basis for making
decisions on protection and safety, these Standards also address the use of value
judgements relating to the management of risks.
The system of protection and safety
1.6. As stated in the Fundamental Safety Principles [1], “The fundamental
safety objective is to protect people and the environment from harmful effects ofionizing radiation.” This objective must be achieved without unduly limiting the4

FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS,INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOURORGANISATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTHORGANIZATION, WORLD HEALTH ORGANIZATION, International Basic Safety
Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources,
IAEA Safety Series No. 115, IAEA, Vienna (1996).

2

operation of facilities or the conduct of activities that give rise to radiation risks5.
Therefore, the system of protection and safety aims to assess, manage and control
exposure to radiation so that radiation risks, including risks of health effects andrisks to the environment, are reduced to the extent reasonably achievable.
1.7. These Standards are based on the following safety principles stated in theFundamental Safety Principles [1]:Principle 1:

Responsibility for safety

The prime responsibility for safety must rest with the person or organization
responsible for facilities and activities that give rise to radiation risks.
Principle 2:

Role of government

An effective legal and governmental framework for safety, including an
independent regulatory body, must be established and sustained.
Principle 3:

Leadership and management for safety

Effective leadership and management for safety must be established andsustained in organizations concerned with, and facilities and activities thatgive rise to, radiation risks.
Principle 4:

Justification of facilities and activities

Facilities and activities that give rise to radiation risks must yield an overall
benefit.

5

The term ‘radiation risks’ is used in a general sense to refer to:——Detrimental health effects of radiation exposure (including the likelihood of such
effects occurring).
——Any other safety related risks (including those to the environment) that might arise
as a direct consequence of:yy Exposure to radiation;
yy The presence of radioactive material (including radioactive waste) or its release to
the environment;
yy A loss of control over a nuclear reactor core, nuclear chain reaction, radioactive
source or any other source of radiation.

3

Principle 5:

Optimization of protection

Protection must be optimized to provide the highest level of safety that canreasonably be achieved.
Principle 6:

Limitation of risks to individuals

Measures for controlling radiation risks must ensure that no individual
bears an unacceptable risk of harm.
Principle 7:

Protection of present and future generations

People and the environment, present and future, must be protected against
radiation risks.
Principle 8:

Prevention of accidents

All practical efforts must be made to prevent and mitigate nuclear orradiation accidents.
Principle 9:

Emergency preparedness and response

Arrangements must be made for emergency preparedness and response fornuclear or radiation incidents.
Principle 10: Protective actions to reduce existing or unregulated radiation risks
Protective actions to reduce existing or unregulated radiation risks must be
justified and optimized.
The three general principles of radiation protection, which concern justification,
optimization of protection and application of dose limits, are expressed in Safety
Principles 4, 5, 6 and also 10 [1].

4

1.8. The prime responsibility for safety must rest with the person or organization
responsible for facilities and activities6 that give rise to radiation risks [1]. Other
parties also bear certain responsibilities. For instance, suppliers of radiation
generators and radioactive sources have responsibilities in relation to theirdesign and manufacture and operating instructions for their safe use. In the caseof medical exposures, because of the medical setting in which such exposuresoccur, primary responsibility for protection and safety for patients lies with thehealth professional responsible for administration of the radiation dose, who isreferred to in these Standards as the ‘radiological medical practitioner’. Other
types of health professional may be involved in the preparation for, and the
conduct of, radiological procedures, and each type has specific responsibilities,
as established in these Standards.
1.9. A properly established governmental, legal and regulatory frameworkfor safety provides for the regulation of facilities and activities that give rise toradiation risks. There is a hierarchy of responsibilities within this framework,from governments to regulatory bodies to the organizations responsible for, andthe persons engaged in, activities involving radiation exposure. The governmentis responsible for the adoption within its national legal system of such legislation,
regulations, and standards and measures as may be necessary to fulfil all its
national and international obligations effectively, and for the establishment of
an independent regulatory body. In some cases, more than one governmentalorganization may have the functions of a regulatory body for activities within
their jurisdictions relating to the control of radiation and radioactive material.
1.10. Both the government and the regulatory body have important
responsibilities in establishing the regulatory framework for protecting people
and the environment from harmful effects of radiation, including establishingstandards. These Standards require the government to ensure that there iscoordination of government departments and agencies that have responsibilities
6

The term ‘facilities and activities’ is a general term encompassing any human activity
that may cause people to be exposed to radiation risks arising from naturally occurring or
artificial sources. The term ‘facilities’ includes: nuclear facilities; irradiation installations;some mining and raw material processing facilities such as uranium mines; radioactive waste
management facilities; and any other places where radioactive material is produced, processed,
used, handled, stored or disposed of — or where radiation generators are installed — on sucha scale that consideration of protection and safety is required. The term ‘activities’ includes:
the production, use, import and export of radiation sources for industrial, research and medical
purposes; the transport of radioactive material; the decommissioning of facilities; radioactive
waste management activities such as the discharge of effluents; and some aspects of theremediation of sites affected by residues from past activities.

5

for protection and safety, including the regulatory body, and of departments andagencies concerned with public health, the environment, labour, mining, scienceand technology, agriculture and education. Standards have to be developed bymeans of consultation with those who are or who could be required to apply them.
1.11. The government is also responsible for ensuring, as necessary, that provision
is made for support services, such as education and training, and technicalservices. If these services are not available within the State, other mechanisms
to provide them may have to be considered. The regulatory body is responsible
for carrying out its required regulatory functions, such as the establishment of
requirements and guidelines, the authorization and inspection of facilities andactivities, and the enforcement of legislative and regulatory provisions.
1.12. Leadership in safety matters has to be demonstrated at the highest levels
in an organization, and safety has to be achieved and maintained by means ofan effective management system. This system has to integrate all elements ofmanagement so that requirements for protection and safety are established andapplied coherently with other requirements, including those for health, humanperformance, quality, protection of the environment and security, together
with economic considerations. The application of the management system also
has to ensure the promotion of safety culture, the regular assessment of safety
performance and the application of lessons learned from experience. Safety
culture includes individual and collective commitment to safety on the part of theleadership, the management and personnel at all levels. The term ‘management
system’ reflects and includes the concept of ‘quality control’ (controlling thequality of products) and its evolution through ‘quality assurance’ (the system forensuring the quality of products) and ‘quality management system’ (the system
for managing quality).
1.13. The operation of facilities or the conduct of activities that introduce a
new source of radiation, that change exposures or that change the likelihood of
exposures has to be justified in the sense that the detriments that may be caused
are outweighed by the individual and societal benefits that are expected. The
comparison of detriments and benefits often goes beyond the consideration ofprotection and safety, and involves the consideration of economic, societal andenvironmental factors also.
1.14. The application of the justification principle to medical exposures requires
a special approach. As an overarching justification of medical exposures, it isaccepted that the use of radiation in medicine does more good than harm.
However, at the next level, there is a need for generic justification, to be carried
6

out by the health authority in conjunction with appropriate professional bodies,of a given radiological procedure. This applies to the justification of newtechnologies and techniques as they evolve. For the final level of justification,
the application of the radiological procedure to a given individual has to beconsidered. The specific objectives of the exposure, the clinical circumstances
and the characteristics of the individual involved have to be taken into accountby means of referral guidelines developed by professional bodies and the healthauthority.
1.15. The optimization of protection and safety, when applied to the exposureof workers and members of the public, and carers and comforters of patients
undergoing radiological procedures, is a process for ensuring that the likelihood
and magnitude of exposures and the number of individuals exposed are as low asreasonably achievable, with economic, societal and environmental factors taken
into account. This means that the level of protection would be the best possible
under the prevailing circumstances. Optimization is a prospective and iterative
process that requires both qualitative and quantitative judgements to be made.
1.16. As is the case with justification, the application of the optimization
principle to the medical exposure of patients, and to that of volunteers as partof a programme of biomedical research, requires a special approach. Too low aradiation dose could be as bad as too high a radiation dose, in that the consequence
could be that a cancer is not cured or the images obtained are not of suitablediagnostic quality. It is of paramount importance that the medical exposure leads
to the required outcome.
1.17. For planned exposure situations, exposures and risks are subject to control
to ensure that the specified dose limits for occupational exposure and those forpublic exposure are not exceeded, and optimization is applied to attain the desired
level of protection and safety.
1.18. All practical efforts must be made to prevent and mitigate nuclear orradiological accidents. The most harmful consequences arising from facilities andactivities have come from the loss of control over a nuclear reactor core, nuclear
chain reaction, radioactive source or other source of radiation. Consequently,
to ensure that the likelihood of an accident having harmful consequences is
extremely low, measures have to be taken:—— To prevent the occurrence of failures or abnormal conditions (including
breaches of security) that could lead to such a loss of control;

7

—— To prevent the escalation of any such failures or abnormal conditions that
do occur;—— To prevent the loss of, or the loss of control over, a radioactive source orother source of radiation.
1.19. Arrangements must be made for emergency preparedness and response fornuclear or radiological incidents. The primary goals of preparedness and response
for a nuclear or radiological emergency are:—— To ensure that arrangements are in place for an effective response at thescene and, as appropriate, at the local, regional, national and international
levels, to a nuclear or radiation emergency;—— To ensure that, for reasonably foreseeable incidents, radiation risks would
be minor;—— For any incidents that do occur, to take practical measures to mitigate any
consequences for human life and health and the environment.
Types of exposure situation
1.20. For the purpose of establishing practical requirements for protection andsafety, these Standards distinguish between three different types of exposure
situation: planned exposure situations, emergency exposure situations andexisting exposure situations [2]. Together, these three types of exposure situation
cover all situations of exposure for which these Standards apply:
(a)

(b)

8

A planned exposure situation is a situation of exposure that arises from theplanned operation of a source or from a planned activity that results in an
exposure due to a source. Since provision for protection and safety can bemade before embarking on the activity concerned, the associated exposuresand their likelihood of occurrence can be restricted from the outset. The
primary means of controlling exposure in planned exposure situations isby good design of facilities, equipment and operating procedures, and bytraining. In planned exposure situations, exposure at some level can be
expected to occur. If exposure is not expected to occur with certainty, but
could result from an accident or from an event or a sequence of events
that may occur but is not certain to occur, this is referred to as ‘potential
exposure’.
An emergency exposure situation is a situation of exposure that arises asa result of an accident, a malicious act or any other unexpected event, andrequires prompt action in order to avoid or to reduce adverse consequences.
Preventive measures and mitigatory actions have to be considered before

(c)an emergency exposure situation arises. However, once an emergency
exposure situation actually arises, exposures can be reduced only byimplementing protective actions.
An existing exposure situation is a situation of exposure that already exists
when a decision on the need for control needs to be taken. Existing exposure
situations include situations of exposure to natural background radiation.
They also include situations of exposure due to residual radioactive material
that derives from past practices that were not subject to regulatory control
or that remains after an emergency exposure situation.

If an event or a sequence of events that has been considered in the assessmentof potential exposure does actually occur, it may be treated either as a planned
exposure situation or, if an emergency has been declared, as an emergency
exposure situation.
1.21. The descriptions that are given in para. 1.20 of the three types of exposure
situation are not always sufficient to determine unequivocally which typeof exposure situation applies for particular circumstances. For instance, thetransitions from an emergency exposure situation to an existing exposure
situation may occur progressively over time; and some exposures due to natural
sources may have some characteristics of both planned exposure situations andexisting exposure situations. In these Standards, the most appropriate type of
exposure situation for particular circumstances has been determined by taking
practical considerations into account. For the purposes of these Standards, theexposure of aircrew to cosmic radiation is considered under existing exposure
situations in Section 5. The exposure of space crew to cosmic radiation presents
exceptional circumstances and these are considered separately in Section 5.
Dose constraints and reference levels
1.22. Dose constraints and reference levels are used for optimization ofprotection and safety, the intended outcome of which is that all exposures arecontrolled to levels that are as low as reasonably achievable, economic, societal
and environmental factors being taken into account. Dose constraints are applied
to occupational exposure and to public exposure in planned exposure situations.
Dose constraints are set separately for each source under control and they
serve as boundary conditions in defining the range of options for the purposesof optimization of protection and safety. Dose constraints are not dose limits:
exceeding a dose constraint does not represent non-compliance with regulatory
requirements, but it could result in follow-up actions.

9

1.23. While the objectives of the use of dose constraints for controlling
occupational exposure and public exposure are similar, the dose constraints
are applied in different ways. For occupational exposure, the dose constraint isa tool to be established and used in the optimization of protection and safety
by the person or organization responsible for a facility or an activity. For public
exposure in planned exposure situations, the government or the regulatory bodyensures the establishment or approval of dose constraints, taking into accountthe characteristics of the site and of the facility or activity, the scenarios for
exposure and the views of interested parties. After exposures have occurred, thedose constraint may be used as a benchmark for assessing the suitability of the
optimized strategy for protection and safety (referred to as the protection strategy)
that has been implemented and for making adjustments as necessary. The settingof the dose constraint needs to be considered in conjunction with other health andsafety provisions and the technology available.
1.24. Reference levels are used for optimization of protection and safety inemergency exposure situations and in existing exposure situations. They are
established or approved by the government, the regulatory body or anotherrelevant authority. For occupational exposure and public exposure in emergency
exposure situations and in existing exposure situations, a reference level serves
as a boundary condition in identifying the range of options for the purposes of
optimization in implementing protective actions. The reference level represents
the level of dose or the level of risk above which it is judged to be inappropriate toplan to allow exposures to occur, and below which the optimization of protection
and safety is implemented. The value chosen for the reference level will dependon the prevailing circumstances for the exposures under consideration. The
optimized protection strategies are intended to keep doses below the reference
level. When an emergency exposure situation has arisen or an existing exposure
situation has been identified, actual exposures could be above or below thereference level. The reference level would be used as a benchmark for judging
whether further protective actions are necessary and, if so, in prioritizing theirapplication. Optimization of protection and safety is to be applied in emergency
exposure situations and in existing exposure situations, even if the doses initially
received are below the reference level.
1.25. The ICRP recommends a range of doses spanning two orders of magnitude
within which the value of a dose constraint or reference level would usually bechosen [2]. At the lower end of this range, the dose constraint or reference level
represents an increase, of up to about 1 mSv, over the dose received in a year10

from exposure due to naturally occurring radiation sources7. It would be used
when individuals are exposed to radiation from a source that yields little or nobenefit for them, but which may benefit society in general. This would be thecase, for instance, in establishing dose constraints for public exposure in planned
exposure situations.
1.26. Dose constraints or reference levels of 1–20 mSv would be used whenthe exposure situation — but not necessarily the exposure itself — usually
benefits individuals. This would be the case, for instance, when establishing dose
constraints for occupational exposure in planned exposure situations or reference
levels for exposure of a member of the public in existing exposure situations.
1.27. Reference levels of 20–100 mSv would be used where individuals are
exposed to radiation from sources that are not under control or where actions
to reduce doses would be disproportionately disruptive. This would be the case,for instance, in establishing reference levels for the residual dose after a nuclear
or radiological emergency. Any situation that resulted in a dose of greater than
100 mSv being incurred within a short period of time or in one year would beconsidered unacceptable, except under the circumstances relating to exposure of
emergency workers that are addressed specifically in these Standards.
1.28. The selection of the value for the dose constraint or the reference level
would be based on the characteristics of the exposure situation, including:—— The nature of the exposure and the practicability of reducing or preventing
the exposure;—— The expected benefits of the exposure for individuals and society, or the
benefits of avoiding preventive measures or protective actions that would
be detrimental to living conditions, as well as other societal criteria relating
to the management of the exposure situation;—— National or regional factors, together with a consideration of international
guidance and good practice elsewhere.
1.29. The system of protection and safety required by these Standards includes
criteria for protection against exposure due to radon that are based on the average
7

According to UNSCEAR [4], the worldwide average annual radiation dose fromexposure due to naturally occurring radiation sources, including radon, is 2.4 mSv. In any
large population, about 65% would be expected to have annual doses of between 1 and 3 mSv.
About 25% of the population would be expected to have annual doses of less than 1 mSv, andabout 10% would be expected to have annual doses greater than 3 mSv.

11

level of risk to a population with typical but various smoking habits. Owing to
the synergistic effects of smoking and exposure due to radon, the absolute riskof lung cancer resulting from unit dose from exposure due to radon for people
who are smokers is substantially greater than for those who have never smoked[3, 5, 6]. Information provided to people on the risks associated with exposuredue to radon needs to highlight this increased risk for smokers.
1.30. Dose constraints are used in optimization of protection and safety for carers
and comforters and for volunteers subject to exposure as part of a programmeof biomedical research. Dose constraints are not applicable to the exposure ofpatients in radiological procedures for the purposes of medical diagnosis ortreatment.
1.31. In X ray medical imaging, image guided interventional procedures anddiagnostic nuclear medicine, a diagnostic reference level is used to indicate
the need for an investigation. Periodic assessments are performed of typicaldoses or activity of the radiopharmaceuticals administered in a medical facility.
If comparison with established diagnostic reference levels shows that the typicaldoses or activity of the radiopharmaceuticals administered are either too high or
unusually low, a local review is to be initiated to ascertain whether protection andsafety has been optimized and whether any corrective action is required.
Protection of the environment
1.32. In a global and long term perspective, protection of people and theenvironment against radiation risks associated with the operation of facilities andthe conduct of activities — and in particular, protection against such risks that
may transcend national borders and may persist for long periods of time — isimportant for achieving equitable and sustainable development.
1.33. The system of protection and safety required by these Standards generally
provides for appropriate protection of the environment from harmful effectsof radiation. Nevertheless, international trends in this field show an increasingawareness of the vulnerability of the environment. Trends also indicate the need
to be able to demonstrate (rather than to assume) that the environment is being
protected against effects of industrial pollutants, including radionuclides, in a
wider range of environmental situations, irrespective of any human connection.
This is usually accomplished by means of a prospective environmental
assessment to identify impacts on the environment, to define the appropriate
criteria for protection of the environment, to assess the impacts and to compare12the expected results of the available options for protection. Methods and criteria
for such assessments are being developed and will continue to evolve.
1.34. Radiological impacts in a particular environment constitute only one typeof impact and, in most cases, may not be the dominant impacts of a particularfacility or activity. Furthermore, the assessment of impacts on the environment
needs to be viewed in an integrated manner with other features of the systemof protection and safety to establish the requirements applicable to a particularsource. Since there are complex interrelations, the approach to the protection ofpeople and the environment is not limited to the prevention of radiological effects
on humans and on other species. When establishing regulations, an integrated
perspective has to be adopted to ensure the sustainability, now and in the future,of agriculture, forestry, fisheries and tourism, and of the use of natural resources.
Such an integrated perspective also has to take into account the need to prevent
unauthorized acts with potential consequences for and via the environment,
including, for example, the illicit dumping of radioactive material and theabandonment of radiation sources. Consideration also needs to be given to thepotential for buildup and accumulation of long lived radionuclides released to theenvironment.
1.35. These Standards are designed to identify the protection of the environment
as an issue necessitating assessment, while allowing for flexibility in incorporating
into decision making processes the results of environmental assessments that arecommensurate with the radiation risks.
Interfaces between safety and security
1.36. Safety measures and security measures have in common the aim ofprotecting human life and health and the environment. In addition, safetymeasures and security measures must be designed and implemented in an
integrated manner, so that security measures do not compromise safety and safetymeasures do not compromise security.
1.37. Security infrastructure and safety infrastructure need to be developed, as
far as possible, in a well coordinated manner. All the organizations involved need
to be made aware of the commonalities and the differences between safety andsecurity so as to be able to factor both into development plans. The synergies
between safety and security have to be developed so that safety and security
complement and enhance one another.

13

OBJECTIVE
1.38. These Standards establish requirements for the protection of people andthe environment from harmful effects of ionizing radiation and for the safety ofradiation sources.
SCOPE
1.39. These Standards apply for protection against ionizing radiation only,
which includes gamma rays, X rays and particles such as beta particles,
neutrons, protons, alpha particles and heavier ions. While these Standards do
not specifically address the control of non-radiological aspects of health, safety
and the environment, these aspects also need to be considered. Protection fromharmful effects of non-ionizing radiation is outside the scope of these Standards.
1.40. These Standards are intended primarily for use by governments andregulatory bodies. Requirements also apply to principal parties and other parties
as specified in Section 2, health authorities, professional bodies and service
providers such as technical support organizations.
1.41. These Standards do not deal with security measures. The IAEA issues
recommendations on nuclear security in the IAEA Nuclear Security Series.
1.42. These Standards apply to all situations involving radiation exposure thatis amenable to control. Exposures deemed to be not amenable to control are
excluded from the scope of these Standards.8
1.43. These Standards establish requirements to be fulfilled in all facilities andactivities giving rise to radiation risks. For certain facilities and activities, suchas nuclear installations, radioactive waste management facilities and the transportof radioactive material, other safety requirements, complementary to theseStandards, also apply. The IAEA issues Safety Guides to assist in the applicationof these Standards.
1.44. These Standards apply to three categories of exposure: occupational
exposure, public exposure and medical exposure.

8

It is generally accepted, for example, that it is not feasible to control 40K in the bodyor cosmic radiation at the surface of the Earth.

14

1.45. These Standards apply to human activities involving radiation exposurethat are:—— Carried out in a State which decides to adopt these Standards or which
requests any of the Sponsoring Organizations to provide for the applicationof these Standards;—— Undertaken by States with the assistance of the Food and Agriculture
Organization of the United Nations, the IAEA, the International Labour
Organization, the Pan American Health Organization, the United Nations
Environment Programme or the World Health Organization, in the light ofrelevant national rules and regulations;—— Carried out by the IAEA or involving the use of materials, services,
equipment, facilities and non-published information made available by the
IAEA or at its request or under its control or supervision; or—— Carried out under any bilateral or multilateral arrangement whereby theparties request the IAEA to provide for the application of these Standards.
1.46. Quantities and units used in these Standards are in accordance with therecommendations of the International Commission on Radiation Units andMeasurements [7].
STRUCTURE
1.47. The requirements of these Standards are grouped into requirements
applicable for all exposure situations and separate sets of requirements forplanned exposure situations, emergency exposure situations and existing exposure
situations. For each of the three types of exposure situation, the requirements arefurther grouped into requirements for occupational exposure, public exposureand (for planned exposure situations only) medical exposure.
1.48. The requirements established by these Standards, both numbered‘overarching’ requirements in bold with titles and other requirements, areexpressed as ‘shall’ statements. Each individual overarching requirement isfollowed by associated requirements.
1.49. Section 2 sets out the requirements that apply generally for all exposure
situations and for all of the three categories of exposure (occupational
exposure, public exposure and medical exposure). These requirements include
the assignment of responsibilities to the government, the regulatory body,and principal parties and other parties with respect to the implementation of a15

protection and safety programme and a management system, the promotion ofsafety culture and the consideration of human factors.
1.50. Section 3 sets out the requirements — in addition to those of Section 2 —for planned exposure situations. Section 3 includes requirements applicable to all
three categories of exposure, requirements for the safety of sources, and separate
sets of requirements in respect of occupational exposure, public exposure andmedical exposure.
1.51. Section 4 sets out the requirements — in addition to those of Section 2 —for emergency exposure situations. Section 4 includes requirements in respect ofpublic exposure and occupational exposure (i.e. exposure of emergency workers)in emergency exposure situations. It also includes requirements on the transitions
from an emergency exposure situation to an existing exposure situation.
1.52. Section 5 sets out the requirements — in addition to those of Section 2 —for existing exposure situations. Section 5 includes requirements in respect ofpublic exposure and occupational exposure in existing exposure situations.
It includes requirements in respect of remediation of sites and habitation inareas with residual radioactive material, radon in homes and in workplaces,
radionuclides in commodities, and exposure of aircrew and of space crew.
1.53. The organization of the requirements in these Standards for the relevant
categories of exposure in each type of exposure situation is as shown in
Table 1. General requirements for all exposure situations are given in Section 2,
and requirements for different exposure situations are given in Sections 3–5.
Thus, for any particular facility or activity, more than one section of theseStandards will be relevant, as illustrated by the following examples:(a)16

The requirements for the regulatory body given in Section 2 are applicablefor all exposure situations and all categories of exposure. They provide theregulatory framework within which persons or organizations responsible
for facilities and activities have to comply with requirements placedon them. These requirements, thus, establish the general regulatory
responsibilities of the regulatory body. Any further requirements on
the regulatory body that apply for one type of exposure situation are
given in Sections 3–5. These further requirements are in addition to therequirements given in Section 2.

TABLE 1. ORGANIZATION OF THE REQUIREMENTS OF THESE
STANDARDS
Occupational exposure
Plannedexposuresituations

Public exposure

Medical exposure

Section 2;
Section 2;
Section 2;
Section 3: paras 3.5–3.67 Section 3: paras 3.5–3.67 Section 3: paras 3.5–3.67
and paras 3.68–3.116
and paras 3.117–3.144
and paras 3.145–3.185

Emergency
Section 2;
exposure
Section 4
situations

Section 2;
Section 4

Not applicable

Existing
exposuresituations

Section 2;
Section 5

Not applicable(b)

Section 2;
Section 5

Persons or organizations responsible for a medical facility in which radiation
generators or radioactive sources are used are subject to the requirements
given in Section 2 for all exposure situations and all categories of exposure,and also to those requirements given in Section 3 that are common to allplanned exposure situations (paras 3.5–3.67). In addition, such persons ororganizations are subject to the separate requirements given in Section 3 foroccupational exposure (such as exposure of medical staff operating medical
devices that emit radiation) (paras 3.68–3.116), public exposure (such as
exposure in rooms adjacent to rooms containing equipment that generates
radiation) (paras 3.117–3.144) and medical exposure (such as exposure ofpatients) (paras 3.145–3.185).

1.54. Schedules I–IV provide numerical values in support of the requirements,
covering exemption and clearance, categorization of sealed sources, dose limits
for planned exposure situations and criteria for use in emergency preparedness
and response.
1.55. Definitions of terms used are included in these Standards.

17

2. GENERAL REQUIREMENTS FOR PROTECTION
AND SAFETY
DEFINITIONS
2.1. Terms used have the meanings given under Definitions.
INTERPRETATION
2.2. Except as specifically authorized by the statutory governing body of aSponsoring Organization, no interpretation of these Standards by any officer
or employee of the Sponsoring Organization other than a written interpretationby the Director General of the Sponsoring Organization will be binding on theSponsoring Organization.
RESOLUTION OF CONFLICTS
2.3. The requirements of these Standards are in addition to and not in place ofother applicable requirements, such as those of relevant binding conventions andnational laws and regulations.
2.4. In cases of conflict between the requirements of these Standards and otherapplicable requirements, the government or the regulatory body, as appropriate,shall determine which requirements are to be enforced.
2.5. Nothing in these Standards shall be construed as restricting any actions that
may otherwise be necessary for protection and safety or as relieving the parties
referred to in paras 2.40 and 2.41 from complying with applicable laws andregulations.
ENTRY INTO FORCE
2.6. These Standards shall enter into force one year after the date of theiradoption or acknowledgement, as appropriate, by the Sponsoring Organization.

18

2.7. If a State decides to adopt these Standards, these Standards shall come into
force at the time indicated in the formal adoption by that State.
APPLICATION OF THE PRINCIPLES OF RADIATION PROTECTION
Requirement 1: Application of the principles of radiation protection
Parties with responsibilities for protection and safety shall ensure that the
principles of radiation protection are applied for all exposure situations.
2.8. For planned exposure situations, each party with responsibilities forprotection and safety shall ensure, when relevant requirements apply to thatparty, that no practice is undertaken unless it is justified.
2.9. For emergency exposure situations and existing exposure situations, eachparty with responsibilities for protection and safety shall ensure, when relevant
requirements apply to that party, that protective actions or remedial actions are
justified and are undertaken in such a way as to achieve the objectives set out ina protection strategy.
2.10. For all exposure situations, each party with responsibilities for protection
and safety shall ensure, when relevant requirements apply to that party, that
protection and safety is optimized9.
2.11. For planned exposure situations other than for medical exposure, each party
with responsibilities for protection and safety shall ensure that, when relevant
requirements apply to that party, specified dose limits are not exceeded.
2.12. The application of the requirements for the system of protection and safety
shall be commensurate with the radiation risks associated with the exposure
situation.

9‘Protection and safety is optimized’ means that optimization of protection and safety
has been applied and the result of that process has been implemented.

19

RESPONSIBILITIES OF THE GOVERNMENT10
Requirement 2: Establishment of a legal and regulatory framework
The government shall establish and maintain a legal and regulatory
framework for protection and safety and shall establish an effectively
independent regulatory body with specified responsibilities and functions.
2.13. The government shall establish and maintain an appropriate and effective
legal and regulatory framework for protection and safety in all exposure
situations.11 This framework shall encompass both the assignment and thedischarge of governmental responsibilities, and the regulatory control of facilities
and activities that give rise to radiation risks. The framework shall allow for thefulfilment of international obligations.
2.14. The government shall ensure that adequate arrangements are in place forthe protection of people and the environment, both now and in the future, against
harmful effects of ionizing radiation, without unduly limiting the operationof facilities or the conduct of activities that give rise to radiation risks. This
shall include arrangements for the protection of people of present and future
generations and populations remote from present facilities and activities.
2.15. The government shall establish legislation that, among other things:
(a)
(b)
(c)
(d)
(e)

Provides the statutory basis for requirements for protection and safety for
all exposure situations;
Specifies that the prime responsibility for protection and safety rests withthe person or organization responsible for facilities and activities that giverise to radiation risks;Specifies the scope of its applicability;
Establishes and provides for maintaining an independent regulatory bodywith clearly specified functions and responsibilities for the regulation ofprotection and safety;
Provides for coordination between authorities with responsibilities relevant
to protection and safety for all exposure situations.
10States have different legal structures, and, therefore, the term ‘government’ as
used in the IAEA safety standards is to be understood in a broad sense, and is accordinglyinterchangeable here with the term ‘State’.
11
Requirements on the governmental, legal and regulatory framework for safety offacilities and activities are established in Ref. [8].

20

2.16. The government shall ensure that the regulatory body is effectively
independent, in making decisions relating to protection and safety, of persons
and organizations using or promoting the use of radiation and radioactive
material, so that it is free from any undue influence by interested parties andfrom any conflicts of interest; and shall ensure that it has functional separationfrom entities having responsibilities or interests that could unduly influence its
decision making.
2.17. The government shall ensure that the regulatory body has the legal
authority, competence and resources necessary to fulfil its statutory functions andresponsibilities.
2.18. The government shall ensure that a graded approach is taken to theregulatory control of radiation exposure, so that the application of regulatory
requirements is commensurate with the radiation risks associated with theexposure situation.
2.19. The government shall establish mechanisms to ensure that:(a)(b)

The activities of the regulatory body are coordinated with those of othergovernmental authorities, in accordance with para. 2.15(e), and withnational and international organizations that have related responsibilities;
Interested parties are involved as appropriate in regulatory decision making
processes or regulatory decision aiding processes.

2.20. The government shall ensure that arrangements are in place at the national
level for making decisions relating to protection and safety that fall outside theauthority of the regulatory body.
2.21. The government shall ensure that requirements are established for:
(a)
(b)
(c)

Education, training, qualification and competence in protection and safetyof all persons engaged in activities relevant to protection and safety;
The formal recognition12 of qualified experts;
The competence of organizations that have responsibilities relating toprotection and safety.

12‘Formal recognition’ means documented acknowledgement by the relevant authoritythat a person has the qualifications and expertise required for the responsibilities that he or she
will bear in the conduct of the authorized activity.

21

2.22. The government shall ensure that arrangements are in place for the provisionof the education and training services required for building and maintaining thecompetence of persons and organizations that have responsibilities relating toprotection and safety.
2.23. The government shall ensure that arrangements are in place for theprovision of technical services relating to protection and safety, such as services
for personal dosimetry, environmental monitoring and the calibration ofmonitoring and measuring equipment.
2.24. The government shall ensure that arrangements are in place for thesafe decommissioning of facilities [9], the safe management of radioactive
waste [10, 11] and the safe management of spent fuel.
2.25. The government shall ensure that the transport of radioactive material isin accordance with the IAEA Regulations for the Safe Transport of Radioactive
Material (the IAEA Transport Regulations) [12] and with any applicableinternational conventions, taking into consideration other internationallyendorsed standards and recommendations derived from the IAEA Transport
Regulations.13
2.26. The government shall ensure that arrangements are in place for regaining
control over radioactive sources that have been abandoned, lost, misplaced,stolen or otherwise transferred without proper authorization.
2.27. The government shall ensure that infrastructural arrangements are in place
for the interfaces between safety and the security of radioactive sources.
2.28. In establishing the legal and regulatory framework for protection andsafety, the government:
(a)
(b)
(c)

Shall fulfil its respective international obligations;
Shall allow for participation in relevant international arrangements,
including international peer reviews;
Shall promote international cooperation to enhance safety globally.

13

Additional measures are taken for security in the transport of radioactive material. The
IAEA issues guidance on security in the transport of radioactive material in the IAEA Nuclear
Security Series of publications.

22

RESPONSIBILITIES OF THE REGULATORY BODY
Requirement 3: Responsibilities of the regulatory body
The regulatory body shall establish or adopt regulations and guides
for protection and safety and shall establish a system to ensure theirimplementation.
2.29. The regulatory body shall establish requirements for the application of theprinciples of radiation protection specified in paras 2.8–2.12 for all exposure
situations and shall establish or adopt regulations and guides for protection andsafety.
2.30. The regulatory body shall establish a regulatory system for protection andsafety that includes [8]:
(a)
(b)
(c)
(d)
(e)
(f)

Notification and authorization;
Review and assessment of facilities and activities;
Inspection of facilities and activities;
Enforcement of regulatory requirements;
The regulatory functions relevant to emergency exposure situations andexisting exposure situations;
Provision of information to, and consultation with, parties affected by its
decisions and, as appropriate, the public and other interested parties.

2.31. The regulatory body shall adopt a graded approach to the implementationof the system of protection and safety, such that the application of regulatory
requirements is commensurate with the radiation risks associated with theexposure situation.
2.32. The regulatory body shall ensure the application of the requirements foreducation, training, qualification and competence in protection and safety of all
persons engaged in activities relevant to protection and safety.
2.33. The regulatory body shall ensure that mechanisms are in place for thetimely dissemination of information to relevant parties, such as suppliers of andusers of sources, on lessons learned for protection and safety from regulatory
experience and operating experience, and from incidents and accidents and therelated findings. The mechanisms established shall, as appropriate, be used toprovide relevant information to other relevant organizations at the national andinternational level.
232.34. The regulatory body, in conjunction with other relevant authorities, shallspecify requirements for acceptance and for performance, by regulation or by theapplication of published standards, for any manufactured or constructed source,
device, equipment or facility that, when in use, has implications for protection
and safety.
2.35. The regulatory body shall make provision for establishing, maintaining
and retrieving adequate records relating to facilities and activities. These records
shall include:—— Registers of sealed sources and radiation generators14;—— Records of doses from occupational exposure;—— Records relating to the safety of facilities and activities;—— Records that might be necessary for the shutdown and decommissioning or
closure of facilities;—— Records of events, including non-routine releases of radioactive material tothe environment;—— Inventories of radioactive waste and of spent fuel.
2.36. The regulatory body shall establish mechanisms for communication anddiscussion that involve professional and constructive interactions with relevant
parties for all protection and safety related issues.
2.37. The regulatory body, in consultation with the health authority, shall ensurethat provisions are in place for ensuring protection and safety in the handling of
deceased persons or human remains that are known to contain sealed or unsealed
radioactive sources, either as a result of radiological procedures for medical
treatment of patients or as a consequence of an emergency.
2.38. The regulatory body shall establish, implement, assess and strive tocontinually improve a management system that is aligned with the goals of theregulatory body and that contributes to the achievement of those goals.

14

The regulatory body specifies which sources are to be included in the registers andinventories, with due consideration given to the associated risks.

24

RESPONSIBILITIES FOR PROTECTION AND SAFETY
Requirement 4: Responsibilities for protection and safety
The person or organization responsible for facilities and activities that giverise to radiation risks shall have the prime responsibility for protection andsafety. Other parties shall have specified responsibilities for protection andsafety.
2.39. The person or organization responsible for any facility or activity that gives
rise to radiation risks shall have the prime responsibility for protection and safety,
which cannot be delegated.
2.40. The principal parties responsible for protection and safety are:
(a)
(b)
(c)
(d)

Registrants or licensees, or the person or organization responsible forfacilities and activities for which notification only is required;
Employers, in relation to occupational exposure;Radiological medical practitioners, in relation to medical exposure;
Those persons or organizations designated to deal with emergency exposure
situations or existing exposure situations.

2.41. Other parties shall have specified responsibilities in relation to protection
and safety. These other parties include:
(a)
(b)
(c)
(d)
(e)
(f)
(g)
(h)

Suppliers of sources, providers of equipment and software, and providersof consumer products;
Radiation protection officers;
Referring medical practitioners;
Medical physicists;
Medical radiation technologists;
Qualified experts or any other party to whom a principal party has assigned
specific responsibilities;
Workers other than workers listed in (a)–(f) in this paragraph;
Ethics committees.

25

2.42. The relevant principal parties shall establish and implement a protection andsafety programme that is appropriate for the exposure situation. The protection
and safety programme:(a)(b)

Shall adopt objectives for protection and safety in accordance with therequirements of these Standards;
Shall apply measures for protection and safety that are commensuratewith the radiation risks associated with the exposure situation and that are
adequate to ensure compliance with the requirements of these Standards.

2.43. The relevant principal parties shall ensure that, in the implementation of theprotection and safety programme:
(a)
(b)
(c)
(d)
(e)

The measures and resources that are necessary for achieving the objectives
for protection and safety have been determined and are duly provided;
The programme is periodically reviewed to assess its effectiveness and its
continued fitness for purpose;
Any failures or shortcomings in protection and safety are identified andcorrected, and steps are taken to prevent their recurrence;
Arrangements are made to consult with interested parties;
Appropriate records are maintained.

2.44. The relevant principal parties and other parties having specified
responsibilities in relation to protection and safety shall ensure that all personnel
engaged in activities relevant to protection and safety have appropriate education,
training and qualification so that they understand their responsibilities and canperform their duties competently, with appropriate judgement and in accordancewith procedures.
2.45. The relevant principal parties shall permit access by authorized
representatives of the regulatory body to carry out inspections of their facilities
and activities and of their protection and safety records, and shall cooperate in the
conduct of inspections.
2.46. The relevant principal parties shall ensure that qualified experts are
identified and are consulted as necessary on the proper observance of theseStandards.

26

MANAGEMENT REQUIREMENTS
Requirement 5: Management for protection and safety
The principal parties shall ensure that protection and safety are effectively
integrated into the overall management system of the organizations forwhich they are responsible.
Protection and safety elements of the management system
2.47. The principal parties shall demonstrate commitment to protection and safety
at the highest levels within the organizations for which they are responsible.
2.48. The principal parties shall ensure that the management system15 is designed
and applied to enhance protection and safety by:
(a)
(b)
(c)
(d)
(e)

Applying the requirements for protection and safety coherently with otherrequirements, including requirements for operational performance, andcoherently with guidelines for security;
Describing the planned and systematic actions necessary to provide
adequate confidence that the requirements for protection and safety are
fulfilled;
Ensuring that protection and safety are not compromised by otherrequirements;
Providing for the regular assessment of performance for protection andsafety, and the application of lessons learned from experience;
Promoting safety culture.

2.49. The principal parties shall ensure that protection and safety elements of the
management system are commensurate with the complexity of and the radiation
risks associated with the activity.
2.50. The principal parties shall be able to demonstrate the effective fulfilment of
the requirements for protection and safety in the management system.

15

Requirements on the management system for facilities and activities are established inRef. [13].

27Safety culture
2.51. The principal parties shall promote and maintain safety culture by:
(a)
(b)
(c)
(d)
(e)
(f)
(g)
(h)

Promoting individual and collective commitment to protection and safety at
all levels of the organization;
Ensuring a common understanding of the key aspects of safety culture
within the organization;
Providing the means by which the organization supports individuals andteams in carrying out their tasks safely and successfully, with account takenof the interactions between individuals, technology and the organization;
Encouraging the participation of workers and their representatives andother relevant persons in the development and implementation of policies,
rules and procedures dealing with protection and safety;
Ensuring accountability of the organization and of individuals at all levels
for protection and safety;
Encouraging open communication with regard to protection and safety
within the organization and with relevant parties, as appropriate;
Encouraging a questioning and learning attitude, and discouraging
complacency, with regard to protection and safety;
Providing means by which the organization continually seeks to develop
and strengthen its safety culture.

Human factors
2.52. The principal parties and other parties having specified responsibilities inrelation to protection and safety, as appropriate, shall take into account humanfactors and shall support good performance and good practices to prevent humanand organizational failures, by ensuring among other things that:
(a)

(b)

28

Sound ergonomic principles are followed in the design of equipment
and the development of operating procedures, so as to facilitate the safe
operation and use of equipment, to minimize the possibility that operator
errors could lead to accidents, and to reduce the possibility that indicationsof normal conditions and abnormal conditions could be misinterpreted.
Appropriate equipment, safety systems and procedural requirements areprovided, and other necessary provision is made:(i) To reduce, as far as practicable, the possibility that human errors or
inadvertent actions could give rise to accidents or to other incidents
leading to the exposure of any person;

(ii) To provide means for detecting human errors and for correcting themor compensating for them;(iii) To facilitate protective actions and corrective actions in the event of
failures of safety systems or failures of measures for protection andsafety.

3. PLANNED EXPOSURE SITUATIONS
SCOPE
3.1. The requirements for planned exposure situations apply to the following
practices:
(a)
(b)
(c)
(d)

(e)
(f)
(g)

The production, supply, provision and transport of radioactive material andof devices that contain radioactive material, including sealed sources andunsealed sources, and of consumer products;
The production and supply of devices that generate radiation, including
linear accelerators, cyclotrons, and fixed and mobile radiographyequipment;
The generation of nuclear power, including any activities within the nuclear
fuel cycle that involve or that could involve exposure to radiation or
exposure due to radioactive material;
The use of radiation or radioactive material for medical, industrial,
veterinary, agricultural, legal or security purposes, including the use of
associated equipment, software or devices where such use could affectexposure to radiation;
The use of radiation or radioactive material for education, training or
research, including any activities relating to such use that involve or could
involve exposure to radiation or exposure due to radioactive material;
The mining and processing of raw materials that involve exposure due toradioactive material;
Any other practice as specified by the regulatory body.

29

3.2. The requirements for planned exposure situations apply to exposure due tosources within practices16, as follows:
(a)

(b)

Facilities that contain radioactive material and facilities that containradiation generators, including nuclear installations, medical radiation
facilities, veterinary radiation facilities, facilities for the management ofradioactive waste, installations for the processing of radioactive material,
irradiation facilities, and mineral extraction and mineral processing
facilities that involve or could involve exposure to radiation or exposuredue to radioactive material;
Individual sources of radiation, including sources within the types offacility mentioned in para. 3.2(a), as appropriate, in accordance with therequirements of the regulatory body.

3.3. The requirements for planned exposure situations apply for any
occupational exposure, medical exposure or public exposure due to any practiceor due to a source within a practice as specified in paras 3.1 and 3.2.
3.4. Exposure due to natural sources is, in general, considered an existing
exposure situation and is subject to the requirements in Section 5. However, therelevant requirements in Section 3 for planned exposure situations apply to:
(a)

(b)

Exposure due to material17 in any practice specified in para. 3.1 where theactivity concentration in the material of any radionuclide in the uranium
decay chain or the thorium decay chain is greater than 1 Bq/g or the activity
concentration of 40K is greater than 10 Bq/g;
Public exposure due to discharges or due to the management of radioactive
waste arising from a practice involving material as specified in (a) above;16

For example, a sterilization gamma irradiation unit is a source for the practice ofradiation preservation of food. An X ray unit may be a source for the practice of radiodiagnosis.
A nuclear power plant is part of the practice of generating electricity by nuclear fission,and may be regarded as a single source (e.g. with respect to discharges) or as a collectionof sources (e.g. for purposes of occupational radiation protection). A complex or multiple
installation situated at one location or site may, as appropriate, be considered a single source forthe purposes of application of these Standards.
17
A situation of exposure due to radionuclides of natural origin in food, feed, drinking
water, agricultural fertilizer and soil amendments, construction materials and residual
radioactive material in the environment is treated as an existing exposure situation regardlessof the activity concentrations of the radionuclides concerned.

30

(c)

(d)

Exposure due to 222Rn and to 222Rn progeny and due to 220Rn and to220
Rn progeny in workplaces in which occupational exposure due to otherradionuclides in the uranium decay chain or the thorium decay chain iscontrolled as a planned exposure situation;
Exposure due to 222Rn and to 222Rn progeny where the annual average
activity concentration of 222Rn in air in workplaces remains above thereference level established in accordance with para. 5.27 after the fulfilmentof the requirement in para. 5.28.

GENERIC REQUIREMENTS
3.5. No person or organization shall adopt, introduce, conduct, discontinue
or cease a practice, or shall, as applicable, mine, extract, process, design,
manufacture, construct, assemble, install, acquire, import, export, supply, provide,
distribute, loan, hire, receive, site, locate, commission, possess, use, operate,
maintain, repair, transfer, decommission, disassemble, transport, store or disposeof a source within a practice other than in accordance with the requirements ofthese Standards.
Requirement 6: Graded approach
The application of the requirements of these Standards in planned exposure
situations shall be commensurate with the characteristics of the practiceor the source within a practice, and with the likelihood and magnitude of
exposures.
3.6. The application of the requirements of these Standards shall be inaccordance with the graded approach and shall also conform to any requirements
specified by the regulatory body. Not all the requirements of these Standards are
relevant for every practice or source, or for all the actions specified in para. 3.5.
Requirement 7: Notification and authorization
Any person or organization intending to operate a facility or to conduct
an activity shall submit to the regulatory body a notification and, as
appropriate, an application for authorization.

31

Notification
3.7. Any person or organization intending to carry out any of the actions
specified in para. 3.5 shall submit a notification to the regulatory body of such an
intention18. Notification alone is sufficient provided that the exposures expected
to be associated with the practice or action are unlikely to exceed a small fraction,as specified by the regulatory body, of the relevant limits, and that the likelihood
and magnitude of potential exposures and any other potential detrimental
consequences are negligible. Notification is required for consumer products onlywith respect to manufacture, maintenance, import, export, provision, distribution
and, in some cases, disposal.
Authorization: Registration or licensing
3.8. Any person or organization intending to carry out any of the actions
specified in para. 3.5 shall, unless notification alone is sufficient, apply tothe regulatory body for authorization18, which shall take the form of either
registration19 or licensing.
3.9. Any person or organization applying for authorization:
(a)
(b)
(c)
(d)

Shall submit to the regulatory body the relevant information necessary tosupport the application;
Shall refrain from carrying out any of the actions specified in para. 3.5 until
the registration or the licence has been issued;
Shall assess the nature, likelihood and magnitude of the expected exposuresdue to the source and shall take all necessary measures for protection andsafety;Shall, if there is a possibility for an exposure to be greater than a levelas specified by the regulatory body, have a safety assessment made andsubmitted to the regulatory body as part of the application;

18
With regard to material being transported in accordance with the IAEA Transport
Regulations [12], the requirements of these Standards for notification and authorization are
fulfilled by means of compliance with the requirements of the IAEA Transport Regulations.
19
Typical practices that are suitable for registration are those for which: (i) safety canlargely be ensured by the design of the facilities and equipment; (ii) the operating procedures
are simple to follow; (iii) the training requirements for safety are minimal; and (iv) there is ahistory of few problems relating to safety in operations. Registration is best suited to thosepractices for which operations do not vary significantly.

32

(e)

Shall, as required by the regulatory body, have an appropriate prospective
assessment made for radiological environmental impacts, commensuratewith the radiation risks associated with the facility or activity.

Requirement 8: Exemption and clearance
The government or the regulatory body shall determine which practices
or sources within practices are to be exempted from some or all of therequirements of these Standards. The regulatory body shall approve
which sources, including materials and objects, within notified practices orauthorized practices may be cleared from regulatory control.
Exemption
3.10. The government or the regulatory body shall determine which practices orsources within practices are to be exempted from some or all of the requirementsof these Standards, including the requirements for notification, registration or
licensing, using as the basis for this determination the criteria for exemption
specified in Schedule I or any exemption levels specified by the regulatory bodyon the basis of these criteria.
3.11. Exemption shall not be granted for practices deemed to be not justified.
Clearance
3.12. The regulatory body shall approve which sources, including materials andobjects, within notified or authorized practices may be cleared from regulatory
control, using as the basis for such approval the criteria for clearance specified in
Schedule I or any clearance levels specified by the regulatory body on the basisof these criteria. By means of this approval, the regulatory body shall ensurethat sources that have been cleared from regulatory control do not again become
subject to the requirements for notification, registration or licensing unless it so
specifies.
Requirement 9: Responsibilities of registrants and licensees in planned
exposure situations
Registrants and licensees shall be responsible for protection and safety inplanned exposure situations.

33

3.13. Registrants and licensees shall bear the responsibility for setting up andimplementing the technical and organizational measures that are necessary
for protection and safety for the practices and sources for which they areauthorized. Registrants and licensees may designate suitably qualified persons
to carry out tasks relating to these responsibilities, but they shall retain the prime
responsibility for protection and safety. Registrants and licensees shall document
the names and responsibilities of persons designated to ensure compliance withthe requirements of these Standards.
3.14. Registrants and licensees shall notify the regulatory body of any intention to
introduce modifications to any practice or source for which they are authorized,
whenever the modifications could have significant implications for protection andsafety, and they shall not carry out any such modification unless it is specificallyauthorized by the regulatory body.
3.15. Registrants and licensees:
(a)
(b)
(c)
(d)

(e)
(f)
(g)
(h)

34

Shall establish clear lines of responsibility and accountability for protection
and safety for the sources for which they are authorized, and shall establish
organizational arrangements for protection and safety;
Shall ensure that any delegation of responsibilities by a principal party is
documented;
Shall, for the sources for which they are authorized and for which a safetyassessment is required in para. 3.9(d), conduct such a safety assessment andkeep it up to date in accordance with para. 3.35;
Shall, for the sources for which they are authorized and for which
the regulatory body requires a prospective assessment to be made forradiological environmental impacts (see para. 3.9(e)), conduct such anassessment and keep it up to date;
Shall assess the likelihood and magnitude of potential exposures, theirlikely consequences and the number of individuals who may be affected by
them;Shall have in place operating procedures and arrangements for protection
and safety that are subject to periodic review and updating under amanagement system;
Shall establish procedures for reporting on and learning from accidents andother incidents;
Shall establish arrangements for the periodic review of the overall
effectiveness of the measures for protection and safety;

(i)
(j)

Shall ensure that adequate maintenance, testing and servicing are carriedout as necessary so that sources remain capable of fulfilling their design
requirements for protection and safety throughout their lifetime;
Shall ensure safe management of and control over all radioactive wastethat is generated, and shall dispose of such waste in accordance with theregulatory requirements.

Requirement 10: Justification of practices
The government or the regulatory body shall ensure that only justified
practices are authorized.
3.16. The government or the regulatory body, as appropriate, shall ensure thatprovision20 is made for the justification of any type of practice21 and for reviewof the justification, as necessary, and shall ensure that only justified practices areauthorized.
3.17. The following practices are deemed to be not justified:
(a)

(b)

(c)

Practices, except for justified practices involving medical exposure22, that
result in an increase in activity, by the deliberate addition of radioactive
substances or by activation23, in food, feed, beverages, cosmetics or
any other commodity or product intended for ingestion, inhalation or
percutaneous intake by, or application to, a person;
Practices involving the frivolous use of radiation or radioactive substancesin commodities or in consumer products such as toys and personal jewellery
or adornments, which result in an increase in activity, by the deliberate
addition of radioactive substances or by activation23;
Human imaging using radiation that is performed as a form of art or for
publicity purposes.

20

Such provision may involve several governmental authorities not necessarily having
direct responsibility for protection and safety, such as ministries of health, justice, immigrationand security.
21
This provision for the justification of any type of practice includes practices for which
notification alone is sufficient.
22
Particular requirements for the justification of medical exposure are specified inparas 3.155–3.161.
23
This requirement is not intended to prohibit those practices that may involve the shortterm activation of commodities or products, for which there is no increase in radioactivity in thecommodity or product as made available.

35

3.18. Human imaging using radiation that is performed for occupational, legal
or health insurance purposes24, and is undertaken without reference to clinicalindication, shall normally be deemed to be not justified. If, in exceptional
circumstances, the government or the regulatory body decides that thejustification of such human imaging for specific practices is to be considered, therequirements of paras 3.61–3.64 and 3.66 shall apply.
3.19. Human imaging using radiation for theft detection purposes shall bedeemed to be not justified.
3.20. Human imaging using radiation for the detection of concealed objects
for anti-smuggling purposes shall normally be deemed to be not justified. If, in
exceptional circumstances, the government or the regulatory body decides thatthe justification of such human imaging is to be considered, the requirements ofparas 3.61–3.67 shall apply.
3.21. Human imaging using radiation for the detection of concealed objects thatcan be used for criminal acts that pose a national security threat shall be justified
only by the government. If the government decides that the justification of suchhuman imaging is to be considered, the requirements of paras 3.61–3.67 shallapply.
Requirement 11: Optimization of protection and safety
The government or the regulatory body shall establish and enforce
requirements for the optimization of protection and safety, and registrants
and licensees shall ensure that protection and safety is optimized.
3.22. The government or the regulatory body:(a)(b)

Shall establish and enforce requirements for the optimization of protection
and safety;
Shall require documentation addressing the optimization of protection andsafety;24

Such purposes for performing human imaging using radiation include: assessment offitness for employment (prior to employment or periodically during employment); assessmentof physiological suitability for a career or a sport; assessment of athletes before a selection
or transfer; determination of age for legal purposes; obtaining evidence for legal purposes;
detection of drugs concealed within the body; immigration or emigration requirements;
pre-insurance checks; and obtaining evidence for the purposes of a compensation claim.

36

(c)

Shall establish or approve constraints25 on dose and on risk, as appropriate,or shall establish or approve a process for establishing such constraints, tobe used in the optimization of protection and safety.

3.23. Registrants and licensees shall ensure that protection and safety is
optimized.
3.24. For occupational exposure and public exposure26, registrants and licensees
shall ensure that all relevant factors are taken into account in a coherent way inthe optimization of protection and safety to contribute to achieving the following
objectives:
(a)

(b)

To determine measures for protection and safety that are optimized for theprevailing circumstances, with account taken of the available options forprotection and safety as well as the nature, likelihood and magnitude of
exposures;
To establish criteria, on the basis of the results of the optimization, forthe restriction of the likelihood and magnitudes of exposures by means ofmeasures for preventing accidents and for mitigating the consequences of
those that do occur.

3.25. For occupational exposure and public exposure, registrants and licensees
shall ensure, as appropriate, that relevant constraints are used in the optimizationof protection and safety for any particular source within a practice.25
Requirement 12: Dose limits
The government or the regulatory body shall establish dose limits foroccupational exposure and public exposure, and registrants and licensees
shall apply these limits.

25
For occupational exposure, the relevant dose constraint is on individual doses
to workers, established and used by registrants and licensees to set the range of options in
optimizing protection and safety for the source. For public exposure, the relevant dose constraint
is a source related value established or approved by the government or the regulatory body, withaccount taken of the doses from planned operations of all sources under control. The dose
constraint for each particular source is intended, among other things, to ensure that the sum ofdoses from planned operations for all sources under control remains within the dose limit.
26
Requirements for the optimization of medical exposure are specified inparas 3.162–3.177.

37

3.26. The government or the regulatory body shall establish and the regulatory
body shall enforce compliance with the dose limits specified in Schedule III for
occupational exposures and public exposures in planned exposure situations.
3.27. The government or the regulatory body shall determine what additional
restrictions, if any, are required to be complied with by registrants and licensees
to ensure that the dose limits specified in Schedule III are not exceeded owing
to possible combinations of doses from exposures due to different authorizedpractices.
3.28. Registrants and licensees shall ensure that the exposures of individuals
due to the practices for which the registrants and licensees are authorized are
restricted, so that neither the effective dose nor the equivalent dose to tissues ororgans exceeds any relevant dose limit specified in Schedule III.27
Requirement 13: Safety assessment
The regulatory body shall establish and enforce requirements for safetyassessment, and the person or organization responsible for a facility or
activity that gives rise to radiation risks shall conduct an appropriate safetyassessment of this facility or activity.
3.29. The regulatory body shall establish requirements for persons ororganizations responsible for facilities and activities that give rise to radiation
risks to conduct an appropriate safety assessment28. Prior to the granting of an
authorization, the responsible person or organization shall be required to submit asafety assessment, which shall be reviewed and assessed by the regulatory body.
3.30. The person or organization, as required under para. 3.9(d), or registrants
and licensees, as appropriate, shall conduct a safety assessment that is either
generic or specific to the practice or source for which they are responsible.29

27

Dose limits do not apply to medical exposures.
Requirements on safety assessment for facilities and activities are established inRef. [14].
29
A generic safety assessment is usually sufficient for types of source with a highdegree of uniformity in design. A specific safety assessment is usually required in other cases;
however, the specific safety assessment need not include those aspects covered by a genericsafety assessment, if a generic safety assessment has been conducted for the type of source.
28

38

3.31. Safety assessments shall be conducted at different stages, including thestages of siting, design, manufacture, construction, assembly, commissioning,
operation, maintenance and decommissioning (or closure) of facilities or parts
thereof, as appropriate, so as:
(a)
(b)
(c)

To identify the ways in which exposures could be incurred, account being
taken of the effects of external events as well as of events directly involving
the sources and associated equipment;
To determine the expected likelihood and magnitudes of exposures innormal operation and, to the extent reasonable and practicable, to make anassessment of potential exposures;
To assess the adequacy of the provisions for protection and safety.

3.32. The safety assessment shall include, as appropriate, a systematic criticalreview of:
(a)
(b)

(c)
(d)
(e)
(f)
(g)

The operational limits and conditions for the operation of the facility;
The ways in which structures, systems and components, including
software, and procedures relating to protection and safety might fail, singly
or in combination, or might otherwise give rise to exposures, and theconsequences of such events;
The ways in which external factors could affect protection and safety;
The ways in which operating procedures relating to protection and safety
might be erroneous, and the consequences of such errors;
The implications for protection and safety of any modifications;
The implications for protection and safety of security measures or of any
modifications to security measures;
Any uncertainties or assumptions and their implications for protection andsafety.

3.33. The registrant or licensee shall take into account in the safety assessment:
(a)

(b)

Factors that could give rise to a substantial release of radioactive material,
the measures available to prevent or to control such a release, and the
maximum activity of radioactive material that, in the event of a major
failure of the containment, could be released to the environment;
Factors that could give rise to a smaller but continuing release of radioactive
material, and the measures available to detect and to prevent or to control
such a release;

39

(c)
(d)

Factors that could give rise to unintended operation of any radiation
generator or a loss of shielding, and the measures available to detect and toprevent or to control such occurrences;
The extent to which the use of redundant and diverse safety features thatare independent of each other, so that failure of one does not result in
failure of any other, is appropriate to restrict the likelihood and magnitude
of potential exposures.

3.34. Registrants and licensees shall ensure that the safety assessment isdocumented and, where appropriate, that it is independently reviewed under the
relevant management system.
3.35. Registrants and licensees shall perform additional reviews of the safetyassessment as necessary to ensure that the technical specifications or conditionsof use continue to be met when:
(a)
(b)
(c)
(d)
(e)

Significant modifications to the facility or to its operating procedures ormaintenance procedures are envisaged;
Significant changes occur on the site that could affect the safety of the
facility or of activities on the site;
Information on operating experience, or information about accidents andother incidents that could result in exposures, indicates that the current
assessment might be invalid;
Any significant changes in activities are envisaged;
Any relevant changes in guidelines or standards have been made or areenvisaged.

3.36. If as a result of a safety assessment, or for any other reason, opportunities
to improve protection and safety appear to be available and improvement seems
desirable, any consequential modifications shall be made cautiously and only
after favourable assessment of all the implications for protection and safety.
The implementation of all improvements shall be prioritized so as to optimize
protection and safety.
Requirement 14: Monitoring for verification of compliance
Registrants and licensees and employers shall conduct monitoring to verify
compliance with the requirements for protection and safety.
3.37. The regulatory body shall establish requirements that monitoring andmeasurements be performed to verify compliance with the requirements for40

protection and safety. The regulatory body shall be responsible for review andapproval of the monitoring and measurement programmes of registrants andlicensees.
3.38. Registrants and licensees and employers shall ensure that:
(a)
(b)
(c)
(d)
(e)

Monitoring and measurements of parameters are performed as necessary
for verification of compliance with the requirements of these Standards;
Suitable equipment is provided and procedures for verification are
implemented;
Equipment is properly maintained, tested and calibrated at appropriate
intervals with reference to standards traceable to national or international
standards;
Records are maintained of the results of monitoring and verification ofcompliance, as required by the regulatory body, including records of thetests and calibrations carried out in accordance with these Standards;
The results of monitoring and verification of compliance are shared withthe regulatory body as required.

Requirement 15: Prevention and mitigation of accidents
Registrants and licensees shall apply good engineering practice and shalltake all practicable measures to prevent accidents and to mitigate theconsequences of those accidents that do occur.
Good engineering practice
3.39. The registrant or licensee, in cooperation with other responsible parties,
shall ensure that the siting, location, design, manufacture, construction, assembly,
commissioning, operation, maintenance and decommissioning (or closure) offacilities or parts thereof are based on good engineering practice which shall, as
appropriate:
(a)
(b)
(c)

Take account of international and national standards;
Be supported by managerial and organizational features, with the purposeof ensuring protection and safety throughout the lifetime of the facility;
Include adequate safety margins in the design and construction of the
facility, and in operations involving the facility, so as to ensure reliable
performance in normal operation, and take account of the necessary quality,
redundancy and capability for inspection, with emphasis on preventing

41

(d)

accidents, mitigating the consequences of those accidents that do occur andrestricting any possible future exposures;
Take account of relevant developments concerning technical criteria, as
well as the results of any relevant research on protection and safety andfeedback of information on lessons learned from experience.

Defence in depth
3.40. Registrants and licensees shall ensure that a multilevel (defence in depth)
system of sequential, independent provisions for protection and safety thatis commensurate with the likelihood and magnitude of potential exposures
is applied to sources for which the registrants and licensees are authorized.
Registrants and licensees shall ensure that if one level of protection were to fail,the subsequent independent level of protection would be available. Such defence
in depth shall be applied for the purposes of:
(a)
(b)
(c)

Preventing accidents;
Mitigating the consequences of any accidents that do occur;
Restoring the sources to safe conditions after any such accidents.

Accident prevention
3.41. Registrants and licensees shall ensure that structures, systems andcomponents, including software, that are related to protection and safety forfacilities and activities are designed, constructed, commissioned, operated andmaintained so as to prevent accidents as far as reasonably practicable.
3.42. The registrant or licensee for any facility or activity shall make suitablearrangements:
(a)
(b)
(c)
(d)
(e)

42

To prevent reasonably foreseeable accidents in the facility or the activity;
To mitigate the consequences of those accidents that do occur;
To provide workers with the information, instruction, training andequipment necessary to restrict potential exposures;
To ensure that there are adequate procedures for the control of the facility
and for the management of any reasonably foreseeable accidents;
To ensure that safety significant structures, systems and components,
including software, and other equipment can be inspected and tested
regularly for any degradation that could lead to abnormal conditions orinadequate performance;

(f)
(g)
(h)
(i)

To ensure that maintenance, inspection and testing appropriate to thepreservation of the provisions for protection and safety can be carried out
without undue occupational exposure;
To provide, wherever appropriate, automatic systems for safely shutting off
or reducing the release of radiation from facilities in the event that operating
conditions are outside the stipulated ranges;
To ensure that abnormal operating conditions that could significantly affectprotection and safety are detected by systems that respond quickly enoughto allow for corrective action to be taken in a timely manner;
To ensure that all relevant safety documentation is available in theappropriate languages understandable to users.

Emergency preparedness and response
3.43. If the safety assessment indicates that there is a reasonable likelihood ofan emergency affecting either workers or members of the public, the registrant
or licensee shall prepare an emergency plan for the protection of people andthe environment. As part of this emergency plan, the registrant or licensee shall
include arrangements for the prompt identification of an emergency, and for
determining the appropriate level of the emergency response [15]. In relation to
the arrangements for the emergency response at the scene by the registrant or
licensee, the emergency plan shall include, in particular:(a)(b)

Provision for individual monitoring and area monitoring, and arrangements
for medical treatment;
Arrangements for assessing and mitigating any consequences of an
emergency.

3.44. Registrants and licensees shall be responsible for the implementation of
their emergency plans and shall be prepared to take any necessary action for
effective response. To prevent the occurrence of conditions that could lead to aloss of control over a source or to the escalation of such conditions, registrants
and licensees shall, as appropriate:
(a)
(b)
(c)

Develop, maintain and implement procedures to provide the means forpreventing loss of control over the source and for regaining control over thesource as necessary;
Make available equipment, instrumentation and diagnostic aids that may beneeded;Train and periodically retrain personnel in the procedures to be followed
and exercise the procedures.
43Requirement 16: Investigations and feedback of information on operating
experience
Registrants and licensees shall conduct formal investigations of abnormal
conditions arising in the operation of facilities or the conduct of activities,
and shall disseminate information that is significant for protection andsafety.
3.45. Registrants and licensees shall ensure that information on both normal
operation and abnormal conditions that are significant for protection and safety
is disseminated or made available, as appropriate, to the regulatory body andrelevant parties, as specified by the regulatory body. This information would
include, for example, details of doses associated with given activities, data on
maintenance, descriptions of events and information on corrective actions, andinformation on operating experience from other relevant facilities and activities.
3.46. Registrants and licensees shall conduct an investigation as specified by theregulatory body in the event that:(a)(b)

A quantity or operating parameter relating to protection and safety exceeds
an investigation level or is outside the stipulated range of operating
conditions; orAny equipment failure, accident, error, mishap or other unusual event orcondition occurs that has the potential for causing a quantity to exceed any
relevant limit or operating restriction.

3.47. The registrant or licensee shall conduct an investigation as soon as possible
after an event and shall prepare a written record of its causes, or suspected causes,
including a verification or determination of any doses received or committed andrecommendations for preventing the recurrence of the event and the occurrenceof similar events.
3.48. The registrant or licensee shall communicate to the regulatory body andto any other relevant parties, as appropriate, a written report of any formal
investigation relating to events as prescribed by the regulatory body, including
exposures giving rise to doses exceeding a dose limit. The registrant or licensee
shall also immediately report to the regulatory body any event in which a dose
limit is exceeded.

44Requirement 17: Radiation generators and radioactive sources
Registrants and licensees shall ensure the safety of radiation generators andradioactive sources.
3.49. Registrants and licensees who are manufacturers or other suppliers ofradiation generators and radioactive sources shall ensure that the following
responsibilities are discharged, as applicable:
(a)

(b)
(c)

(d)

Supplying a well designed, well manufactured and well constructedradiation generator or radioactive source and device in which the radiation
generator or radioactive source is used that:(i) Provides for protection and safety in accordance with the requirementsof these Standards;(ii) Meets engineering, performance and functional specifications;(iii) Meets quality standards commensurate with the significance forprotection and safety of systems and components, including software;(iv) Provides clear displays, gauges and instructions on operating consoles
in the appropriate language understandable to users.
Ensuring that radiation generators and radioactive sources are tested todemonstrate compliance with the relevant specifications.
Making information available, in the appropriate language understandable
to users, on the proper installation and use of the radiation generator
or radioactive source and on its associated radiation risks, including
performance specifications, instructions for operating and maintenance,
and instructions for protection and safety.
Ensuring that the protection provided by shielding and by other protective
devices is optimized.

3.50. Where applicable, registrants and licensees shall make suitablearrangements with suppliers of radiation generators and radioactive sources, theregulatory body and relevant parties for the purposes of:(a)(b)

Obtaining information on conditions of use and operating experience that
may be important for protection and safety;
Providing feedback and information that may have implications forprotection and safety for other users, or that may have implications forthe possibility for improvements in protection and safety for radiation
generators and radioactive sources.

45

3.51. When choosing a location to use or to store a radiation generator orradioactive source, registrants and licensees shall take into account:
(a)
(b)
(c)

Factors that could affect the safe management of and control over theradiation generator or radioactive source;
Factors that could affect occupational exposure and public exposure due tothe radiation generator or radioactive source;
The feasibility of taking the foregoing factors into account in engineering
design.

3.52. In selecting a site for a facility that will contain a large amount of radioactive
material and that will have the potential for the release of significant amountsof radioactive material, registrants and licensees shall take into account featuresthat might affect protection and safety, features that might affect the integrity orfunctioning of the facility, and the feasibility of carrying out off-site protective
actions if they become necessary.
3.53. Registrants and licensees shall maintain an inventory that includes records
of:
(a)
(b)

The location and description of each radiation generator or radioactive
source for which they are responsible;
The activity and form of each radioactive source for which they are
responsible.

3.54. Registrants and licensees shall provide the regulatory body as required withappropriate information from their inventory records of radiation generators andradioactive sources.
3.55. Registrants and licensees shall keep radiation generators and radioactive
sources under control so as to prevent loss or damage and to prevent any
unauthorized person from carrying out any of the activities specified in para. 3.5,
by ensuring that:
(a)
(b)

46

Control over a radiation generator or radioactive source is relinquished onlyin compliance with all relevant requirements specified in the registration or
licence;
The regulatory body is promptly notified of information regarding aradiation generator or radioactive source that is lost, missing or not undercontrol;(c)(d)

A radiation generator or radioactive source is transferred only if therecipient possesses the necessary authorization;
An inventory, as required in para. 3.53, of radiation generators or radioactive
sources is checked periodically to confirm that they are in their assigned
locations and are under control.

3.56. Registrants and licensees shall ensure that sealed sources are categorizedin accordance with the categorization scheme set out in Schedule II, and inaccordance with the requirements of the regulatory body.
3.57. The manufacturer of a radioactive source or a device containing aradioactive source shall ensure that, where practicable, the source itself andits container are marked with the symbol recommended by the International
Organization for Standardization [16]30.
3.58. Registrants and licensees, in cooperation with manufacturers, shall ensure
that, where practicable, sealed sources are identifiable and traceable.
3.59. Registrants and licensees shall ensure that when radioactive sources are notin use they are stored in an appropriate manner for protection and safety.
3.60. Registrants and licensees shall ensure that arrangements are made promptly
for the safe management of and control over radiation generators and radioactive
sources, including appropriate financial provision, once it has been decided totake them out of use.
Requirement 18: Human imaging using radiation for purposes other than
medical diagnosis, medical treatment or biomedical research
The government shall ensure that the use of ionizing radiation for humanimaging for purposes other than medical diagnosis, medical treatment orbiomedical research is subject to the system of protection and safety.
3.61. The government, if so decided in accordance with paras 3.18, 3.20 and 3.21,
shall ensure that the requirements of para. 3.16 for the justification of practices
30

For categories 1, 2 and 3 sealed sources as defined in Schedule II, the manufacturer
may consider placement near the source, preferably on the shield or near the point of access tothe source, of the supplementary symbol specified in Ref. [17]. The supplementary symbol is
not placed on the external surfaces of transport packages, freight containers or conveyances oron building access doors.

47

are applied to any type of human imaging procedure in which radiation is used
for purposes other than for medical diagnosis or medical treatment or other thanas part of a programme of biomedical research. The justification process shall
include the consideration of:
(a)
(b)
(c)
(d)
(e)

The benefits and detriments of implementing the type of human imaging
procedure;
The benefits and detriments of not implementing the type of humanimaging procedure;
Any legal or ethical issues associated with the introduction of the type ofhuman imaging procedure;
The effectiveness and suitability of the type of human imaging procedure,
including the appropriateness of the radiation equipment for the intendeduse;
The availability of sufficient resources to conduct the human imaging
procedure safely throughout the intended period of the practice.

3.62. If it has been determined by means of the process specified in para. 3.61
that a particular practice of human imaging using radiation is justified, then sucha practice shall be subject to regulatory control.
3.63. The regulatory body, in cooperation with other relevant authorities,
agencies and professional bodies, as appropriate, shall establish the requirements
for regulatory control of the practice and for review of the justification.
3.64. For human imaging using radiation, performed by medical personnel using
medical radiological equipment, that exposes people to radiation for employment
related, legal or health insurance31 purposes without reference to clinicalindications:(a)

The government shall ensure, on the basis of consultation between
relevant authorities, professional bodies and the regulatory body, that dose
constraints are established for such human imaging;

31

Such purposes for performing human imaging using radiation include: assessment offitness for employment (prior to employment or periodically during employment); assessmentof physiological suitability for a career or a sport; assessment of athletes before a selection
or transfer; determination of age for legal purposes; obtaining evidence for legal purposes;
detection of drugs concealed within the body; immigration or emigration requirements;
pre-insurance checks; and obtaining evidence for the purposes of a compensation claim.

48

(b)

The registrant or licensee shall ensure that the appropriate optimization
requirements for medical exposure in paras 3.162–3.177 are applied,with dose constraints as required in (a) above used instead of diagnostic
reference levels.

3.65. Procedures with inspection imaging devices in which radiation is used to
expose persons for the purpose of detection of concealed weapons, contrabandor other objects on or within the body shall be considered to give rise to public
exposure. Registrants and licensees shall apply the requirements for public
exposure in planned exposure situations. In particular, registrants and licensees
shall ensure that optimization of protection and safety is subject to any dose
constraints for public exposure set by the government or the regulatory body.
3.66. Registrants and licensees shall ensure that all persons who are to undergo
procedures with inspection imaging devices in which ionizing radiation is used
are informed of the possibility of requesting the use of an alternative inspection
technique that does not use ionizing radiation, where available.
3.67. The registrant or licensee shall ensure that any inspection imaging device
used for the detection of concealed objects on or within the body, whether it
is manufactured in or imported into the State in which it is used, conforms toapplicable standards of the International Electrotechnical Commission or theInternational Organization for Standardization or to equivalent national standards.
OCCUPATIONAL EXPOSURE
Scope
3.68. The requirements in respect of occupational exposure in planned exposure
situations (paras 3.69–3.116) apply to occupational exposure due to a practice or asource within a practice, as stated in paras 3.1–3.3; and to occupational exposure
as required in Section 4 for emergency exposure situations and as required in
Section 5 for existing exposure situations. For exposure due to natural sources,
these requirements for occupational exposure in planned exposure situations
apply, as appropriate, only to the exposure situations specified in para. 3.4(a),(c) and (d).

49

Requirement 19: Responsibilities of the regulatory body specific to
occupational exposure
The government or the regulatory body shall establish and enforce
requirements to ensure that protection and safety is optimized, and theregulatory body shall enforce compliance with dose limits for occupational
exposure.
3.69. The government or the regulatory body shall establish the responsibilities
of employers, registrants and licensees with regard to application of therequirements for occupational exposure in planned exposure situations.
3.70. The government or the regulatory body shall establish and enforce
requirements to ensure that protection and safety is optimized for occupational
exposure.
3.71. The government or the regulatory body shall establish, and the regulatory
body shall enforce compliance with, the dose limits specified in Schedule III for
occupational exposure.
3.72. Before authorization of a new or modified practice, the regulatory bodyshall require, as appropriate, and review supporting documents from theresponsible parties that state:(a)(b)

Design criteria and design features relating to the exposure and potential
exposure of workers in all operational states and in accident conditions;
Design criteria and design features of the appropriate systems andprogrammes for monitoring of workers for occupational exposure in all
operational states and in accident conditions.

Requirement 20: Requirements for monitoring and recording of occupational
exposures
The regulatory body shall establish and enforce requirements for themonitoring and recording of occupational exposures in planned exposure
situations.
3.73. The regulatory body shall be responsible, as appropriate, for:

50

(a)
(b)
(c)
(d)
(e)
(f)

Establishment and enforcement of requirements for the monitoring,recording and control of occupational exposures in planned exposure
situations in accordance with the requirements of these Standards;
Review of monitoring programmes of registrants and licensees, which shallbe adequate to ensure that the requirements with regard to occupational
exposure in planned exposure situations are fulfilled;
Authorization or approval of service providers for individual monitoring
and calibration services;
Review of periodic reports on occupational exposure (including results ofmonitoring programmes and dose assessments) submitted by employers,
registrants and licensees;
Provision for maintaining exposure records and results of the assessment ofdoses from occupational exposure;
Verification of compliance of an authorized practice with the requirementson the control of occupational exposure.

Requirement 21: Responsibilities of employers, registrants and licensees forthe protection of workers
Employers, registrants and licensees shall be responsible for the protectionof workers against occupational exposure. Employers, registrants andlicensees shall ensure that protection and safety is optimized and that thedose limits for occupational exposure are not exceeded.
3.74. For workers who are engaged in activities in which they are or could be
subject to occupational exposure in planned exposure situations, employers,
registrants and licensees shall be responsible for:(a)(b)

Protection of workers against occupational exposure;Compliance with other relevant requirements of these Standards.

3.75. Employers who are also registrants or licensees shall have theresponsibilities of both employers and registrants or licensees.
3.76. Employers, registrants and licensees shall ensure, for all workers engagedin activities in which they are or could be subject to occupational exposure, that:(a)(b)

Occupational exposure is controlled so that the relevant dose limits foroccupational exposure specified in Schedule III are not exceeded;
Protection and safety is optimized in accordance with the requirements ofthese Standards;
51

(c)
(d)

(e)
(f)
(g)
(h)
(i)
(j)

(k)

Decisions with regard to measures for protection and safety are recorded
and made available to relevant parties, through their representatives whereappropriate, as specified by the regulatory body;
Policies, procedures and organizational arrangements for protection andsafety are established for implementing the relevant requirements of theseStandards, with priority given to design measures and technical measuresfor controlling occupational exposure;
Suitable and adequate facilities, equipment and services for protection andsafety are provided, the type and extent of which are commensurate withthe expected likelihood and magnitude of occupational exposure;
Necessary workers’ health surveillance and health services for workers areprovided;Appropriate monitoring equipment and personal protective equipment isprovided and arrangements are made for its proper use, calibration, testing
and maintenance;
Suitable and adequate human resources and appropriate training inprotection and safety are provided, as well as periodic retraining as required
to ensure the necessary level of competence;
Adequate records are maintained in accordance with the requirements ofthese Standards;
Arrangements are made to facilitate consultation of and cooperation withworkers, through their representatives where appropriate, with regard toprotection and safety on all measures necessary to achieve the effective
application of these Standards;
Necessary conditions for promoting safety culture are provided.

3.77. Employers, registrants and licensees:(a)(b)

Shall involve workers, through their representatives where appropriate, in
optimization of protection and safety;
Shall establish and use, as appropriate, constraints as part of optimizationof protection and safety.

3.78. Employers, registrants and licensees shall ensure that workers exposed
to radiation from sources within a practice that are not required by or directly
related to their work have the same level of protection against such exposure as
members of the public.
3.79. Employers, registrants and licensees shall take such administrative actions
as are necessary to ensure that workers are informed that ensuring protection andsafety is an integral part of a general occupational health and safety programme in52

which they have specific obligations and responsibilities for their own protection
and the protection of others against radiation exposure and for the safety ofsources.
3.80. Employers, registrants and licensees shall record any report received froma worker that identifies circumstances that could affect compliance with therequirements of these Standards, and shall take appropriate action.
3.81. Nothing in these Standards shall be construed as relieving employers fromcomplying with applicable national and local laws and regulations governing
hazards in the workplace.
3.82. Employers, registrants and licensees shall facilitate compliance by workers
with the requirements of these Standards.
Requirement 22: Compliance by workers
Workers shall fulfil their obligations and carry out their duties for protection
and safety.
3.83. Workers:
(a)
(b)
(c)
(d)
(e)
(f)

Shall follow any applicable rules and procedures for protection and safety
as specified by the employer, registrant or licensee;
Shall use properly the monitoring equipment and personal protective
equipment provided;
Shall cooperate with the employer, registrant or licensee with regard toprotection and safety, and programmes for workers’ health surveillance andprogrammes for dose assessment;
Shall provide to the employer, registrant or licensee such informationon their past and present work that is relevant for ensuring effective andcomprehensive protection and safety for themselves and others;
Shall abstain from any wilful action that could put themselves or others insituations that would not be in accordance with the requirements of theseStandards;
Shall accept such information, instruction and training in protection andsafety as will enable them to conduct their work in accordance with therequirements of these Standards.

53

3.84. A worker who identifies circumstances that could adversely affectprotection and safety shall report such circumstances to the employer, registrant
or licensee as soon as possible.
Requirement 23: Cooperation between employers and registrants andlicensees
Employers and registrants and licensees shall cooperate to the extent
necessary for compliance by all responsible parties with the requirementsfor protection and safety.
3.85. If workers are engaged in work that involves or that could involve asource that is not under the control of their employer, the registrant or licensee
responsible for the source and the employer shall cooperate to the extent necessary
for compliance by both parties with the requirements of these Standards.
3.86. Cooperation between the employer and the registrant or licensee shall
include, where appropriate:
(a)

(b)
(c)

The development and use of specific restrictions on exposure and othermeans of ensuring that the measures for protection and safety for workers
who are engaged in work that involves or could involve a source that is
not under the control of their employer are at least as good as those for
employees of the registrant or licensee;
Specific assessments of the doses received by workers as specified in (a)above;
A clear allocation and documentation of the responsibilities of the employer
and those of the registrant or licensee for protection and safety.

3.87. As part of the cooperation between parties, the registrant or licensee
responsible for the source or for the exposure as appropriate:
(a)
(b)
(c)

54

Shall obtain from the employers, including self-employed persons,the previous occupational exposure history of workers as specified inpara. 3.103, and any other necessary information;
Shall provide appropriate information to the employer, including any
available information relevant for compliance with the requirements ofthese Standards that the employer requests;
Shall provide both the worker and the employer with the relevant exposure
records.

Requirement 24: Arrangements under the radiation protection programme
Employers, registrants and licensees shall establish and maintainorganizational, procedural and technical arrangements for the designationof controlled areas and supervised areas, for local rules and for monitoringof the workplace, in a radiation protection programme for occupational
exposure.
Classification of areas: Controlled areas
3.88. Registrants and licensees shall designate as a controlled area any area32 inwhich specific measures for protection and safety are or could be required for:(a)(b)

Controlling exposures or preventing the spread of contamination in normal
operation;
Preventing or limiting the likelihood and magnitude of exposures in
anticipated operational occurrences and accident conditions.

3.89. In defining the boundaries of any controlled area, registrants and licensees
shall take account of the magnitude of the exposures expected in normal
operation, the likelihood and magnitude of exposures in anticipated operational
occurrences and in accident conditions, and the type and extent of the procedures
required for protection and safety.
3.90. Registrants and licensees:
(a)
(b)

(c)

Shall delineate controlled areas by physical means or, where this is notreasonably practicable, by some other suitable means.
Shall, where a source is only intermittently brought into operation orenergized, or is moved from place to place, delineate an appropriate
controlled area by means that are appropriate under the prevailingcircumstances and shall specify exposure times.
Shall display the symbol recommended by the International Organizationfor Standardization [16] and shall display instructions at access points toand at appropriate locations within controlled areas.

32

The transport of radioactive material is regulated in accordance with the IAEA
Transport Regulations [12].

55

(d)
(e)

(f)

(g)

(h)
(i)

Shall establish measures for protection and safety, including, as appropriate,
physical measures to control the spread of contamination and local rules
and procedures for controlled areas.
Shall restrict access to controlled areas by means of administrative
procedures such as the use of work permits, and by physical barriers,
which could include locks or interlocks, the degree of restriction beingcommensurate with the likelihood and magnitude of exposures.
Shall provide, as appropriate, at entrances to controlled areas:(i) Personal protective equipment;(ii) Equipment for individual monitoring and workplace monitoring;(iii) Suitable storage for personal clothing.
Shall provide, as appropriate, at exits from controlled areas:(i) Equipment for monitoring for contamination of skin and clothing;(ii) Equipment for monitoring for contamination of any objects or material
being removed from the area;(iii) Washing or showering facilities and other personal decontamination
facilities;(iv) Suitable storage for contaminated personal protective equipment.
Shall periodically review conditions to assess whether there is any needto modify the measures for protection and safety or the boundaries ofcontrolled areas;
Shall provide appropriate information, instruction and training for persons
working in controlled areas.

Classification of areas: Supervised areas
3.91. Registrants and licensees shall designate as a supervised area any area
not already designated as a controlled area but for which occupational exposure
conditions need to be kept under review, even though specific measures forprotection and safety are not normally needed.
3.92. Registrants and licensees, taking into account the nature, likelihood andmagnitude of exposures or contamination in the supervised areas:
(a)
(b)
(c)

56

Shall delineate the supervised areas by appropriate means;
Shall display approved signs, as appropriate, at access points to supervised
areas;
Shall periodically review conditions to assess whether there is any need forfurther measures for protection and safety or any need for changes to theboundaries of supervised areas.

Local rules and procedures and personal protective equipment
3.93. Employers, registrants and licensees shall minimize the need to rely on
administrative controls and personal protective equipment for protection andsafety by providing well engineered controls and satisfactory working conditions,in accordance with the following hierarchy of preventive measures:
(1)
(2)
(3)

Engineered controls;
Administrative controls;
Personal protective equipment.

3.94. Employers, registrants and licensees, in consultation with workers, or
through their representatives where appropriate:
(a)
(b)
(c)
(d)

(e)

Shall establish in writing local rules and procedures that are necessary forprotection and safety for workers and other persons;
Shall include in the local rules and procedures any relevant investigationlevel or authorized level, and the procedures to be followed in the eventthat any such level is exceeded;
Shall make the local rules and procedures and the measures for protection
and safety known to those workers to whom they apply and to other persons
who may be affected by them;
Shall ensure that any work in which workers are or could be subject tooccupational exposure is adequately supervised and shall take all reasonable
steps to ensure that the rules, procedures, and measures for protection andsafety are observed;
Shall designate, as appropriate, a radiation protection officer in accordancewith criteria established by the regulatory body.

3.95. Employers, registrants and licensees shall ensure that:
(a)

(b)

Workers are provided with suitable and adequate personal protective
equipment that meets relevant standards or specifications, including as
appropriate:(i) Protective clothing;(ii) Respiratory protective equipment the characteristics of which are
made known to the users;(iii) Protective aprons, protective gloves and organ shields.
Where appropriate, workers receive adequate instruction in the proper useof respiratory protective equipment, including testing for good fit.

57

(c)
(d)
(e)

Tasks requiring the use of certain personal protective equipment areassigned only to workers who on the basis of medical advice are capable ofsafely sustaining the extra effort necessary.
All personal protective equipment, including equipment for use in an
emergency, is maintained in proper condition and, if appropriate, is tested
at regular intervals.
If the use of personal protective equipment is considered for any given task,
account is taken of any additional exposure that could result owing to theadditional time taken or the inconvenience, and of any non-radiologicalrisks that might be associated with using personal protective equipment
while performing the task.

Monitoring of the workplace
3.96. Registrants and licensees, in cooperation with employers where appropriate,shall establish, maintain and keep under review a programme for workplacemonitoring under the supervision of a radiation protection officer or qualified
expert.
3.97. The type and frequency of workplace monitoring:
(a)

(b)

Shall be sufficient to enable:(i) Evaluation of the radiological conditions in all workplaces;(ii) Assessment of exposures in controlled areas and supervised areas;(iii) Review of the classification of controlled areas and supervised areas.
Shall be based on dose rate, activity concentration in air and surface
contamination, and their expected fluctuations, and on the likelihood andmagnitude of exposures in anticipated operational occurrences and accident
conditions.

3.98. Registrants and licensees, in cooperation with employers where appropriate,shall maintain records of the findings of the workplace monitoring programme.
The findings of the workplace monitoring programme shall be made available toworkers, through their representatives where appropriate.
Requirement 25: Assessment of occupational exposure and workers’ healthsurveillance
Employers, registrants and licensees shall be responsible for making
arrangements for assessment and recording of occupational exposures andfor workers’ health surveillance.
58

Assessment of occupational exposure
3.99. Employers, as well as self-employed persons, and registrants and licensees
shall be responsible for making arrangements for assessment of the occupational
exposure of workers, on the basis of individual monitoring where appropriate, andshall ensure that arrangements are made with authorized or approved dosimetry
service providers that operate under a quality management system.
3.100. For any worker who usually works in a controlled area, or who
occasionally works in a controlled area and may receive a significant dosefrom occupational exposure, individual monitoring shall be undertaken whereappropriate, adequate and feasible. In cases where individual monitoring of theworker is inappropriate, inadequate or not feasible, the occupational exposure
shall be assessed on the basis of the results of workplace monitoring andinformation on the locations and durations of exposure of the worker33.
3.101. For any worker who regularly works in a supervised area or who entersa controlled area only occasionally, the occupational exposure shall be assessedon the basis of the results of workplace monitoring or individual monitoring, as
appropriate.
3.102. Employers shall ensure that workers who could be subject to exposuredue to contamination are identified, including workers who use respiratory
protective equipment. Employers shall arrange for appropriate monitoring to theextent necessary to demonstrate the effectiveness of the measures for protection
and safety and to assess intakes of radionuclides and the committed effective
doses.
Records of occupational exposure
3.103. Employers, registrants and licensees shall maintain records ofoccupational exposure34 for every worker for whom assessment of occupational
exposure is required in paras 3.99–3.102.

33

The distinction between types of worker in paras 3.100 and 3.101 for the purposes ofmonitoring has similarities to the distinction between category A and category B workers in
European Union legislation [18].
34
Records of occupational exposure are also referred to as ‘exposure records’ or ‘dose
records’.

59

3.104. Records of occupational exposure for each worker shall be maintained
during and after the worker’s working life, at least until the former worker attains
or would have attained the age of 75 years, and for not less than 30 years after
cessation of the work in which the worker was subject to occupational exposure.
3.105. Records of occupational exposure shall include:
(a)
(b)
(c)
(d)

Information on the general nature of the work in which the worker was
subject to occupational exposure;
Information on dose assessments, exposures and intakes at or above therelevant recording levels specified by the regulatory body and the data
upon which the dose assessments were based;
When a worker is or has been exposed while in the employ of more than
one employer, information on the dates of employment with each employer
and on the doses, exposures and intakes in each such employment;
Records of any assessments made of doses, exposures and intakes due toactions taken in an emergency or due to accidents or other incidents, whichshall be distinguished from assessments of doses, exposures and intakes
due to normal conditions of work and which shall include references toreports of any relevant investigations.

3.106. Employers, registrants and licensees:
(a)
(b)
(c)
(d)
(e)

Shall provide workers with access to records of their own occupational
exposure;
Shall provide the supervisor of the programme for workers’ healthsurveillance, the regulatory body and the relevant employer with access toworkers’ records of occupational exposure;
Shall facilitate the provision of copies of workers’ exposure records to new
employers when workers change employment;
Shall make arrangements for the retention of exposure records for former
workers by the employer, registrant or licensee, as appropriate;
Shall, in complying with (a)–(d) above, give due care and attention tomaintaining the confidentiality of records.

3.107. If employers, registrants and licensees cease to conduct activities
in which workers are subject to occupational exposure, they shall makearrangements for the retention of workers’ records of occupational exposure by
the regulatory body or a State registry, or by a relevant employer, registrant or
licensee, as appropriate.

60

Workers’ health surveillance
3.108. Programmes for workers’ health surveillance as required in para. 3.76(f):(a)(b)

Shall be based on the general principles of occupational health [19];Shall be designed to assess the initial fitness and continuing fitness ofworkers for their intended tasks.

3.109. If one or more workers are to be engaged in work in which they areor could be exposed to radiation from a source that is not under the control of
their employer, the registrant or licensee responsible for the source shall, as aprecondition for the engagement of such workers, make with the employer any
special arrangements for workers’ health surveillance that are needed to comply
with the rules established by the regulatory body or other relevant authority.
Requirement 26: Information, instruction and training
Employers, registrants and licensees shall provide workers with adequate
information, instruction and training for protection and safety.
3.110. Employers, in cooperation with registrants and licensees:
(a)

(b)
(c)

Shall provide all workers with adequate information on health risks dueto their occupational exposure in normal operation, anticipated operational
occurrences and accident conditions, adequate instruction and training andperiodic retraining in protection and safety, and adequate information on
the significance of their actions for protection and safety;
Shall provide those workers who could be involved in or affected by the
response to an emergency with appropriate information, and adequate
instruction and training and periodic retraining, for protection and safety;
Shall maintain records of the training provided to individual workers.

Requirement 27: Conditions of service
Employers, registrants and licensees shall not offer benefits as substitutes
for measures for protection and safety.
3.111. The conditions of service of workers shall be independent of whether
they are or could be subject to occupational exposure. Special compensatory
arrangements, or preferential consideration with respect to salary, special
insurance coverage, working hours, length of vacation, additional holidays
61

or retirement benefits, shall neither be granted nor be used as substitutes formeasures for protection and safety in accordance with the requirements of theseStandards.
3.112. Employers shall make all reasonable efforts to provide workers
with suitable alternative employment in circumstances for which it has been
determined, either by the regulatory body or in the framework of the programme
for workers’ health surveillance in accordance with the requirements ofthese Standards, that workers, for health reasons, may no longer continue inemployment in which they are or could be subject to occupational exposure.
Requirement 28: Special arrangements for protection and safety for female
workers and for persons under 18 years of age undergoing training
Employers, registrants and licensees shall make special arrangements forfemale workers, as necessary, for protection of the embryo or fetus andbreastfed infants. Employers, registrants and licensees shall make special
arrangements for protection and safety for persons under 18 years of age
who are undergoing training.
3.113. Employers, in cooperation with registrants and licensees, shall provide
female workers who are liable to enter controlled areas or supervised areas or
who may undertake emergency duties with appropriate information on:
(a)
(b)
(c)

The risk to the embryo or fetus due to exposure of a pregnant woman;
The importance for a female worker of notifying her employer as soon as
possible if she suspects that she is pregnant35 or if she is breast-feeding;
The risk of health effects for a breastfed infant due to ingestion ofradioactive substances.

3.114. Notification of the employer by a female worker if she suspects that
she is pregnant or if she is breast-feeding shall not be considered a reason to
exclude the female worker from work. The employer of a female worker, who
has been notified of her suspected pregnancy or that she is breast-feeding, shalladapt the working conditions in respect of occupational exposure so as to ensure

35

Notification of an employer of a suspected pregnancy or of breast-feeding cannot bemade a requirement on a female worker in these Standards. However, it is necessary that all
female workers understand the importance of making such notifications so that their working
conditions may be modified accordingly.

62that the embryo or fetus or the breastfed infant is afforded the same broad level ofprotection as is required for members of the public.
3.115. Employers, registrants and licensees shall ensure that no person under
the age of 16 years is or could be subject to occupational exposure.
3.116. Employers, registrants and licensees shall ensure that persons under theage of 18 years are allowed access to a controlled area only under supervisionand only for the purpose of training for employment in which they are or could
be subject to occupational exposure or for the purpose of studies in which sources
are used.
PUBLIC EXPOSURE
Scope
3.117. The requirements in respect of public exposure in planned exposure
situations (paras 3.118–3.144) apply to public exposure due to a practice or asource within a practice, as referred to in paras 3.1–3.3. For exposure due tonatural sources, such requirements apply only to the types of public exposure
specified in para. 3.4(a) and (b).
Requirement 29: Responsibilities of the government and the regulatory bodyspecific to public exposure
The government or the regulatory body shall establish the responsibilities
of relevant parties that are specific to public exposure, shall establish andenforce requirements for optimization, and shall establish, and the regulatory
body shall enforce compliance with, dose limits for public exposure.
3.118. The government or the regulatory body shall establish the responsibilities
of registrants and licensees, of suppliers, and of providers of consumer products36
in relation to the application of requirements for public exposure in planned
exposure situations.

36

The term ‘providers of consumer products’ includes the designers, manufacturers,
producers, constructors, installers, distributors, sellers, and importers and exporters of consumer
products.

633.119. The government or the regulatory body shall establish and enforce
requirements for the optimization of protection and safety for situations in which
individuals are or could be subject to public exposure.
3.120. The government or the regulatory body shall establish or approve
constraints on dose and constraints on risk to be used in the optimization ofprotection and safety for members of the public. When establishing or approving
constraints in respect of a source within a practice, the government or the
regulatory body shall take into account, as appropriate:
(a)
(b)
(c)

(d)

The characteristics of the source and of the practice that are of relevance forpublic exposure;Good practice in the operation of similar sources;
Dose contributions from other authorized practices or from possible futureauthorized practices37, estimated at the design and planning stage, so thatthe total dose to members of the public is not expected to exceed the dose
limit at any time after the start of operation of the source;
The views of interested parties.

3.121. The government or the regulatory body shall establish, and the regulatory
body shall enforce compliance with, the dose limits specified in Schedule III for
public exposure.
3.122. Before authorization of a new or modified practice, the regulatory
body shall require the submission of, and shall review, the safety assessments(paras 3.29–3.36) and other design related documents from the responsible parties
that address the optimization of protection and safety, the design criteria and thedesign features relating to the assessment of exposure and potential exposure ofmembers of the public.
3.123. The regulatory body shall establish or approve operational limits andconditions relating to public exposure, including authorized limits for discharges.
These operational limits and conditions:(a)Shall be used by registrants and licensees as the criteria for demonstrationof compliance after the commencement of operation of a source;

37

Dose contributions from possible future authorized practices have to be anticipated in
an assessment made on the basis of realistic assumptions.

64

(b)
(c)
(d)
(e)

Shall correspond to doses below the dose limits with account taken of theresults of optimization of protection and safety;
Shall reflect good practice in the operation of similar facilities or activities;
Shall allow for operational flexibility;
Shall take into account the results of the prospective assessment forradiological environmental impacts that is undertaken in accordance withrequirements of the regulatory body (see paras 3.9(e) and 3.15(d)).

3.124. When a source within a practice could cause public exposure outside theterritory or other area under the jurisdiction or control of the State in which thesource is located, the government or the regulatory body:
(a)
(b)
(c)

Shall ensure that the assessment for radiological impacts includes those
impacts outside the territory or other area under the jurisdiction or controlof the State;
Shall, to the extent possible, establish requirements for the control ofdischarges;
Shall arrange with the affected State the means for the exchange of
information and consultations, as appropriate.

Requirement 30: Responsibilities of relevant parties specific to public
exposure
Relevant parties shall apply the system of protection and safety to protect
members of the public against exposure.
General considerations
3.125. Registrants and licensees, in cooperation with suppliers and with
providers of consumer products, shall apply the requirements of these Standards
and shall verify and demonstrate compliance with them, as specified by theregulatory body, in relation to any public exposure delivered by a source forwhich they have responsibility.
3.126. Registrants and licensees, in cooperation with suppliers, in applying
the principle of optimization of protection and safety in the design, planning,
operation and decommissioning of a source (or for closure and the post-closure
period for waste disposal facilities), shall take into account:(a)Possible changes in any conditions that could affect exposure of membersof the public, such as changes in the characteristics and use of the source,
65

(b)
(c)
(d)

changes in environmental dispersion conditions, changes in exposure
pathways or changes in values of parameters used for the determination of
the representative person;
Good practice in the operation of similar sources or the conduct of similar
practices;
Possible buildup and accumulation in the environment of radioactive
substances from discharges during the lifetime of the source;
Uncertainties in the assessment of doses, especially uncertainties incontributions to doses if the source and the representative person are
separated in space or in time.

3.127. Registrants and licensees, for sources under their responsibility, shallestablish, implement and maintain:
(a)
(b)

(c)
(d)
(e)
(f)
(g)
(h)

Policies, procedures and organizational arrangements for protection andsafety in relation to public exposure, in accordance with the requirementsof these Standards.
Measures for ensuring:(i) Optimization of protection and safety;(ii) Limitation of exposure of members of the public from such sources, inaccordance with the authorization.
Measures for ensuring the safety of such sources.
Provision for suitable and adequate resources (including facilities,
equipment and services) for the protection and safety of members of the
public, commensurate with the likelihood and magnitude of exposures.
Programmes for appropriate training of personnel having functions relevant
to protection and safety of members of the public, as well as periodic
retraining as required, to ensure the necessary level of competence.
Provision for appropriate monitoring equipment, monitoring programmes
and methods for assessing public exposure.
Adequate records of monitoring programmes.
Emergency plans, emergency procedures and emergency arrangements, inaccordance with the nature and magnitude of the radiation risks associatedwith the sources.

Visitors
3.128. Registrants and licensees, in cooperation with employers whereappropriate:

66

(a)
(b)
(c)

(d)

Shall apply the relevant requirements of these Standards in respect of public
exposure for visitors to a controlled area or a supervised area;
Shall ensure that visitors are accompanied in any controlled area by aperson who knows the measures for protection and safety for the controlled
area;
Shall provide adequate information and instructions to visitors before they
enter a controlled area or a supervised area, so as to provide for protection
and safety for visitors and for other individuals who could be affected bytheir actions;
Shall ensure that adequate control is maintained over the entry of visitors
to a controlled area or a supervised area, including the use of signs for suchareas.

External exposure and contamination in areas accessible to members of the
public3.129. Registrants and licensees shall ensure that if a source can give rise toexternal exposure of members of the public:
(a)

(b)

The floor plans and arrangements of equipment for all new installations
utilizing such sources, as well as all significant modifications to existing
installations, are subject, as appropriate, to review and approval by theregulatory body prior to commissioning;
Shielding and other measures for protection and safety, including access
control, are provided as appropriate for restricting public exposure,in particular at open sites such as for some applications of industrial
radiography.

3.130. Registrants and licensees shall ensure, as appropriate, that:(a)(b)

Specific provisions for confinement are established for the design andoperation of a source that could cause the spread of contamination in areasthat are accessible to members of the public;
Measures for protection and safety are implemented for restricting public
exposure due to contamination in areas within a facility that are accessible
to members of the public.

67

Requirement 31: Radioactive waste and discharges
Relevant parties shall ensure that radioactive waste and discharges ofradioactive material to the environment are managed in accordance with theauthorization.
Radioactive waste
3.131. Registrants and licensees, in cooperation with suppliers, as appropriate:
(a)
(b)
(c)

(d)

(e)
(f)

Shall ensure that any radioactive waste generated is kept to the minimum
practicable in terms of both activity and volume;
Shall ensure that radioactive waste is managed in accordance with therequirements of these Standards and the requirements of other applicable
IAEA standards, and in accordance with the relevant authorization;
Shall ensure that there is separate processing of radioactive wasteof different types, where warranted by differences in factors such asradionuclide content, half-life, activity concentration, volume, and physicaland chemical properties, taking into account the available options forstorage and disposal of radioactive waste, without precluding the mixing ofradioactive waste for purposes of protection and safety;
Shall ensure that activities for the predisposal management of and forthe disposal of radioactive waste are conducted in accordance with therequirements of applicable IAEA standards38, and in accordance with theauthorization;
Shall maintain an inventory of all radioactive waste that is generated,
stored, transferred or disposed of;
Shall develop and implement a strategy for radioactive waste management
and shall include appropriate evidence that protection and safety is
optimized.

Discharges
3.132. Registrants and licensees, in cooperation with suppliers, in applying for
an authorization for discharges, as appropriate:38

Requirements for the predisposal management of radioactive waste are established inRef. [10] and requirements for the disposal of radioactive waste are established in Ref. [11].

68

(a)
(b)
(c)
(d)
(e)

Shall determine the characteristics and activity of the material to bedischarged, and the possible points and methods of discharge;
Shall determine by an appropriate pre-operational study all significant
exposure pathways by which discharged radionuclides could give rise toexposure of members of the public;
Shall assess the doses to the representative person due to the planned
discharges;
Shall consider the radiological environmental impacts in an integrated
manner with features of the system of protection and safety, as required by
the regulatory body;
Shall submit to the regulatory body the findings of (a)–(d) above as an input
to the establishment by the regulatory body, in accordance with para. 3.123,
of authorized limits on discharges and conditions for their implementation.

3.133. Registrants and licensees shall ensure that operational limits andconditions relating to public exposure are met in accordance with paras 3.123
and 3.124.
3.134. Registrants and licensees shall review and modify their discharge control
measures, as appropriate and in agreement with the regulatory body, taking into
account:(a)(b)

Operating experience;
Any changes in exposure pathways or in the characteristics of therepresentative person that could affect the assessment of doses due to thedischarges.

Requirement 32: Monitoring and reporting
The regulatory body and relevant parties shall ensure that programmes forsource monitoring and environmental monitoring are in place and that theresults from the monitoring are recorded and are made available.
3.135. The regulatory body shall be responsible, as appropriate, for:(a)

Review and approval of monitoring programmes of registrants andlicensees, which shall be sufficient for:(i) Verifying compliance with the requirements of these Standards inrespect of public exposure in planned exposure situations;(ii) Assessing doses from public exposure.

69

(b)
(c)
(d)

(e)
(f)

Review of periodic reports on public exposure (including results ofmonitoring programmes and dose assessments) submitted by registrants
and licensees.
Making provision for an independent monitoring programme.
Assessment of the total public exposure due to authorized sources andpractices in the State on the basis of monitoring data provided by registrants
and licensees and with the use of data from independent monitoring andassessments.
Making provision for maintaining records of discharges, results ofmonitoring programmes and results of assessments of public exposure.
Verification of compliance of an authorized practice with the requirementsof these Standards for the control of public exposure.

3.136. The regulatory body shall publish or shall make available on request,
as appropriate, results from source monitoring and environmental monitoring
programmes and assessments of doses from public exposure.
3.137. Registrants and licensees shall, as appropriate:
(a)

(b)
(c)

(d)

(e)

70

Establish and implement monitoring programmes to ensure that public
exposure due to sources under their responsibility is adequately assessed
and that the assessment is sufficient to verify and demonstrate compliancewith the authorization. These programmes shall include monitoring of thefollowing, as appropriate:(i) External exposure due to such sources;(ii) Discharges;(iii) Radioactivity in the environment;(iv) Other parameters important for the assessment of public exposure.
Maintain appropriate records of the results of the monitoring programmes
and estimated doses to members of the public.
Report or make available to the regulatory body the results of the monitoring
programme at approved intervals, including, as applicable, the levels andcomposition of discharges, dose rates at the site boundary and in premises
open to members of the public, results of environmental monitoring andretrospective assessments of doses to the representative person.
Report promptly to the regulatory body any levels exceeding the operational
limits and conditions relating to public exposure, including authorized
limits on discharges, in accordance with reporting criteria established by
the regulatory body.
Report promptly to the regulatory body any significant increase in dose
rate or concentrations of radionuclides in the environment that could be

(f)

(g)
(h)

attributed to the authorized practice, in accordance with reporting criteria
established by the regulatory body.
Establish and maintain a capability to conduct monitoring in an emergency
in the event of unexpected increases in radiation levels or in concentrationsof radionuclides in the environment due to an accident or other unusual
event attributed to the authorized source or facility.
Verify the adequacy of the assumptions made for the assessment of public
exposure and the assessment for radiological environmental impacts.
Publish or make available on request, as appropriate, results from source
monitoring and environmental monitoring programmes and assessments ofdoses from public exposure.

Requirement 33: Consumer products
Providers of consumer products shall ensure that consumer products are notmade available to the public unless their use by members of the public has
been justified, and either their use has been exempted or their provision to
the public has been authorized.
3.138. Providers of consumer products shall ensure that consumer products are
not made available to the public unless the justification of their use by membersof the public has been approved by the government or the regulatory body,and either their use has been exempted on the basis of the criteria specified in
Schedule I or their provision to the public has been authorized.
3.139. Upon receipt of a request for authorization to provide consumer products
to the public, the regulatory body:
(a)
(b)
(c)
(d)

Shall require the provider of the consumer product to provide documents todemonstrate compliance with the requirements in paras 3.138–3.144;
Shall verify the assessments and the selection of parameters presented in
the request for authorization;
Shall determine whether the end use of the consumer product can be
exempted;
Shall authorize the provision to the public of the consumer product, whereappropriate, subject to specific conditions of authorization.

3.140. Providers of consumer products:(a)Shall comply with the conditions of the authorization to provide consumer
products to the public;
71

(b)
(c)

Shall ensure that consumer products comply with the requirements of theseStandards;
Shall plan for appropriate arrangements for the servicing, maintenance,
recycling or disposal of consumer products.

3.141. The design and manufacture of consumer products, with regard tofeatures that could affect exposure during normal handling, transport and use,
as well as in the event of mishandling, misuse, accident or disposal, shall be
subject to the optimization of protection and safety. In this regard, designers,
manufacturers and other providers of consumer products shall take into accountthe following:
(a)
(b)
(c)
(d)
(e)

The various radionuclides that could be used in consumer products andtheir radiation types, energies, activities and half-lives;
The chemical and physical forms of the radionuclides that could be usedin consumer products and their significance for protection and safety innormal conditions and abnormal conditions;
The containment and shielding of radioactive substances in consumer
products and access to these radioactive substances in normal conditions
and abnormal conditions;
The need for servicing or repair of consumer products and ways in which
this could be done;
Relevant experience with similar consumer products.

3.142. Providers of consumer products shall ensure that:
(a)

(b)

Where practicable, a legible label is firmly affixed to a visible surface ofeach consumer product that:(i) States that the consumer product contains radioactive substances andidentifies the radionuclides and their activities;(ii) States that the provision of the consumer product to the public has
been authorized by the regulatory body;(iii) Provides information on required or recommended options forrecycling or disposal.
The information specified in (a) above is also printed legibly on the retailpackaging of the consumer product.

3.143. Providers of consumer products shall provide clear and appropriate
information and instructions with each consumer product on:

72

(a)
(b)
(c)
(d)
(e)

Correct installation, use and maintenance of the consumer product;
Servicing and repair;
The radionuclides and their activities at a specified date;
Dose rates in normal operation and during servicing and repair;
Required or recommended options for recycling or disposal.

3.144. Providers of consumer products shall provide the consumer productretailers with appropriate information on safety and instructions on their transportand storage.
MEDICAL EXPOSURE
Scope
3.145. The requirements in respect of medical exposure in planned exposure
situations (paras 3.146–3.185) apply to all medical exposures39, including
intended, unintended and accidental exposures.
3.146. Dose limits do not apply to medical exposures.
Requirement 34: Responsibilities of the government specific to medical
exposure
The government shall ensure that relevant parties are authorized to assume
their roles and responsibilities, and that diagnostic reference levels, dose
constraints, and criteria and guidelines for the release of patients are
established.
3.147. The government, in accordance with paras 2.13–2.28, shall ensure withregard to medical exposures that, as a result of consultation between the healthauthority, relevant professional bodies and the regulatory body, the relevant
parties identified in paras 2.40 and 2.41 are authorized to assume their roles andresponsibilities, and shall ensure that they are notified of their duties in relation toprotection and safety for individuals undergoing medical exposures.

39

Requirements on human imaging using radiation for purposes other than medical
diagnosis, medical treatment or biomedical research (and, hence, not within the scope of
medical exposure) are stated in paras 3.61–3.67.

73

3.148. The government shall ensure, as part of the responsibilities specified inpara. 2.15, that as a result of consultation between the health authority, relevant
professional bodies and the regulatory body, a set of diagnostic reference levels isestablished for medical exposures incurred in medical imaging, including image
guided interventional procedures. In setting such diagnostic reference levels,
account shall be taken of the need for adequate image quality, to enable therequirements of para. 3.169 to be fulfilled. Such diagnostic reference levels shallbe based, as far as possible, on wide scale surveys or on published values that areappropriate for the local circumstances.
3.149. The government shall ensure that, as a result of consultation between
the health authority, relevant professional bodies and the regulatory body, thefollowing are established:
(a)

(b)

Dose constraints, to enable the requirements of paras 3.173 and 3.174,
respectively, to be fulfilled for:(i) Exposures of carers and comforters40;(ii) Exposures due to diagnostic investigations of volunteers participating
in a programme of biomedical research.
Criteria and guidelines for the release of patients who have undergone
therapeutic radiological procedures using unsealed sources or patients who
still retain implanted sealed sources.

Requirement 35: Responsibilities of the regulatory body specific to medical
exposure
The regulatory body shall require that health professionals withresponsibilities for medical exposure are specialized in the appropriate area
and that they fulfil the requirements for education, training and competencein the relevant specialty.
3.150. The regulatory body shall ensure that the authorization for medical
exposures to be performed at a particular medical radiation facility allows
personnel (radiological medical practitioners, medical physicists, medical
radiation technologists and any other health professionals with specific duties
in relation to the radiation protection of patients) to assume the responsibilities
specified in these Standards only if they:40

The selection of constraints for carers and comforters is a complex process in which
a number of factors have to be taken into account, such as the age of the individual and for awoman the possibility of her being pregnant.

74

(a)
(b)
(c)

Are specialized41 in the appropriate area42;
Meet the respective requirements for education, training and competence inradiation protection, in accordance with para. 2.32;
Are named in a list maintained up to date by the registrant or licensee.

Requirement 36: Responsibilities of registrants and licensees specific to
medical exposure
Registrants and licensees shall ensure that no person incurs a medical
exposure unless there has been an appropriate referral, responsibility has
been assumed for ensuring protection and safety, and the person subject
to exposure has been informed as appropriate of the expected benefits andrisks.
3.151. Registrants and licensees shall ensure that no patient, whether
symptomatic or asymptomatic, undergoes a medical exposure unless:
(a)
(b)
(c)
(d)

It is a radiological procedure that has been requested by a referring medical
practitioner and information on the clinical context has been provided, or itis part of an approved health screening programme;
The medical exposure has been justified by means of consultation between
the radiological medical practitioner and the referring medical practitioner,
as appropriate, or it is part of an approved health screening programme;
A radiological medical practitioner has assumed responsibility forprotection and safety in the planning and delivery of the medical exposure
as specified in para. 3.154(a);The patient or the patient’s legal authorized representative has been
informed as appropriate of the expected diagnostic or therapeutic benefitsof the radiological procedure as well as the radiation risks.

3.152. Registrants and licensees shall ensure that no individual incurs a medical
exposure as part of a programme of biomedical research unless the exposure
41‘Specialized’ means specialized as acknowledged by the relevant professional body,
health authority or appropriate organization.
42‘The appropriate area’ means, in the first instance, diagnostic radiology, image guided
interventional procedures, or radiation therapy or nuclear medicine (diagnostic radiologicalprocedures, therapeutic radiological procedures or both). The area of specialization is often
likely to be narrower, however, in particular with regard to the radiological medical practitioner.
Examples are dental, chiropractic or podiatric specialists in the case of diagnostic radiology, andcardiologists, urologists or neurologists in the case of image guided interventional procedures.

75

has been approved by an ethics committee (or other institutional body that has
been assigned functions similar to those of an ethics committee by the relevant
authority) as required in para. 3.161 and a radiological medical practitioner has
assumed responsibility as specified in para. 3.154(a). Registrants and licensees
shall ensure that the requirements specified in para. 3.174 are fulfilled for the
optimization of protection and safety for persons subject to exposure as part of aprogramme of biomedical research.
3.153. Registrants and licensees shall ensure that no individual incurs a medical
exposure as a carer or comforter unless he or she has received, and has indicatedan understanding of, relevant information on radiation protection and informationon the radiation risks prior to providing care and comfort to an individual
undergoing a radiological procedure. Registrants and licensees shall ensure thatthe requirements specified in para. 3.173 are fulfilled for the optimization ofprotection and safety for any radiological procedure in which an individual acts
as a carer or comforter.
3.154. Registrants and licensees shall ensure that:
(a)

(b)

(c)
(d)

(e)

76

The radiological medical practitioner performing or overseeing theradiological procedure has assumed responsibility for ensuring overall
protection and safety for patients in the planning and delivery of the
medical exposure, including the justification of the radiological procedure
as required in paras 3.155–3.161 and the optimization of protection andsafety, in cooperation with the medical physicist and the medical radiation
technologist as required in paras 3.162–3.177;
Radiological medical practitioners, medical physicists, medical radiation
technologists and other health professionals with specific duties in relation
to protection and safety for patients in a given radiological procedure are
specialized in the appropriate area;
Sufficient medical personnel and paramedical personnel are available as
specified by the health authority;
For therapeutic radiological procedures, the requirements of theseStandards for calibration, dosimetry and quality assurance, including theacceptance and commissioning of medical radiological equipment, as
specified in paras 3.167, 3.168(c), 3.170 and 3.171, are fulfilled by or under
the supervision of a medical physicist;
For diagnostic radiological procedures and image guided interventional
procedures, the requirements of these Standards for medical imaging,calibration, dosimetry and quality assurance, including the acceptanceand commissioning of medical radiological equipment, as specified in(f)paras 3.167, 3.168(a) and (b), 3.169, 3.170 and 3.171, are fulfilled byor under the oversight of or with the documented advice of a medical
physicist, whose degree of involvement is determined by the complexity of
the radiological procedures and the associated radiation risks;
Any delegation of responsibilities by a principal party is documented.

Requirement 37: Justification of medical exposures
Relevant parties shall ensure that medical exposures are justified.
3.155. Medical exposures shall be justified by weighing the diagnostic ortherapeutic benefits43 that they are expected to yield against the radiation
detriment that they might cause, with account taken of the benefits and the risksof available alternative techniques that do not involve medical exposure.
3.156. Generic justification of a radiological procedure shall be carried out by
the health authority in conjunction with appropriate professional bodies, and shallbe reviewed from time to time, with account taken of advances in knowledge andtechnological developments.
3.157. The justification of medical exposure for an individual patient shall be
carried out by means of consultation between the radiological medical practitioner
and the referring medical practitioner, as appropriate, with account taken, inparticular for patients who are pregnant or breast-feeding or are paediatric, of:
(a)
(b)
(c)
(d)
(e)

The appropriateness of the request;
The urgency of the radiological procedure;
The characteristics of the medical exposure;
The characteristics of the individual patient;
Relevant information from the patient’s previous radiological procedures.

3.158. Relevant national or international referral guidelines shall be taken into
account for the justification of the medical exposure of an individual patient in aradiological procedure.

43

The diagnostic or therapeutic benefit that medical exposures are expected to yield
may not necessarily be to the person exposed. For patients, this is clearly the case, but for
exposures in biomedical research the benefit is expected to be for biomedical sciences and for
future health care. Similarly, the benefit for carers and comforters might be, for example, thesuccessful performance of a diagnostic procedure on a child.

77

3.159. Justification for radiological procedures to be performed as part of ahealth screening programme for asymptomatic populations shall be carried out
by the health authority in conjunction with appropriate professional bodies.
3.160. Any radiological procedure on an asymptomatic individual that is
intended to be performed for the early detection of disease, but not as part ofan approved health screening programme, shall require specific justification forthat individual by the radiological medical practitioner and the referring medical
practitioner, in accordance with the guidelines of relevant professional bodies
or the health authority. As part of this process, the individual shall be informedin advance of the expected benefits, risks and limitations of the radiologicalprocedure.
3.161. The medical exposure of volunteers as part of a programme ofbiomedical research is deemed to be not justified unless:
(a)

(b)

It is in accordance with the provisions of the Helsinki Declaration [20] andtakes into account the guidelines published by the Council for International
Organizations of Medical Sciences [21], together with the recommendationsof the ICRP [22];It is subject to approval by an ethics committee (or other institutional bodythat has been assigned functions similar to those of an ethics committee by
the relevant authority), subject to any dose constraints that may be specified(as required in paras 3.149(a)(ii) and 3.174), and subject to applicablenational regulations and local regulations.

Requirement 38: Optimization of protection and safety
Registrants and licensees and radiological medical practitioners shall ensurethat protection and safety is optimized for each medical exposure.
Design considerations
3.162. In addition to ensuring that the responsibilities stated in para. 3.49 are
discharged, as applicable, registrants and licensees, in cooperation with suppliers,
shall ensure that medical radiological equipment and software that could
influence the delivery of medical exposure are used only if they conform to theapplicable standards of the International Electrotechnical Commission and theInternational Organization for Standardization or to national standards adopted
by the regulatory body.

78

Operational considerations
3.163. For diagnostic radiological procedures and image guided interventional
procedures, the radiological medical practitioner, in cooperation with the medical
radiation technologist and the medical physicist, and if appropriate with theradiopharmacist or radiochemist, shall ensure that the following are used:(a)(b)

Appropriate medical radiological equipment and software, and, for nuclear
medicine, appropriate radiopharmaceuticals;
Appropriate techniques and parameters to deliver a medical exposure of thepatient that is the minimum necessary to fulfil the clinical purpose of theradiological procedure, with account taken of relevant norms of acceptable
image quality established by relevant professional bodies and of relevant
diagnostic reference levels established in accordance with paras 3.148
and 3.169.

3.164. For therapeutic radiological procedures, the radiological medical
practitioner, in cooperation with the medical physicist and the medical radiation
technologist, shall ensure that for each patient the exposure of volumes other thanthe planning target volume is kept as low as reasonably achievable consistent
with delivery of the prescribed dose to the planning target volume within therequired tolerances.
3.165. For therapeutic radiological procedures in which radiopharmaceuticals
are administered, the radiological medical practitioner, in cooperation with the
medical physicist and the medical radiation technologist, and if appropriate
with the radiopharmacist or radiochemist, shall ensure that for each patient theappropriate radiopharmaceutical with the appropriate activity is selected andadministered, so that the radioactivity is primarily localized in the organ(s) ofinterest, while the radioactivity in the rest of the body is kept as low as reasonably
achievable.
3.166. Registrants and licensees shall ensure that the particular aspects ofmedical exposures are considered in the optimization process for:
(a)
(b)
(c)

Paediatric patients subject to medical exposure;
Individuals subject to medical exposure as part of an approved healthscreening programme;
Volunteers subject to medical exposure as part of a programme ofbiomedical research;

79

(d)
(e)
(f)

Relatively high doses44 to the patient;
Exposure of the embryo or fetus, in particular for radiological proceduresin which the abdomen or pelvis of the pregnant female patient is exposedto the useful radiation beam or could otherwise receive a significant dose;
Exposure of a breastfed infant as a result of a female patient having
undergone a radiological procedure with radiopharmaceuticals.

Calibration
3.167. In accordance with para. 3.154(d) and (e), the medical physicist shallensure that:
(a)
(b)
(c)
(d)

All sources giving rise to medical exposure are calibrated in terms ofappropriate quantities using internationally accepted or nationally accepted
protocols;
Calibrations are carried out at the time of commissioning a unit prior toclinical use, after any maintenance procedure that could affect the dosimetry
and at intervals approved by the regulatory body;
Calibrations of radiation therapy units are subject to independent
verification45 prior to clinical use;
Calibration of all dosimeters used for dosimetry of patients and for thecalibration of sources is traceable to a standards dosimetry laboratory.

Dosimetry of patients
3.168. Registrants and licensees shall ensure that dosimetry of patients is
performed and documented by or under the supervision of a medical physicist,using calibrated dosimeters and following internationally accepted or nationallyaccepted protocols, including dosimetry to determine the following:

44

The term ‘relatively high dose’ is intended to apply in a given context. Clearly, doses
from therapeutic radiological procedures are included in ‘relatively high doses’, as are image
guided interventional procedures. In medical imaging, ‘relatively high doses’ would include
doses from exposures in computed tomography and in radiological procedures in nuclear
medicine with higher doses.
45‘Independent verification’ ideally means verification by a different, independent
medical physicist using different dosimetry equipment. However, other options, such asverification by a second medical physicist or verification using a second set of equipment, oreven using a form of verification by postal thermoluminescence dosimetry, could be acceptable.
In checking for compliance, the regulatory body needs to be aware of the limitations on local
resources.

80

(a)
(b)
(c)

(d)

For diagnostic radiological procedures, typical doses to patients forcommon procedures;
For image guided interventional procedures, typical doses to patients;
For therapeutic radiological procedures, absorbed doses to the planningtarget volume for each patient treated with external beam therapy
and/or brachytherapy and absorbed doses to relevant tissues or organs as
determined by the radiological medical practitioner;
For therapeutic radiological procedures with unsealed sources, typicalabsorbed doses to patients.

Diagnostic reference levels
3.169. Registrants and licensees shall ensure that:(a)(b)

Local assessments, on the basis of the measurements required in para. 3.168,
are made at approved intervals for those radiological procedures for which
diagnostic reference levels have been established (para. 3.148).
A review is conducted to determine whether the optimization of protection
and safety for patients is adequate, or whether corrective action is required
if, for a given radiological procedure:(i) Typical doses or activities exceed the relevant diagnostic reference
level; or(ii) Typical doses or activities fall substantially below the relevant
diagnostic reference level and the exposures do not provide usefuldiagnostic information or do not yield the expected medical benefit to
the patient.

Quality assurance for medical exposures
3.170. Registrants and licensees, in applying the requirements of these Standards
in respect of management systems, shall establish a comprehensive programmeof quality assurance for medical exposures with the active participation of
medical physicists, radiological medical practitioners, medical radiation
technologists and, for complex nuclear medicine facilities, radiopharmacists andradiochemists, and in conjunction with other health professionals as appropriate.
Principles established by the World Health Organization, the Pan American
Health Organization and relevant professional bodies shall be taken into account.
3.171. Registrants and licensees shall ensure that programmes of quality
assurance for medical exposure include, as appropriate to the medical radiation
facility:
81

(a)

(b)
(c)
(d)
(e)

Measurements of the physical parameters of medical radiologicalequipment made by, or under the supervision of, a medical physicist:(i) At the time of acceptance and commissioning of the equipment prior
to its clinical use on patients;(ii) Periodically thereafter;(iii) After any major maintenance procedure that could affect protection
and safety of patients;(iv) After any installation of new software or modification of existing
software that could affect protection and safety of patients.
Implementation of corrective actions if measured values of the physicalparameters mentioned in (a) above are outside established tolerance limits.
Verification of the appropriate physical and clinical factors used inradiological procedures.
Maintaining records of relevant procedures and results.
Periodic checks of the calibration and conditions of operation of dosimetry
equipment and monitoring equipment.

3.172. Registrants and licensees shall ensure that regular and independent
audits are made of the programme of quality assurance for medical exposures,and that their frequency is in accordance with the complexity of the radiologicalprocedures being performed and the associated risks.
Dose constraints
3.173. Registrants and licensees shall ensure that relevant dose constraints(para. 3.149(a)(i)) are used in the optimization of protection and safety in any
radiological procedure in which an individual acts as a carer or comforter.
3.174. Registrants and licensees shall ensure that dose constraints specified
or approved by the ethics committee (or other institutional body that has been
assigned functions similar to those of an ethics committee by the relevant
authority) on a case by case basis as part of a proposal for biomedical research(para. 3.161) are used in the optimization of protection and safety for persons
subject to exposure as part of a programme of biomedical research.
Requirement 39: Pregnant or breast-feeding female patients
Registrants and licensees shall ensure that there are arrangements in place
for appropriate radiation protection in cases where a female patient is or
might be pregnant or is breast-feeding.

82

3.175. Registrants and licensees shall ensure that signs in appropriate
languages are placed in public places, waiting rooms for patients, cubicles andother appropriate places, and that other means of communication are also used
as appropriate46, to request female patients who are to undergo a radiologicalprocedure to notify the radiological medical practitioner, medical radiation
technologist or other personnel in the event that:(a)(b)

She is or might be pregnant;
She is breast-feeding and the scheduled radiological procedure includes theadministration of a radiopharmaceutical.

3.176. Registrants and licensees shall ensure that there are procedures in place
for ascertaining the pregnancy status of a female patient of reproductive capacity
before the performance of any radiological procedure that could result in asignificant dose to the embryo or fetus, so that this information can be consideredin the justification for the radiological procedure (paras 3.155 and 3.156) and in
the optimization of protection and safety (para. 3.166).
3.177. Registrants and licensees shall ensure that there are arrangements inplace for establishing that a female patient is not currently breast-feeding before
the performance of any radiological procedure involving the administration of aradiopharmaceutical that could result in a significant dose to a breastfed infant,so that this information can be considered in the justification for the radiologicalprocedure (paras 3.155 and 3.157) and in the optimization of protection andsafety (para. 3.166).
Requirement 40: Release of patients after radionuclide therapy
Registrants and licensees shall ensure that there are arrangements in place
to ensure appropriate radiation protection for members of the public and forfamily members before a patient is released following radionuclide therapy.
3.178. The radiological medical practitioner shall ensure that no patient who
has undergone a therapeutic radiological procedure with a sealed source or an
unsealed source is discharged from a medical radiation facility until it has been
established by either a medical physicist or the facility’s radiation protection
officer that:46‘Other means of communication’ include explicitly asking female patients whether
they are or might be pregnant or whether they are breast-feeding.

83

(a)

(b)

The activity of radionuclides in the patient is such that doses that could
be received by members of the public and family members would bein compliance with the requirements set by the relevant authorities(para. 3.149(b)); andThe patient or the legal guardian of the patient is provided with:(i) Written instructions for keeping doses to persons in contact with orin the vicinity of the patient as low as reasonably achievable and foravoiding the spread of contamination;(ii) Information on the radiation risks.

Requirement 41: Unintended and accidental medical exposures
Registrants and licensees shall ensure that all practicable measures are taken
to minimize the likelihood of unintended or accidental medical exposures.
Registrants and licensees shall promptly investigate unintended or accidental
medical exposures and, if appropriate, shall implement corrective actions.
3.179. Registrants and licensees, in accordance with the relevant requirementsof paras 2.51, 3.41–3.42 and 3.49–3.50, shall ensure that all practicable measures
are taken to minimize the likelihood of unintended or accidental medical
exposures arising from flaws in design and operational failures of medical
radiological equipment, from failures of and errors in software, or as a result of
human error.
Investigation of unintended and accidental medical exposures
3.180. Registrants and licensees shall promptly investigate any of the following
unintended or accidental medical exposures:
(a)

(b)
(c)
(d)

84

Any medical treatment delivered to the wrong individual or to the wrong
tissue or organ of the patient, or using the wrong radiopharmaceutical,
or with an activity, a dose or dose fractionation differing substantiallyfrom (over or under) the values prescribed by the radiological medical
practitioner, or that could lead to unduly severe secondary effects;
Any diagnostic radiological procedure or image guided interventional
procedure in which the wrong individual or the wrong tissue or organ of thepatient is subject to exposure;Any exposure for diagnostic purposes that is substantially greater than was
intended;Any exposure arising from an image guided interventional procedure that is
substantially greater than was intended;

(e)
(f)

Any inadvertent exposure of the embryo or fetus in the course of performinga radiological procedure;
Any failure of medical radiological equipment, failure of software orsystem failure, or accident, error, mishap or other unusual occurrencewith the potential for subjecting the patient to a medical exposure that is
substantially different from what was intended.

3.181. Registrants and licensees shall, with regard to any unintended or
accidental medical exposures investigated as required in para. 3.180:
(a)
(b)
(c)
(d)

(e)

Calculate or estimate the doses received and the dose distribution within
the patient;
Indicate the corrective actions required to prevent the recurrence of such an
unintended or accidental medical exposure;
Implement all the corrective actions that are under their own responsibility;
Produce and keep, as soon as possible after the investigation or as otherwise
required by the regulatory body, a written record that states the cause of theunintended or accidental medical exposure and includes the information
specified in (a)–(c) above, as relevant, and any other information as
required by the regulatory body; and for significant unintended or accidental
medical exposures or as otherwise required by the regulatory body, submit
this written record, as soon as possible, to the regulatory body, and to therelevant health authority if appropriate;
Ensure that the appropriate radiological medical practitioner informs
the referring medical practitioner and the patient or the patient’s legal
authorized representative of the unintended or accidental medical exposure.

Requirement 42: Reviews and records
Registrants and licensees shall ensure that radiological reviews are
performed periodically at medical radiation facilities and that records aremaintained.
Radiological reviews
3.182. Registrants and licensees shall ensure that radiological reviews are
performed periodically by the radiological medical practitioners at the medical
radiation facility, in cooperation with the medical radiation technologists andthe medical physicists. The radiological review shall include an investigationand critical review of the current practical application of the radiation protection85

principles of justification and optimization for the radiological procedures thatare performed in the medical radiation facility.
Records
3.183. Registrants and licensees shall maintain for a period as specified by theregulatory body and shall make available, as required, the following personnel
records:(a)(b)

Records of any delegation of responsibilities by a principal party(as required in para. 3.154(f));
Records of training of personnel in radiation protection (as required inpara. 3.150(b)).

3.184. Registrants and licensees shall maintain for a period as specified by theregulatory body and shall make available, as required, the following records ofcalibration, dosimetry and quality assurance:
(a)
(b)
(c)
(d)

Records of the results of the calibrations and periodic checks of the relevant
physical and clinical parameters selected during treatment of patients;
Records of dosimetry of patients, as required in para. 3.168;
Records of local assessments and reviews made with regard to diagnostic
reference levels, as required in para. 3.169;
Records associated with the quality assurance programme, as required inpara. 3.171(d).

3.185. Registrants and licensees shall maintain for a period as specified by theregulatory body and shall make available, as required, the following records for
medical exposure:
(a)
(b)
(c)
(d)

86

For diagnostic radiology, information necessary for retrospective
assessment of doses, including the number of exposures and the duration offluoroscopic radiological procedures;
For image guided interventional procedures, information necessary for
retrospective assessment of doses, including the duration of the fluoroscopic
component and the number of images acquired;
For nuclear medicine, the types of radiopharmaceutical administered andtheir activity;
For external beam radiation therapy or brachytherapy, a description of theplanning target volume, the absorbed dose to the centre of the planningtarget volume, and the maximum and minimum absorbed doses delivered

(e)
(f)

to the planning target volume, or equivalent alternative information on
absorbed doses to the planning target volume, and the absorbed doses
to relevant tissues or organs as determined by the radiological medical
practitioner; and in addition, for external beam radiation therapy, the dose
fractionation and the overall treatment time;
Exposure records for volunteers subject to medical exposure as part of aprogramme of biomedical research;
Reports on investigations of unintended and accidental medical exposures(as required in para. 3.181(d)).

4. EMERGENCY EXPOSURE SITUATIONS
SCOPE
4.1. The requirements for emergency exposure situations established in
Section 4 apply to activities undertaken in preparedness for and in response to anuclear or radiological emergency.
GENERIC REQUIREMENTS
Requirement 43: Emergency management system
The government shall ensure that an integrated and coordinated emergency
management system is established and maintained.
4.2. The government shall ensure that an emergency management system isestablished and maintained on the territories and within the jurisdiction of theState for the purposes of emergency response to protect human life, health andthe environment in the event of a nuclear or radiological emergency.
4.3. The emergency management system shall be designed to be commensuratewith the results of a hazard assessment [15] and to enable an effective emergency
response to reasonably foreseeable events (including very low probability events)
in connection with facilities or activities.
4.4. The emergency management system shall be integrated, to the extent
practicable, into an all-hazards emergency management system.
87

4.5. The emergency management system shall provide for essential elements
at the scene, and at the local, national and international level, as appropriate,including the following [15]:
(a)
(b)
(c)
(d)
(e)
(f)

(g)
(h)
(i)
(j)
(k)
(l)

Hazard assessment;
Development and exercising of emergency plans and emergency
procedures;
Clear allocation of responsibilities to persons and organizations having
roles in the arrangements for emergency preparedness and response;
Arrangements for efficient and effective cooperation and coordination
among organizations;
Reliable communication, including public information;
Optimized protection strategies for the implementation and the terminationof measures for the protection of members of the public who could be
subject to exposure in an emergency, including relevant considerations forprotection of the environment;
Arrangements for the protection of emergency workers;
Education and training, including training in radiation protection, of all
persons involved in emergency response and exercising of emergency plans
and emergency procedures;
Preparations for the transition from emergency exposure situation toexisting exposure situation;
Arrangements for the medical response and the public health response in an
emergency;
Provision for individual monitoring and environmental monitoring and for
dose assessment;
Involvement of relevant parties and interested parties.

4.6. The government shall ensure the coordination of its emergency arrangements
and capabilities with the relevant international emergency arrangements.
PUBLIC EXPOSURE
Requirement 44: Preparedness and response for an emergency
The government shall ensure that protection strategies are developed,
justified and optimized at the planning stage, and that emergency response
is undertaken by their timely implementation.

88

4.7. The government shall ensure that protection strategies are developed,
justified and optimized at the planning stage, by using scenarios based on thehazard assessment, for avoiding deterministic effects and reducing the likelihoodof stochastic effects due to public exposure.
4.8. Development of a protection strategy shall include, but shall not be limited
to, the following three successive steps:
(1)

(2)

(3)

A reference level expressed in terms of residual dose shall be set,typically an effective dose in the range of 20–100 mSv, that includes dose
contributions via all exposure pathways. The protection strategy shall
include planning for residual doses to be as low as reasonably achievablebelow the reference level, and the strategy shall be optimized.
On the basis of the outcome of the optimization of the protection strategy,
using the reference level, generic criteria for particular protective actions
and other response actions, expressed in terms of projected dose or of dosethat has been received, shall be developed. If the numerical values of thegeneric criteria47 are exceeded, those protective actions and other response
actions, either individually or in combination, shall be implemented.
Once the protection strategy has been optimized and a set of generic criteria
has been developed, pre-established operational criteria for initiating thedifferent parts of an emergency plan, primarily for the initial phase, shallbe derived from the generic criteria. Operational criteria, such as on-scene
conditions, operational intervention levels and emergency action levels,shall be expressed in terms of parameters or observable conditions.
Arrangements shall be established in advance to revise these operational
criteria, as appropriate, in an emergency, with account taken of theprevailing conditions as they evolve.

4.9. Each protective action shall be justified in the context of the protection
strategy.
4.10. The government shall ensure that in making arrangements for emergency
preparedness and response it is taken into consideration that emergencies are
dynamic, that decisions taken early in the emergency response may influencesubsequent actions, and that different geographical areas may have different
prevailing conditions and there may be different requirements for the response.
47

Table A–1 in the Annex (p. 380) provides a set of generic criteria for use in theprotection strategy that are compatible with reference levels within a range of 20–100 mSv, andprovides further details for specific actions in different time frames.

894.11. The government shall ensure that the response in an emergency exposure
situation is undertaken by the timely implementation of arrangements for
emergency response, including but not limited to:
(a)

(b)
(c)
(d)

Promptly taking protective actions and other response actions to avoid
severe deterministic effects on the basis of observed conditions and, if
possible, before any exposure occurs. Dose levels required to be used as
generic criteria for preventing severe deterministic effects are given in
Table IV.1 of Schedule IV (p. 372);
Assessing the effectiveness of the protective actions and other response
actions taken and modifying them as appropriate;
Comparing residual doses with the applicable reference level, giving
priority to those groups for whom residual doses exceed the reference level;
Implementing further protection strategies as necessary, on the basis ofprevailing conditions and available information.

EXPOSURE OF EMERGENCY WORKERS
Requirement 45: Arrangements for controlling the exposure of emergency
workers
The government shall establish a programme for managing, controlling andrecording the doses received in an emergency by emergency workers.
4.12. The government shall establish a programme for managing, controlling
and recording the doses received in an emergency by emergency workers, whichshall be implemented by response organizations and employers.
4.13. The response organization and employers responsible for ensuring
compliance with the requirements in paras 4.14–4.19 shall be specified in theemergency plan.
4.14. In an emergency exposure situation, the relevant requirements foroccupational exposure in planned exposure situations (paras 3.69–3.116) shall beapplied for emergency workers, in accordance with a graded approach, except as
required in para. 4.15.
4.15. Response organizations and employers shall ensure that no emergency
worker is subject to an exposure in an emergency in excess of 50 mSv other than:

90

(a)
(b)
(c)

For the purposes of saving life or preventing serious injury;
When undertaking actions to prevent severe deterministic effects andactions to prevent the development of catastrophic conditions that could
significantly affect people and the environment; orWhen undertaking actions to avert a large collective dose.

4.16. In the exceptional circumstances specified in para. 4.15, responseorganizations and employers shall make all reasonable efforts to keep doses toemergency workers below the values set out in Table IV.2 of Schedule IV (p. 373).
In addition, emergency workers undertaking actions as a result of which theirdoses could approach or exceed the values set out in Table IV.2 of Schedule IV
shall do so only when the expected benefits to others would clearly outweigh therisks to the emergency workers.
4.17. Response organizations and employers shall ensure that emergency
workers who undertake actions in which the doses received might exceed 50 mSv
do so voluntarily48; that they have been clearly and comprehensively informedin advance of the associated health risks, as well as of available measures forprotection and safety; and that they are, to the extent possible, trained in theactions that they may be required to take.
4.18. Response organizations and employers shall take all reasonable steps toassess and record the doses received in an emergency by emergency workers.
Information on the doses received and information concerning the associatedhealth risks shall be communicated to the workers involved.
4.19. Workers who receive doses in an emergency exposure situation shall notnormally be precluded from incurring further occupational exposure. However,qualified medical advice shall be obtained before any further occupational
exposure if such a worker has received a dose exceeding 200 mSv or at therequest of the worker.

48

The voluntary basis for actions to be taken by emergency workers is usually coveredin emergency arrangements.

91

TRANSITION FROM AN EMERGENCY EXPOSURE SITUATIONTO AN EXISTING EXPOSURE SITUATION
Requirement 46: Arrangements for the transition from an emergency
exposure situation to an existing exposure situation
The government shall ensure that arrangements are in place and are
implemented as appropriate for the transition from an emergency exposure
situation to an existing exposure situation.
4.20. The government shall ensure that, as part of its overall emergency
preparedness, arrangements are in place for the transition from an emergency
exposure situation to an existing exposure situation. The arrangements shalltake into account that different geographical areas may undergo the transition
at different times. The responsible authority shall take the decision to makethe transition to an existing exposure situation. The transition shall be madein a coordinated and orderly manner, by making any necessary transfer of
responsibilities between organizations, with the involvement of relevant
authorities and interested parties.
4.21. Workers undertaking work such as repairs to plant and buildings oractivities for radioactive waste management, or undertaking remedial actions
for the decontamination of the site and surrounding areas, shall be subject to therelevant requirements for occupational exposure in planned exposure situations
stated in Section 3.

5. EXISTING EXPOSURE SITUATIONS
SCOPE
5.1. The requirements for existing exposure situations in Section 5 apply to:(a)92

Exposure due to contamination of areas by residual radioactive material
deriving from:(i) Past activities that were never subject to regulatory control or thatwere subject to regulatory control but not in accordance with therequirements of these Standards;

(b)
(c)

(ii) A nuclear or radiological emergency, after an emergency has been
declared to be ended (as required in para. 4.20).
Exposure due to commodities, including food, feed, drinking water andconstruction materials, that incorporate radionuclides deriving fromresidual radioactive material as stated in para. 5.1(a).
Exposure due to natural sources, including:(i) 222Rn and its progeny and 220Rn and its progeny, in workplaces otherthan those workplaces for which exposure due to other radionuclides
in the uranium decay chain or the thorium decay chain is controlled asa planned exposure situation, in dwellings and in other buildings withhigh occupancy factors for members of the public;(ii) Radionuclides of natural origin, regardless of activity concentration,in commodities, including food, feed, drinking water, agricultural
fertilizer and soil amendments, and construction materials, andresidual radioactive material in the environment;(iii) Materials, other than those stated in (c)(ii) above, in which the activity
concentration of no radionuclide in either the uranium decay chain or
the thorium decay chain exceeds 1 Bq/g and the activity concentrationof 40K does not exceed 10 Bq/g;(iv) Exposure of aircrew and space crew to cosmic radiation.

GENERIC REQUIREMENTS
Requirement 47: Responsibilities of the government specific to existing
exposure situations
The government shall ensure that existing exposure situations that havebeen identified are evaluated to determine which occupational exposuresand public exposures are of concern from the point of view of radiation
protection.
5.2. The government shall ensure that, when an existing exposure situation is
identified, responsibilities for protection and safety are assigned and appropriate
reference levels are established.
5.3. The government shall include in the legal and regulatory framework forprotection and safety (see Section 2) provision for the management of existing
exposure situations. The government, in the legal and regulatory framework, as
appropriate:

93

(a)
(b)
(c)

(d)

Shall specify the exposure situations that are included in the scope ofexisting exposure situations;49
Shall specify the general principles underlying the protection strategies
developed to reduce exposure when remedial actions and protective actions
have been determined to be justified;50
Shall assign responsibilities for the establishment and implementationof protection strategies to the regulatory body and to other relevant
authorities51 and, as appropriate, to registrants, licensees and other parties
involved in the implementation of remedial actions and protective actions;
Shall provide for the involvement of interested parties in decisions
regarding the development and implementation of protection strategies, as
appropriate.

5.4. The regulatory body or other relevant authority assigned to establish aprotection strategy for an existing exposure situation shall ensure that it specifies:(a)(b)

The objectives to be achieved by means of the protection strategy;
Appropriate reference levels.

5.5. The regulatory body or other relevant authority shall implement theprotection strategy, including:(a)(b)

Arranging for evaluation of the available remedial actions and protective
actions for achieving the objectives, and for evaluation of the efficiency of
the actions planned and implemented;
Ensuring that information is available to individuals subject to exposure
on potential health risks and on the means available for reducing their
exposures and the associated risks.

49

In the case of exposure due to radon, the types of situation that are included in the scopeof existing exposure situations will include exposure in workplaces for which the exposure due
to radon is not required by or directly related to the work and for which annual average activity
concentrations due to 222Rn might be expected not to exceed the reference level established inaccordance with para. 5.27.
50
Such actions include remedial actions such as the removal or reduction of the source
giving rise to the exposure, as well as other longer term protective actions such as restriction of
the use of construction materials, restriction of the consumption of foodstuffs and restriction ofland use or of access to land or buildings.
51
In existing exposure situations that do not fall under the jurisdiction of the regulatory
body, another relevant authority such as a health authority may have authority for implementing
measures for protection and safety.

94

PUBLIC EXPOSURE
Scope
5.6. The requirements in respect of public exposure in existing exposure
situations (paras 5.7–5.23) apply to any public exposure arising from thesituations specified in para. 5.1.
Requirement 48: Justification for protective actions and optimization ofprotection and safety
The government and the regulatory body or other relevant authority shallensure that remedial actions and protective actions are justified and that
protection and safety is optimized.
5.7. The government and the regulatory body or other relevant authority shallensure that the protection strategy for the management of existing exposure
situations, established in accordance with paras 5.2 and 5.4, is commensuratewith the radiation risks associated with the existing exposure situation; and that
remedial actions or protective actions are expected to yield sufficient benefits tooutweigh the detriments associated with taking them, including detriments in theform of radiation risks.52
5.8. The regulatory body or other relevant authority and other parties responsible
for remedial actions or protective actions shall ensure that the form, scale andduration of such actions are optimized. While this optimization process isintended to provide optimized protection for all individuals subject to exposure,priority shall be given to those groups for whom the dose exceeds the reference
level. All reasonable steps shall be taken to prevent doses from remaining
above the reference levels. Reference levels shall typically be expressed as anannual effective dose to the representative person in the range of 1–20 mSv orother corresponding quantity, the actual value depending on the feasibility ofcontrolling the situation and on experience in managing similar situations in the
past.

52

The implementation of remedial actions (remediation) does not imply the eliminationof all radioactivity or all traces of radioactive substances. The optimization process may lead toextensive remediation but not necessarily to the restoration of previous conditions.

955.9. The regulatory body or other relevant authority shall periodically review
the reference levels to ensure that they remain appropriate in the light of theprevailing circumstances.
Requirement 49: Responsibilities for remediation of areas with residual
radioactive material
The government shall ensure that provision is made for identifying those
persons or organizations responsible for areas with residual radioactive
material; for establishing and implementing remediation programmes andpost-remediation control measures, if appropriate; and for putting in place
an appropriate strategy for radioactive waste management.
5.10. For the remediation of areas with residual radioactive material derivingfrom past activities or from a nuclear or radiological emergency (para. 5.1(a)), thegovernment shall ensure that provision is made in the framework for protection
and safety for:
(a)

(b)
(c)
(d)

The identification of those persons or organizations responsible for thecontamination of areas and those responsible for financing the remediation
programme, and the determination of appropriate arrangements foralternative sources of funding if such persons or organizations are no longer
present or are unable to meet their liabilities;
The designation of persons or organizations responsible for planning,
implementing and verifying the results of remedial actions;
The establishment of any restrictions on the use of or access to the areas
concerned before, during and, if necessary, after remediation;
An appropriate system for maintaining, retrieval and amendment of records
that cover the nature and the extent of contamination; the decisions madebefore, during and after remediation; and information on verificationof the results of remedial actions, including the results of all monitoring
programmes after completion of the remedial actions.

5.11. The government shall ensure that a strategy for radioactive waste
management is put in place to deal with any waste arising from the remedialactions and that provision for such a strategy is made in the framework forprotection and safety.
5.12. The persons or organizations responsible for the planning, implementationand verification of remedial actions shall, as appropriate, ensure that:

96

(a)
(b)
(c)
(d)

(e)
(f)
(g)
(h)

A remedial action plan, supported by a safety assessment, is prepared andis submitted to the regulatory body or other relevant authority for approval.
The remedial action plan is aimed at the timely and progressive reduction of
the radiation risks and eventually, if possible, at the removal of restrictions
on the use of or access to the area.
Any additional doses received by members of the public as a result of
the remedial actions are justified on the basis of the resulting net benefit,
including consideration of the consequent reduction of the annual dose.
In the choice of the optimized remediation option:(i) Radiological impacts on people and the environment are considered
together with non-radiological impacts on people and the environment,
and with technical, societal and economic factors;(ii) The costs of the transport and management of radioactive waste, theradiation exposure of and health risks to the workers managing theradioactive waste, and any subsequent public exposure associatedwith its disposal are all taken into account.
A mechanism for public information is in place and interested parties are
involved in the planning, implementation and verification of the remedialactions, including any monitoring following remediation.
A monitoring programme is established and implemented.
A system for maintaining adequate records relating to the existing exposure
situation and to actions taken for protection and safety is in place.
Procedures are in place for reporting to the regulatory body or other relevant
authority on any abnormal conditions relevant to protection and safety.

5.13. The regulatory body, in accordance with para. 2.29, or other relevant
authority shall take responsibility, in particular for:
(a)

(b)
(c)
(d)

(e)

Review of the safety assessment submitted by the responsible person ororganization, approval of the remedial action plan and of any subsequentchanges to the remedial action plan, and granting of any necessary
authorization;
Establishment of criteria and methods for assessing safety;
Review of work procedures, monitoring programmes and records;
Review and approval of significant changes to procedures or equipmentthat may have radiological environmental impacts or that may alter the
exposure conditions for workers taking remedial actions or for members of
the public;
Where necessary, establishment of regulatory requirements for control
measures following remediation.

97

5.14. The person or organization responsible for carrying out the remedialactions:
(a)
(b)
(c)

(d)
(e)

Shall ensure that the work, including management of the radioactive waste
arising, is conducted in accordance with the remedial action plan;
Shall take responsibility for all aspects of protection and safety, including
the conduct of a safety assessment;
Shall monitor the area regularly during the remediation so as to verify
levels of contamination, to verify compliance with the requirements forradioactive waste management, and to enable any unexpected levelsof radiation to be detected and the remedial action plan to be modified
accordingly, subject to approval by the regulatory body or other relevant
authority;
Shall perform a radiological survey after completion of remedial actions
to demonstrate that the end point conditions, as established in the remedialaction plan, have been met;
Shall prepare and retain a final remediation report and shall submit a copy
to the regulatory body or other relevant authority.

5.15. After the remedial actions have been completed, the regulatory body orother relevant authority:
(a)
(b)
(c)

(d)

Shall review, amend as necessary and formalize the type, extent andduration of any post-remediation control measures already identified in theremedial action plan, with due consideration of the residual radiation risks.
Shall identify the person or organization responsible for any
post-remediation control measures.
Shall, where necessary, impose specific restrictions for the remediated area
to control:(i) Access by unauthorized persons;(ii) Removal of radioactive material or use of such material, including its
use in commodities;(iii) Future use of the area, including the use of water resources and its use
for the production of food or feed, and the consumption of food fromthe area.
Shall periodically review conditions in the remediated area and, if
appropriate, shall amend or remove any restrictions.

5.16. The person or organization responsible for post-remediation control
measures shall establish and maintain, for as long as required by the regulatory
body or other relevant authority, an appropriate programme, including any
98

necessary provision for monitoring, to verify the long term effectiveness ofthe completed remedial actions for areas in which controls are required after
remediation.
5.17. For those areas with long lasting residual radioactive material, in which
the government has decided to allow habitation and the resumption of social andeconomic activities, the government, in consultation with interested parties, shallensure that arrangements are in place, as necessary, for the continuing control of
exposure with the aim of establishing conditions for sustainable living, including:(a)(b)

Establishment of reference levels for protection and safety that areconsistent with day to day life;
Establishment of an infrastructure to support continuing ‘self-help
protective actions’ in the affected areas, such as by the provision of
information and advice, and by monitoring.

5.18. The conditions prevailing after the completion of remedial actions, if
the regulatory body or other relevant authority has imposed no restrictions orcontrols, shall be considered to constitute the background conditions for any new
facilities and activities or for habitation on the land.
Requirement 50: Public exposure due to radon indoors
The government shall provide information on levels of radon indoors andthe associated health risks and, if appropriate, shall establish and implement
an action plan for controlling public exposure due to radon indoors.
5.19. As part of its responsibilities, as required in para. 5.3, the government shallensure that:(a)(b)

Information is gathered on activity concentrations of radon in dwellings andother buildings with high occupancy factors for members of the public53
through appropriate means, such as representative radon surveys;
Relevant information on exposure due to radon and the associated healthrisks, including the increased risks relating to smoking, is provided to the
public and other interested parties.

53

Buildings with high occupancy factors for members of the public include kindergartens,
schools and hospitals.

99

5.20. Where activity concentrations of radon that are of concern for publichealth are identified on the basis of the information gathered as required inpara. 5.19(a), the government shall ensure that an action plan is establishedcomprising coordinated actions to reduce activity concentrations of radon inexisting buildings and in future buildings, which includes54:
(a)

(b)
(c)
(d)

Establishing an appropriate reference level for 222Rn for dwellings andother buildings with high occupancy factors for members of the public,
with account taken of the prevailing social and economic circumstances,that in general will not exceed an annual average activity concentration due
to 222Rn of 300 Bq/m3 55;
Reducing activity concentrations of 222Rn and consequent exposures tolevels at which protection is optimized;
Giving priority to actions to reduce activity concentrations of 222Rn in thosesituations for which such action is likely to be most effective56;
Including in building codes appropriate preventive measures and corrective
actions to prevent the ingress of 222Rn and to facilitate further actions
wherever necessary.

5.21. The government shall assign responsibility for:(a)(b)

Establishing and implementing the action plan for controlling public
exposure due to 222Rn indoors;
Determining the circumstances under which actions are to be mandatoryor are to be voluntary, with account taken of legal requirements and of theprevailing social and economic circumstances.

54

Guidance on the preparation of an action plan for radon is provided in Ref. [6], forexample.
55
On the assumption of an equilibrium factor for 222Rn of 0.4 and an annual occupancy
of 7000 h, the value of activity concentration due to 222Rn of 300 Bq/m3 corresponds to anannual effective dose of the order of 10 mSv.
56
Examples of giving priority to reducing activity concentrations of 222Rn in thosesituations for which such action is likely to be most effective include (i) specifying the levelsof activity concentrations of 222Rn in dwellings and other buildings with high occupancy
factors at which protection can be considered optimized; (ii) identifying radon prone areas;(iii) identifying characteristics of buildings that are likely to give rise to elevated activity
concentrations of 222Rn; and (iv) identifying and requiring preventive measures for radon in
future buildings that can be introduced at relatively low cost.

100Requirement 51: Exposure due to radionuclides in commodities
The regulatory body or other relevant authority shall establish reference
levels for exposure due to radionuclides in commodities.
5.22. The regulatory body or other relevant authority shall establish specificreference levels for exposure due to radionuclides in commodities such as
construction materials, food and feed, and in drinking water, each of whichshall typically be expressed as, or be based on, an annual effective dose to therepresentative person that generally does not exceed a value of about 1 mSv.
5.23. The regulatory body or other relevant authority shall consider the guideline
levels for radionuclides in food traded internationally that could containradioactive substances as a result of a nuclear or radiological emergency, whichhave been published by the Joint Food and Agriculture Organization of the United
Nations/World Health Organization Codex Alimentarius Commission [23]. The
regulatory body or other relevant authority shall consider the guideline levels forradionuclides contained in drinking water that have been published by the World
Health Organization [24].
OCCUPATIONAL EXPOSURE
Scope
5.24. The requirements in respect of occupational exposure in existing exposure
situations (paras 5.25–5.33) apply to any occupational exposure arising from thesituations specified in para. 5.1.
Requirement 52: Exposure in workplaces
The regulatory body shall establish and enforce requirements for theprotection of workers in existing exposure situations.
5.25. The requirements in respect of public exposure stated in paras 5.7–5.9 shallbe applied for protection and safety for workers in existing exposure situations,other than in those specific situations identified in paras 5.26–5.33.

101

Remediation of areas with residual radioactive material
5.26. Employers shall ensure that the exposure of workers undertaking remedialactions is controlled in accordance with the relevant requirements on occupational
exposure in planned exposure situations as established in Section 3.
Exposure due to radon in workplaces
5.27. The regulatory body or other relevant authority shall establish a strategy
for protection against exposure due to 222Rn in workplaces, including theestablishment of an appropriate reference level for 222Rn. The reference levelfor 222Rn shall be set at a value that does not exceed an annual average activity
concentration of 222Rn of 1000 Bq/m3, with account taken of the prevailing socialand economic circumstances.57
5.28. Employers shall ensure that activity concentrations of 222Rn in workplaces
are as low as reasonably achievable below the reference level established inaccordance with para. 5.27, and shall ensure that protection is optimized.
5.29. If, despite all reasonable efforts by the employer to reduce activity
concentrations of radon, the activity concentration of 222Rn in workplaces
remains above the reference level established in accordance with para. 5.27, therelevant requirements for occupational exposure in planned exposure situations
as stated in Section 3 shall apply.
Exposure of aircrew and space crew due to cosmic radiation
5.30. The regulatory body or other relevant authority shall determine whether
assessment of the exposure of aircrew due to cosmic radiation is warranted.
5.31. Where such assessment is deemed to be warranted, the regulatory bodyor other relevant authority shall establish a framework which shall include areference level of dose and a methodology for the assessment and recording ofdoses received by aircrew from occupational exposure to cosmic radiation.

57

On the assumption of an equilibrium factor for 222Rn of 0.4 and an annual occupancy
of 2000 h, the value of activity concentration due to 222Rn of 1000 Bq/m3 corresponds to anannual effective dose of the order of 10 mSv.

102

5.32. In accordance with para. 5.31:
(a)

(b)

Where the doses of aircrew are likely to exceed the reference level,
employers of aircrew:(i) Shall assess and keep records of doses;(ii) Shall make records of doses available to aircrew.
Employers:(i) Shall inform female aircrew of the risk to the embryo or fetus due toexposure to cosmic radiation and of the need for early notification ofpregnancy;(ii) Shall apply the requirements of para. 3.114 in respect of notificationof pregnancy.

5.33. The regulatory body or other relevant authority shall establish, whereappropriate, a framework for radiation protection that applies to individuals inspace based activities that is appropriate for the exceptional conditions of space.
While the requirements of these Standards in respect of dose limits do not apply
to individuals in space based activities, all reasonable efforts shall be made to
optimize protection for individuals in space based activities by restricting thedoses received by such individuals while not unduly limiting the extent of suchactivities.

103

Schedule I
EXEMPTION AND CLEARANCE
CRITERIA FOR EXEMPTION
I.1. The general criteria for exemption of a practice or a source within a practicefrom some or all of the requirements of these Standards are that:
(a)

(b)

Radiation risks arising from the practice or from a source within thepractice are sufficiently low as not to warrant regulatory control, with noappreciable likelihood of situations arising that could lead to a failure tomeet the general criterion for exemption; orRegulatory control of the practice or the source would yield no net benefit,
in that no reasonable measures for regulatory control would achieve aworthwhile return in terms of reduction of individual doses or of healthrisks.

I.2. A practice or a source within a practice may be exempted without further
consideration from some or all of the requirements of these Standards under theterms of para. I.1(a) provided that under all reasonably foreseeable circumstances
the effective dose expected to be incurred by any individual (normally evaluatedon the basis of a safety assessment) owing to the exempt practice or the exempt
source within the practice is of the order of 10 μSv or less in a year. To take into
account low probability scenarios, a different criterion could be used, namelythat the effective dose expected to be incurred by any individual for such low
probability scenarios does not exceed 1 mSv in a year.
I.3. Under the criteria set out in paras I.1 and I.2, the following sources withinjustified practices are automatically exempted without further consideration fromthe requirements of these Standards, including requirements for notification,
registration or licensing:

105

(a)

(b)
(c)

Material in a moderate amount58 for which either the total activity of anindividual radionuclide present on the premises at any one time or theactivity concentration as used in the practice does not exceed the applicable
exemption level given in Table I.1 (p. 111)59.
Material in bulk amount58 for which the activity concentration of a given
radionuclide of artificial origin used in the practice does not exceed therelevant value given in Table I.2 (p. 124)59.
Radiation generators of a type approved by the regulatory body, or in theform of an electronic tube, such as a cathode ray tube for the display ofvisual images, provided that:(i) They do not in normal operating conditions cause an ambient dose
equivalent rate or a directional dose equivalent rate, as appropriate,exceeding 1 μSv/h at a distance of 0.1 m from any accessible surfaceof the equipment; or(ii) The maximum energy of the radiation generated is no greater than
5 keV.

I.4. For radionuclides of natural origin, exemption of bulk amounts of material
is necessarily considered on a case by case basis60 by using a dose criterion of
the order of 1 mSv in a year, commensurate with typical doses due to natural
background levels of radiation.

58

The exemption values (activity concentrations) presented in Table I.1 have been
calculated on the basis of scenarios involving a moderate amount of material: “The calculated
values apply to practices involving small scale usage of activity where the quantities involved
are at the most of the order of a tonne” (see Ref. [25]). The regulatory body will need toestablish the amounts for which the concentration values in Table I.1 may be applied, bearing in
mind that for many radionuclides, in particular those for which there is no corresponding value
given in Table I.2 (p. 124), a restriction on the amount is not meaningful.
59
The exemption levels set out in Table I.1 (p. 111) and the exemption and clearance
levels set out in Table I.2 are subject to the following considerations: (a) they were derived
using a conservative model based on (i) the criteria of paras I.2 and I.11, respectively, and(ii) a series of limiting (bounding) scenarios for use and disposal (see Refs [25, 26] in the caseof Table I.1 and Ref. [27] in the case of Table I.2); (b) if there is more than one radionuclide, thederived exemption level or derived clearance level for the mixture is determined as specified inparas I.7 and I.14.
60
Material containing radionuclides of natural origin at an activity concentration ofless than 1 Bq/g for any radionuclide in the uranium decay chain or the thorium decay chain
and of less than 10 Bq/g for 40K is not subject to the requirements in Section 3 for planned
exposure situations (para. 3.4(a)); hence, the concept of exemption from the requirements ofthese Standards does not apply for such material.

106I.5. The IAEA Regulations for the Safe Transport of Radioactive Material [12](the IAEA Transport Regulations) do not apply to exempt material or exempt
consignments; that is, they do not apply to material in transport for which theactivity concentration of the material (for exempt material) or the total activityof radionuclides in the consignment (for an exempt consignment) does notexceed the relevant ‘basic radionuclide value’ given in the IAEA Transport
Regulations for exemption from the requirements of the IAEA Transport
Regulations61. Usually, such basic radionuclide values are numerically equal tothe corresponding exempt activity concentrations or exempt activities given in
Table I.1 (p. 111).
I.6. Exemptions may be granted subject to conditions specified by theregulatory body, such as conditions relating to the physical or chemical form of
the radioactive material, and to its use or the means of its disposal. In particular,such an exemption may be granted for equipment containing radioactive material
that is not otherwise automatically exempted without further consideration fromsome or all of the requirements of these Standards under para. I.3(a) provided
that:
(a)
(b)

(c)

(d)

The equipment containing radioactive material is of a type approved by theregulatory body.
The radioactive material:(i) Is in the form of a sealed source that effectively prevents any contact
with the radioactive material and prevents its leakage; or(ii) Is in the form of an unsealed source in a small amount such as sources
used for radioimmunoassay.
In normal operating conditions, the equipment does not cause an ambient
dose equivalent rate or a directional dose equivalent rate, as appropriate,exceeding 1 μSv/h at a distance of 0.1 m from any accessible surface of theequipment.
Necessary conditions for disposal of the equipment have been specified by
the regulatory body.

I.7. For exemption of radioactive material containing more than one
radionuclide, on the basis of the levels given in Tables I.1 (p. 111) andI.2 (p. 124), the condition for exemption from some or all of the requirements of61

For the purposes of material in transport, ‘exemption’ means exemption from therequirements of the IAEA Transport Regulations [12].

107these Standards is that the sum of the individual radionuclide activities or activity
concentrations, as appropriate, is less than the derived exemption level for the
mixture (Xm), determined as follows:
Xm =

1
n

f (i )
(i )
X
i =1

∑

(I.1)

whereis the fraction of activity or activity concentration, as appropriate, ofradionuclide i in the mixture;
X(i) is the applicable level for radionuclide i as given in Table I.1 (p. 111) or
Table I.2 (p. 124);f(i)and n is the number of radionuclides present.
I.8. Radioactive material arising from authorized discharges is exempt from any
requirements for notification, registration or licensing unless otherwise specified
by the regulatory body.
I.9. The values provided in Tables I.1 and I.2 are not intended to be applied tothe control of discharges or to the control of residual radioactive material in theenvironment.
CRITERIA FOR CLEARANCE
I.10. The general criteria for clearance are that:
(a)

(b)

Radiation risks arising from the cleared material are sufficiently low as
not to warrant regulatory control, and there is no appreciable likelihood of
occurrence for scenarios that could lead to a failure to meet the generalcriterion for clearance; orContinued regulatory control of the material would yield no net benefit, inthat no reasonable control measures would achieve a worthwhile return interms of reduction of individual doses or reduction of health risks.

I.11. Material may be cleared without further consideration under the terms ofpara. I.10(a) provided that in reasonably foreseeable circumstances the effective108

dose expected to be incurred by any individual owing to the cleared material
is of the order of 10 μSv or less in a year. To take into account low probability
scenarios, a different criterion can be used, namely that the effective dose
expected to be incurred by any individual for such low probability scenarios does
not exceed 1 mSv in a year.
I.12. Radioactive material within a notified practice or an authorized practice
may be cleared without further consideration provided that:
(a)
(b)
(c)

The activity concentration of an individual radionuclide of artificial origin in
solid form does not exceed the relevant level given in Table I.2 (p. 124)62; orThe activity concentrations of radionuclides of natural origin do not exceed
the relevant level given in Table I.3 (p. 128)63; orFor radionuclides of natural origin in residues that might be recycled into
construction materials64, or the disposal of which is liable to cause thecontamination of drinking water supplies, the activity concentration in
the residues does not exceed specific values derived so as to meet a dosecriterion of the order of 1 mSv in a year, which is commensurate withtypical doses due to natural background levels of radiation.

I.13. Clearance may be granted by the regulatory body for specific situations,on the basis of the criteria of paras I.10 and I.11, with account taken of thephysical or chemical form of the radioactive material, and its use or the meansof its disposal65. Such clearance levels may be specified in terms of activity
concentration per unit mass or activity concentration per unit surface area.

62

The exemption levels set out in Table I.1 (p. 111) and the exemption and clearance
levels set out in Table I.2 are subject to the following considerations: (a) they were derived
using a conservative model based on (i) the criteria of paras I.2 and I.11, respectively, and(ii) a series of limiting (bounding) scenarios for use and disposal (see Refs [25, 26] in the caseof Table I.1 and Ref. [27] in the case of Table I.2); (b) if there is more than one radionuclide, thederived exemption level or derived clearance level for the mixture is determined as specified inparas I.7 and I.14.
63
These values of activity concentration may also be applied for the clearance ofmaterials arising from practices subject to the clearance criteria given in para. I.11, pending
establishment of radionuclide specific values for the radionuclides of natural origin given in
Table I.3.
64
Regulatory control of construction materials incorporating radionuclides is addressedin Section 5 as an existing exposure situation.
65
For example, specific clearance levels may be developed for metals, for rubble frombuildings and waste for disposal in landfill sites.

109

I.14. For clearance of radioactive material containing more than one radionuclideof artificial origin, on the basis of the levels given in Table I.2 (p. 124), thecondition for clearance is that the sum of the activity concentrations forindividual radionuclides is less than the derived clearance level for the mixture(Xm), determined as follows:
Xm =

1
n

f (i )X (i )i =1∑

(I.2)

where
f(i) is the fraction of activity concentration of radionuclide i in the mixture;
X(i) is the applicable level for radionuclide i as given in Table I.2;
and n is the number of radionuclides present.
I.15. For clearance of bulk quantities of material containing a mixture ofradionuclides of natural origin and radionuclides of artificial origin, theconditions given in paras I.12(b) and I.14 both have to be satisfied.

110

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDESRadionuclidea
H-3
Be-7
Be-10
C-11
C-14
N-13
Ne-19
O-15
F-18
Na-22
Na-24
Mg-28
Al-26
Si-31
Si-32
P-32
P-33
S-35
Cl-36
Cl-38
Cl-39
Ar-37
Ar-39
Ar-41
K-40
K-42
K-43
K-44
K-45
Ca-41
Ca-45
Ca-47
Sc-43
Sc-44

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 106
1 × 103
1 × 104
1 × 101
1 × 104
1 × 1021 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 103
1 × 103
1 × 103
1 × 105
1 × 105
1 × 104
1 × 101
1 × 101
1 × 106
1 × 107
1 × 1021 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 105
1 × 104
1 × 101
1 × 101
1 × 101

1 × 109
1 × 107
1 × 106
1 × 106
1 × 107
1 × 109
1 × 109
1 × 109
1 × 106
1 × 106
1 × 105
1 × 105
1 × 105
1 × 106
1 × 106
1 × 105
1 × 108
1 × 108
1 × 106
1 × 105
1 × 105
1 × 108
1 × 104
1 × 109
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 107
1 × 107
1 × 106
1 × 106
1 × 105

Sc-45
Sc-46
Sc-47
Sc-48
Sc-49
Ti-44
Ti-45
V-47
V-48
V-49
Cr-48
Cr-49
Cr-51
Mn-51
Mn-52
Mn-52m
Mn-53
Mn-54
Mn-56
Fe-52
Fe-55
Fe-59
Fe-60
Co-55
Co-56
Co-57
Co-58
Co-58m
Co-60
Co-60m
Co-61
Co-62m
Ni-56
Ni-57

Activity
concentration(Bq/g)

Activity(Bq)

1 × 1021 × 101
1 × 1021 × 101
1 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 104
1 × 1021 × 101
1 × 103
1 × 101
1 × 101
1 × 101
1 × 104
1 × 101
1 × 101
1 × 101
1 × 104
1 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 104
1 × 101
1 × 103
1 × 1021 × 101
1 × 101
1 × 101

1 × 107
1 × 106
1 × 106
1 × 105
1 × 105
1 × 105
1 × 106
1 × 105
1 × 105
1 × 107
1 × 106
1 × 106
1 × 107
1 × 105
1 × 105
1 × 105
1 × 109
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 106
1 × 107
1 × 105
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106111

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Ni-59
Ni-63
Ni-65
Ni-66
Cu-60
Cu-61
Cu-64
Cu-67
Zn-62
Zn-63
Zn-65
Zn-69
Zn-69m
Zn-71m
Zn-72
Ga-65
Ga-66
Ga-67
Ga-68
Ga-70
Ga-72
Ga-73
Ge-66
Ge-67
Ge-68b
Ge-69
Ge-71
Ge-75
Ge-77
Ge-78
As-69
As-70
As-71

112

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 104
1 × 105
1 × 101
1 × 104
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 101
1 × 101
1 × 104
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 104
1 × 103
1 × 101
1 × 1021 × 101
1 × 101
1 × 101

1 × 108
1 × 108
1 × 106
1 × 107
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 108
1 × 106
1 × 105
1 × 106
1 × 105
1 × 105
1 × 106

As-72
As-73
As-74
As-76
As-77
As-78
Se-70
Se-73
Se-73m
Se-75
Se-79
Se-81
Se-81m
Se-83
Br-74
Br-74m
Br-75
Br-76
Br-77
Br-80
Br-80m
Br-82
Br-83
Br-84
Kr-74
Kr-76
Kr-77
Kr-79
Kr-81
Kr-81m
Kr-83m
Kr-85
Kr-85mActivity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 103
1 × 101
1 × 1021 × 103
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 104
1 × 103
1 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 103
1 × 101
1 × 103
1 × 101
1 × 1021 × 1021 × 1021 × 103
1 × 104
1 × 103
1 × 105
1 × 105
1 × 103

1 × 105
1 × 107
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 107
1 × 105
1 × 105
1 × 105
1 × 106
1 × 105
1 × 106
1 × 105
1 × 107
1 × 106
1 × 106
1 × 105
1 × 109
1 × 109
1 × 109
1 × 105
1 × 107
1 × 1010
1 × 1012
1 × 104
1 × 1010

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Kr-87
Kr-88
Rb-79
Rb-81
Rb-81m
Rb-82m
Rb-83b
Rb-84
Rb-86
Rb-87
Rb-88
Rb-89
Sr-80
Sr-81
Sr-82b
Sr-83
Sr-85
Sr-85m
Sr-87m
Sr-89
Sr-90b
Sr-91
Sr-92
Y-86
Y-86m
Y-87b
Y-88
Y-90
Y-90m
Y-91
Y-91m
Y-92
Y-93

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 1021 × 1021 × 101
1 × 101
1 × 103
1 × 101
1 × 1021 × 101
1 × 1021 × 103
1 × 1021 × 1021 × 103
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 103
1 × 1021 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 103
1 × 101
1 × 103
1 × 1021 × 1021 × 1021 × 109
1 × 109
1 × 105
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 105
1 × 107
1 × 105
1 × 105
1 × 107
1 × 105
1 × 105
1 × 106
1 × 106
1 × 107
1 × 106
1 × 106
1 × 104
1 × 105
1 × 106
1 × 105
1 × 107
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105

Y-94
Y-95
Zr-86
Zr-88
Zr-89
Zr-93b
Zr-95
Zr-97b
Nb-88
Nb-89
Nb-89m
Nb-90
Nb-93m
Nb-94
Nb-95
Nb-95m
Nb-96
Nb-97
Nb-98
Mo-90
Mo-93
Mo-93m
Mo-99
Mo-101
Tc-93
Tc-93m
Tc-94
Tc-94m
Tc-95
Tc-95m
Tc-96
Tc-96m
Tc-97

Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 101
1 × 1021 × 1021 × 101
1 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 104
1 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 103
1 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 103
1 × 103

1 × 105
1 × 105
1 × 107
1 × 106
1 × 106
1 × 107
1 × 106
1 × 105
1 × 105
1 × 105
1 × 105
1 × 105
1 × 107
1 × 106
1 × 106
1 × 107
1 × 105
1 × 106
1 × 105
1 × 106
1 × 108
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 107
1 × 108113

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Tc-97m
Tc-98
Tc-99
Tc-99m
Tc-101
Tc-104
Ru-94
Ru-97
Ru-103
Ru-105
Ru-106b
Rh-99
Rh-99m
Rh-100Rh-101
Rh-101m
Rh-102
Rh-102m
Rh-103m
Rh-105
Rh-106m
Rh-107
Pd-100
Pd-101
Pd-103
Pd-107
Pd-109Ag-102
Ag-103Ag-104Ag-104m
Ag-105
Ag-106

114

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 103
1 × 101
1 × 104
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 101
1 × 1021 × 104
1 × 1021 × 101
1 × 1021 × 1021 × 1021 × 103
1 × 105
1 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101

1 × 107
1 × 106
1 × 107
1 × 107
1 × 106
1 × 105
1 × 106
1 × 107
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 106
1 × 108
1 × 107
1 × 105
1 × 106
1 × 107
1 × 106
1 × 108
1 × 108
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106

Ag-106m
Ag-108m
Ag-110m
Ag-111
Ag-112
Ag-115
Cd-104
Cd-107
Cd-109
Cd-113
Cd-113m
Cd-115
Cd-115m
Cd-117
Cd-117m
In-109In-110In-110m
In-111
In-112
In-113m
In-114
In-114m
In-115
In-115m
In-116m
In-117
In-117m
In-119m
Sn-110Sn-111
Sn-113
Sn-117m

Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 101
1 × 101
1 × 103
1 × 101
1 × 101
1 × 1021 × 103
1 × 104
1 × 103
1 × 103
1 × 1021 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 103
1 × 1021 × 103
1 × 1021 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 103
1 × 1021 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 107
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 106
1 × 105
1 × 107
1 × 106
1 × 107
1 × 106

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Sn-119m
Sn-121
Sn-121mb
Sn-123
Sn-123m
Sn-125
Sn-126bSn-127
Sn-128
Sb-115
Sb-116
Sb-116m
Sb-117
Sb-118m
Sb-119
Sb-120
Sb-120m
Sb-122
Sb-124
Sb-124m
Sb-125
Sb-126
Sb-126m
Sb-127
Sb-128
Sb-128m
Sb-129
Sb-130
Sb-131
Te-116
Te-121
Te-121m
Te-123

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 103
1 × 105
1 × 103
1 × 103
1 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 103
1 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 103

1 × 107
1 × 107
1 × 107
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 104
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 105
1 × 105
1 × 106
1 × 105
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106

Te-123m
Te-125m
Te-127
Te-127m
Te-129Te-129m
Te-131
Te-131m
Te-132
Te-133Te-133m
Te-134
I-120
I-120m
I-121
I-123
I-124
I-125
I-126
I-128
I-129
I-130
I-131
I-132
I-132m
I-133
I-134
I-135
Xe-120
Xe-121
Xe-122b
Xe-123
Xe-125

Activity
concentration(Bq/g)

Activity(Bq)

1 × 1021 × 103
1 × 103
1 × 103
1 × 1021 × 103
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 101
1 × 103
1 × 1021 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 103

1 × 107
1 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 105
1 × 106
1 × 107
1 × 105
1 × 105
1 × 106
1 × 105
1 × 105
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 105
1 × 106
1 × 109
1 × 109
1 × 109
1 × 109
1 × 109115

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Xe-127
Xe-129m
Xe-131m
Xe-133m
Xe-133
Xe-135
Xe-135m
Xe-138
Cs-125
Cs-127
Cs-129
Cs-130Cs-131
Cs-132
Cs-134m
Cs-134
Cs-135
Cs-135m
Cs-136
Cs-137b
Cs-138
Ba-126
Ba-128
Ba-131
Ba-131m
Ba-133Ba-133m
Ba-135m
Ba-137m
Ba-139Ba-140b
Ba-141
Ba-142

116

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 103
1 × 103
1 × 104
1 × 103
1 × 103
1 × 103
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 1021 × 103
1 × 101
1 × 103
1 × 101
1 × 104
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 1021 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 1021 × 105
1 × 104
1 × 104
1 × 104
1 × 104
1 × 1010
1 × 109
1 × 109
1 × 104
1 × 105
1 × 105
1 × 106
1 × 106
1 × 105
1 × 105
1 × 104
1 × 107
1 × 106
1 × 105
1 × 104
1 × 104
1 × 107
1 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 105
1 × 106

La-131
La-132
La-135
La-137
La-138
La-140La-141
La-142
La-143Ce-134Ce-135Ce-137Ce-137m
Ce-139Ce-141
Ce-143Ce-144b
Pr-136Pr-137
Pr-138m
Pr-139Pr-142Pr-142m
Pr-143Pr-144Pr-145Pr-147
Nd-136
Nd-138
Nd-139Nd-139m
Nd-141
Nd-147

Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 101
1 × 103
1 × 103
1 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 103
1 × 101
1 × 103
1 × 103
1 × 1021 × 1021 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 1021 × 107
1 × 104
1 × 1021 × 103
1 × 101
1 × 1021 × 103
1 × 1021 × 101
1 × 1021 × 1021 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 105
1 × 105
1 × 105
1 × 105
1 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 107
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 107
1 × 105
1 × 109
1 × 106
1 × 105
1 × 105
1 × 105
1 × 106
1 × 107
1 × 106
1 × 106
1 × 107
1 × 106

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Nd-149
Nd-151
Pm-141
Pm-143
Pm-144
Pm-145
Pm-146
Pm-147
Pm-148
Pm-148m
Pm-149Pm-150Pm-151
Sm-141
Sm-141m
Sm-142Sm-145
Sm-146
Sm-147
Sm-151
Sm-153
Sm-155
Sm-156
Eu-145
Eu-146
Eu-147
Eu-148
Eu-149Eu-150Eu-150m
Eu-152
Eu-152m
Eu-154

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 103
1 × 101
1 × 104
1 × 101
1 × 101
1 × 103
1 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 1021 × 101
1 × 101
1 × 104
1 × 1021 × 1021 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 103
1 × 101
1 × 1021 × 101

1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 107
1 × 106
1 × 107
1 × 105
1 × 106
1 × 106
1 × 105
1 × 106
1 × 105
1 × 106
1 × 107
1 × 107
1 × 105
1 × 104
1 × 108
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106

Eu-155
Eu-156
Eu-157
Eu-158
Gd-145
Gd-146b
Gd-147
Gd-148
Gd-149Gd-151
Gd-152
Gd-153
Gd-159
Tb-147
Tb-149
Tb-150
Tb-151
Tb-153
Tb-154
Tb-155
Tb-156
Tb-156m (24.4 h)
Tb‑156mʹ (5 h)Tb-157
Tb-158
Tb-160
Tb-161
Dy-155Dy-157
Dy-159Dy-165Dy-166
Ho-155

Activity
concentration(Bq/g)

Activity(Bq)

1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 1021 × 101
1 × 1021 × 103
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 103
1 × 104
1 × 104
1 × 101
1 × 101
1 × 103
1 × 101
1 × 1021 × 103
1 × 103
1 × 103
1 × 1021 × 107
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 104
1 × 106
1 × 107
1 × 104
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 107
1 × 106
1 × 107
1 × 107
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106

117

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Ho-157
Ho-159Ho-161
Ho-162
Ho-162m
Ho-164
Ho-164m
Ho-166
Ho-166m
Ho-167
Er-161
Er-165
Er-169Er-171
Er-172
Tm-162
Tm-166
Tm-167
Tm-170
Tm-171
Tm-172
Tm-173
Tm-175
Yb-162
Yb-166
Yb-167
Yb-169
Yb-175
Yb-177
Yb-178Lu-169Lu-170Lu-171

118

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 1021 × 1021 × 1021 × 1021 × 101
1 × 103
1 × 103
1 × 103
1 × 101
1 × 1021 × 101
1 × 103
1 × 104
1 × 1021 × 1021 × 101
1 × 101
1 × 1021 × 103
1 × 104
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 1021 × 1021 × 103
1 × 1021 × 103
1 × 101
1 × 101
1 × 101

1 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 106
1 × 107
1 × 105
1 × 106
1 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 108
1 × 106
1 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 107
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106

Lu-172
Lu-173Lu-174Lu-174m
Lu-176
Lu-176m
Lu-177
Lu-177m
Lu-178Lu-178m
Lu-179
Hf-170
Hf-172b
Hf-173
Hf-175
Hf-177m
Hf-178m
Hf-179m
Hf-180m
Hf-181
Hf-182
Hf-182m
Hf-183
Hf-184
Ta-172
Ta-173
Ta-174
Ta-175
Ta-176
Ta-177
Ta-178
Ta-179Ta-180

Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 103
1 × 103
1 × 101
1 × 1021 × 101
1 × 103
1 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 103
1 × 101

1 × 106
1 × 107
1 × 107
1 × 107
1 × 106
1 × 106
1 × 107
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 107
1 × 106

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Ta-180m
Ta-182
Ta-182m
Ta-183
Ta-184
Ta-185
Ta-186
W-176
W-177
W-178b
W-179
W-181
W-185
W-187
W-188bRe-177
Re-178
Re-181
Re-182
Re-182m
Re-184
Re-184m
Re-186
Re-186m
Re-187
Re-188
Re-188m
Re-189b
Os-180Os-181
Os-182
Os-185
Os-189m

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

Activity
concentration(Bq/g)

Activity(Bq)

1 × 103
1 × 101
1 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 103
1 × 104
1 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 103
1 × 103
1 × 106
1 × 1021 × 1021 × 1021 × 1021 × 101
1 × 1021 × 101
1 × 104

1 × 107
1 × 104
1 × 106
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 106
1 × 107
1 × 107
1 × 107
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 109
1 × 105
1 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 107

Os-191
Os-191m
Os-193
Os-194b
Ir-182
Ir-184
Ir-185
Ir-186
Ir-186m
Ir-187
Ir-188
Ir-189b
Ir-190Ir-190m (3.1 h)
Ir‑190mʹ (1.2 h)
Ir-192
Ir-192m
Ir-193m
Ir-194Ir-194m
Ir-195
Ir-195m
Pt-186
Pt-188b
Pt-189Pt-191
Pt-193
Pt-193m
Pt-195m
Pt-197
Pt-197m
Pt-199Pt-2001 × 1021 × 103
1 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 104
1 × 101
1 × 1021 × 104
1 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 101
1 × 1021 × 1021 × 104
1 × 103
1 × 1021 × 103
1 × 1021 × 1021 × 1021 × 107
1 × 107
1 × 106
1 × 105
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 106
1 × 107
1 × 104
1 × 107
1 × 107
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 107
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106

119

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Au-193
Au-194
Au-195
Au-198
Au-198m
Au-199
Au-200Au-200m
Au-201
Hg-193Hg-193m
Hg-194b
Hg-195
Hg-195mb
Hg-197
Hg-197m
Hg-199m
Hg-203Tl-194Tl-194m
Tl-195Tl-197
Tl-198Tl-198m
Tl-199Tl-200Tl-201
Tl-202
Tl-204
Pb-195m
Pb-198
Pb-199
Pb-200120

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 1021 × 1021 × 101
1 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 1021 × 104
1 × 101
1 × 1021 × 101
1 × 1021 × 107
1 × 106
1 × 107
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 104
1 × 106
1 × 106
1 × 106
1 × 106

Pb-201
Pb-202
Pb-202m
Pb-203
Pb-205
Pb-209
Pb-210b
Pb-211
Pb-212b
Pb-214
Bi-200Bi-201
Bi-202
Bi-203
Bi-205
Bi-206
Bi-207
Bi-210Bi-210mb
Bi-212b
Bi-213
Bi-214Po-203
Po-205
Po-206
Po-207
Po-208Po-209
Po-210At-207
At-211
Fr-222
Fr-223

Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 103
1 × 101
1 × 1021 × 104
1 × 105
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 103
1 × 101
1 × 101
1 × 1021 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 101
1 × 103
1 × 103
1 × 1021 × 106
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 104
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106
1 × 105
1 × 106
1 × 106
1 × 105
1 × 105
1 × 106
1 × 105
1 × 106
1 × 106
1 × 106
1 × 106
1 × 104
1 × 104
1 × 104
1 × 106
1 × 107
1 × 105
1 × 106

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea
Rn-220b
Rn-222bRa-223bRa-224bRa-225
Ra-226b
Ra-227
Ra-228b
Ac-224
Ac-225b
Ac-226
Ac-227b
Ac-228
Th-226b
Th-227
Th-228b
Th-229b
Th-230Th-231
Th-232
Th-234bPa-227
Pa-228
Pa-230
Pa-231
Pa-232
Pa-233
Pa-234
U-230b
U-231
U-232b
U-233
U-234

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

1 × 104
1 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 101
1 × 1021 × 10–1
1 × 101
1 × 103
1 × 101
1 × 100
1 × 100
1 × 100
1 × 103
1 × 101
1 × 103
1 × 101
1 × 101
1 × 101
1 × 100
1 × 101
1 × 1021 × 101
1 × 101
1 × 1021 × 100
1 × 101
1 × 101

1 × 107
1 × 108
1 × 105
1 × 105
1 × 105
1 × 104
1 × 106
1 × 105
1 × 106
1 × 104
1 × 105
1 × 103
1 × 106
1 × 107
1 × 104
1 × 104
1 × 103
1 × 104
1 × 107
1 × 104
1 × 105
1 × 106
1 × 106
1 × 106
1 × 103
1 × 106
1 × 107
1 × 106
1 × 105
1 × 107
1 × 103
1 × 104
1 × 104

U-235b
U-236
U-237
U-238b
U-239
U-240
U-240b
Np-232
Np-233
Np-234
Np-235
Np-236
Np-236m
Np-237b
Np-238
Np-239
Np-240
Pu-234
Pu-235
Pu-236
Pu-237
Pu-238
Pu-239Pu-240Pu-241
Pu-242
Pu-243
Pu-244
Pu-245
Pu-246
Am-237
Am-238
Am-239Activity
concentration(Bq/g)

Activity(Bq)

1 × 101
1 × 101
1 × 1021 × 101
1 × 1021 × 103
1 × 101
1 × 101
1 × 1021 × 101
1 × 103
1 × 1021 × 103
1 × 100
1 × 1021 × 1021 × 101
1 × 1021 × 1021 × 101
1 × 103
1 × 100
1 × 100
1 × 100
1 × 1021 × 100
1 × 103
1 × 100
1 × 1021 × 1021 × 1021 × 101
1 × 1021 × 104
1 × 104
1 × 106
1 × 104
1 × 106
1 × 107
1 × 106
1 × 106
1 × 107
1 × 106
1 × 107
1 × 105
1 × 107
1 × 103
1 × 106
1 × 107
1 × 106
1 × 107
1 × 107
1 × 104
1 × 107
1 × 104
1 × 104
1 × 103
1 × 105
1 × 104
1 × 107
1 × 104
1 × 106
1 × 106
1 × 106
1 × 106
1 × 106

121

TABLE I.1. LEVELS FOR EXEMPTION OF MODERATE AMOUNTS OF
MATERIAL WITHOUT FURTHER CONSIDERATION: EXEMPT ACTIVITY
CONCENTRATIONS AND EXEMPT ACTIVITIES OF RADIONUCLIDES(cont.)
Radionuclidea

Activity
concentration(Bq/g)

Activity(Bq)

Radionuclidea

Am-240
Am-241
Am-242
Am-242mb
Am-243bAm-244Am-244m
Am-245
Am-246Am-246m
Cm-238
Cm-240Cm-241
Cm-242
Cm-243
Cm-244
Cm-245
Cm-246
Cm-247
Cm-248
Cm-249Cm-250
Bk-245
Bk-246

1 × 101
1 × 100
1 × 103
1 × 100
1 × 100
1 × 101
1 × 104
1 × 103
1 × 101
1 × 101
1 × 1021 × 1021 × 1021 × 1021 × 100
1 × 101
1 × 100
1 × 100
1 × 100
1 × 100
1 × 103
1 × 10–1
1 × 1021 × 101

1 × 106
1 × 104
1 × 106
1 × 104
1 × 103
1 × 106
1 × 107
1 × 106
1 × 105
1 × 106
1 × 107
1 × 105
1 × 106
1 × 105
1 × 104
1 × 104
1 × 103
1 × 103
1 × 104
1 × 103
1 × 106
1 × 103
1 × 106
1 × 106

Bk-247
Bk-249
Bk-250
Cf-244
Cf-246
Cf-248
Cf-249
Cf-250
Cf-251
Cf-252
Cf-253
Cf-254
Es-250Es-251
Es-253
Es-254
Es-254m
Fm-252
Fm-253
Fm-254
Fm-255
Fm-257
Md-257
Md-258ab

Activity
concentration(Bq/g)

Activity(Bq)

1 × 100
1 × 103
1 × 101
1 × 104
1 × 103
1 × 101
1 × 100
1 × 101
1 × 100
1 × 101
1 × 1021 × 100
1 × 1021 × 1021 × 1021 × 101
1 × 1021 × 103
1 × 1021 × 104
1 × 103
1 × 101
1 × 1021 × 1021 × 104
1 × 106
1 × 106
1 × 107
1 × 106
1 × 104
1 × 103
1 × 104
1 × 103
1 × 104
1 × 105
1 × 103
1 × 106
1 × 107
1 × 105
1 × 104
1 × 106
1 × 106
1 × 106
1 × 107
1 × 106
1 × 105
1 × 107
1 × 105m and mʹ denote metastable states of the radionuclide. The metastable state mʹ is of higher
energy than the metastable state m.
Parent radionuclides and their progeny whose dose contributions are taken into account in
the dose calculations (thus requiring only the exemption level of the parent radionuclide to
be considered) are listed here:

Ge-68
Rb-83
Sr-82
Sr-90

122

Ga-68
Kr-83m
Rb-82
Y-90

Y-87
Zr-93
Zr-97
Ru-106

Sr-87m
Nb-93m
Nb-97
Rh-106

Ag-108m
Sn-121m
Sn-126
Xe-122
Cs-137
Ba-140Ce-134Ce-144Gd-146
Hf-172
W-178
W-188
Re-189Ir-189Pt-188Hg-194Hg-195m
Pb-210
Pb-212
Bi-210m
Bi-212
Rn-220
Rn-222
Ra-223
Ra-224Ag-108Sn-121 (0.776)
Sb-126m
I-122
Ba-137m
La-140La-134Pr-144Eu-146
Lu-172
Ta-178
Re-188Os-189m (0.241)
Os-189m
Ir-188
Au-194Hg-195 (0.542)
Bi-210, Po-210
Bi-212, Tl-208 (0.36),
Po-212 (0.64)
Tl-206
Tl-208 (0.36), Po-212 (0.64)
Po-216
Po-218, Pb-214, Bi-214,
Po-214
Rn-219, Po-215, Pb-211,
Bi-211, Tl-207
Rn-220, Po-216, Pb-212,
Bi-212, Tl-208 (0.36),
Po-212 (0.64)

Ra-226
Ra-228
Ac-225

Ac-227
Th-226
Th-228
Th-229Th-234
U-230
U-232
U-235
U-238
U-240
Np-237
Am-242m
Am-243

Rn-222, Po-218, Pb-214,
Bi-214, Po-214, Pb-210,
Bi-210, Po-210
Ac-228
Fr-221, At-217, Bi-213,
Po-213 (0.978),Tl-209 (0.0216),
Pb-209 (0.978)Fr-223 (0.0138)
Ra-222, Rn-218, Po-214
Ra-224, Rn-220, Po-216,
Pb-212, Bi-212,Tl-208 (0.36),
Po-212 (0.64)
Ra-225, Ac-225, Fr-221,
At-217, Bi-213, Po-213,
Pb-209Pa-234m
Th-226, Ra-222, Rn-218,
Po-214
Th-228, Ra-224, Rn-220,
Po-216, Pb-212, Bi-212,
Tl-208 (0.36), Po-212 (0.64)
Th-231
Th-234, Pa-234m
Np-240m
Pa-233Am-242
Np-239Note: The exemption values (activity concentrations) presented in this table have been
calculated on the basis of scenarios involving a moderate amount of material: “Thecalculated values apply to practices involving small scale usage of activity where thequantities involved are at the most of the order of a tonne” (see Ref. [25]). The regulatory
body will need to establish the amounts for which the concentration values in this table
may be applied, bearing in mind that for many radionuclides, in particular those forwhich there is no corresponding value given in Table I.2, a restriction on the amountis not meaningful. The exemption levels set out in this table and the exemption andclearance levels set out in Table I.2 are subject to the following considerations: (a) they
were derived using a conservative model based on (i) the criteria of paras I.2 and I.11,
respectively, and (ii) a series of limiting (bounding) scenarios for use and disposal(see Refs [25, 26] in the case of this table and Ref. [27] in the case of Table I.2); (b) if there
is more than one radionuclide, the derived exemption level or derived clearance level forthe mixture is determined as specified in paras I.7 and I.14.

123

TABLE I.2. LEVELS FOR EXEMPTION OF BULK AMOUNTS OF
SOLID MATERIAL WITHOUT FURTHER CONSIDERATION AND
FOR CLEARANCE OF SOLID MATERIAL WITHOUT FURTHERCONSIDERATION: ACTIVITY CONCENTRATIONS OF RADIONUCLIDESOF ARTIFICIAL ORIGIN
Radionuclide
H-3
Be-7
C-14
F-18
Na-22
Na-24
Si-31
P-32
P-33
S-35
Cl-36
Cl-38
K-42
K-43
Ca-45
Ca-47
Sc-46
Sc-47
Sc-48
V-48
Cr-51
Mn-51
Mn-52
Mn-52m
Mn-53
Mn-54
Mn-56
Fe-52a
Fe-55
Fe-59
Co-55
Co-56
Co-57

124

Activity concentration(Bq/g)
100
10
1
10
0.1
1
1 000
1 000
1 000
100
1
10
100
10
100
10
0.1
100
1
1
100
10
1
10
100
0.1
10
10
1 000
1
10
0.1
1

Radionuclide

Activity concentration(Bq/g)

Co-58

1

Co-58m
Co-60
Co-60m
Co-61
Co-62m
Ni-59
Ni-63
Ni-65
Cu-64
Zn-65
Zn-69
Zn-69ma
Ga-72
Ge-71
As-73
As-74
As-76
As-77
Se-75
Br-82
Rb-86
Sr-85
Sr-85m
Sr-87m
Sr-89
Sr-90aSr-91a
Sr-92
Y-90
Y-91
Y-91m
Y-92

10 000
0.1
1 000
100
10
100
100
10
100
0.1
1 000
10
10
10 000
1 000
10
10
1 000
1
1
100
1
100
100
1 000
1
10
10
1 000
100
100
100

TABLE I.2. LEVELS FOR EXEMPTION OF BULK AMOUNTS OF
SOLID MATERIAL WITHOUT FURTHER CONSIDERATION AND
FOR CLEARANCE OF SOLID MATERIAL WITHOUT FURTHERCONSIDERATION: ACTIVITY CONCENTRATIONS OF RADIONUCLIDESOF ARTIFICIAL ORIGIN (cont.)
Radionuclide

Activity concentration(Bq/g)

Y-93
Zr-93
Zr-95a
Zr-97aNb-93m
Nb-94
Nb-95
Nb-97a
Nb-98
Mo-90
Mo-93
Mo-99aMo-101a
Tc-96
Tc-96m
Tc-97
Tc-97m
Tc-99
Tc-99m
Ru-97
Ru-103aRu-105aRu-106aRh-103m
Rh-105
Pd-103aPd-109aAg-105
Ag-110ma
Ag-111
Cd-109a
Cd-115aCd-115ma

100
10
1
10
10
0.1
1
10
10
10
10
10
10
1
1 000
10
100
1
100
10
1
10
0.1
10 000
100
1 000
100
1
0.1
100
1
10
100

Radionuclide
In-111
In-113m
In-114ma
In-115m
Sn-113aSn-125
Sb-122
Sb-124
Sb-125aTe-123m
Te-125m
Te-127
Te-127ma
Te-129Te-129ma
Te-131
Te-131ma
Te-132aTe-133Te-133m
Te-134
I-123
I-125
I-126
I-129
I-130
I-131
I-132
I-133
I-134
I-135
Cs-129
Cs-131

Activity concentration(Bq/g)
10
100
10
100
1
10
10
1
0.1
1
1 000
1 000
10
100
10
100
10
1
10
10
10
100
100
10
0.01
10
10
10
10
10
10
10
1 000

125

TABLE I.2. LEVELS FOR EXEMPTION OF BULK AMOUNTS OF
SOLID MATERIAL WITHOUT FURTHER CONSIDERATION AND
FOR CLEARANCE OF SOLID MATERIAL WITHOUT FURTHERCONSIDERATION: ACTIVITY CONCENTRATIONS OF RADIONUCLIDESOF ARTIFICIAL ORIGIN (cont.)
Radionuclide
Cs-132
Cs-134
Cs-134m
Cs-135
Cs-136
Cs-137aCs-138
Ba-131
Ba-140La-140Ce-139Ce-141
Ce-143Ce-144aPr-142Pr-143
Nd-147
Nd-149Pm-147
Pm-149Sm-151
Sm-153
Eu-152
Eu-152m
Eu-154Eu-155
Gd-153
Gd-159
Tb-160
Dy-165Dy-166
Ho-166
Er-169126

Activity concentration(Bq/g)
10
0.1
1 000
100
1
0.1
10
10
1
1
1
100
10
10
100
1 000
100
100
1 000
1 000
1 000
100
0.1
100
0.1
1
10
100
1
1 000
100
100
1 000

Radionuclide
Er-171
Tm-170
Tm-171
Yb-175
Lu-177
Hf-181
Ta-182
W-181
W-185
W-187
Re-186
Re-188Os-185
Os-191
Os-191m
Os-193
Ir-190Ir-192
Ir-194
Pt-191
Pt-193m
Pt-197
Pt-197m
Au-198
Au-199Hg-197
Hg-197m
Hg-203
Tl-200Tl-201
Tl-202
Tl-204
Pb-203

Activity concentration(Bq/g)
100
100
1 000
100
100
1
0.1
10
1 000
10
1 000
100
1
100
1 000
100
1
1
100
10
1 000
1 000
100
10
100
100
100
10
10
100
10
1
10

TABLE I.2. LEVELS FOR EXEMPTION OF BULK AMOUNTS OF
SOLID MATERIAL WITHOUT FURTHER CONSIDERATION AND
FOR CLEARANCE OF SOLID MATERIAL WITHOUT FURTHERCONSIDERATION: ACTIVITY CONCENTRATIONS OF RADIONUCLIDESOF ARTIFICIAL ORIGIN (cont.)
Radionuclide
Bi-206
Bi-207
Po-203
Po-205
Po-207
At-211
Ra-225
Ra-227
Th-226
Th-229Pa-230
Pa-233
U-230
U-231
U-232a
U-233
U-236
U-237
U-239
U-240a
Np-237aNp-239
Np-240
Pu-234
Pu-235
Pu-236
Pu-237
Pu-238
Pu-239Pu-240a

Activity concentration(Bq/g)
1
0.1
10
10
10
1 000
10
100
1 000
0.1
10
10
10
100
0.1
1
10
100
100
100
1
100
10
100
100
1
100
0.1
0.1
0.1

Radionuclide

Activity concentration(Bq/g)

Pu-241
Pu-242
Pu-243
Pu-244aAm-241
Am-242
Am-242ma
Am-243aCm-242
Cm-243
Cm-244
Cm-245
Cm-246
Cm-247aCm-248
Bk-249
Cf-246
Cf-248
Cf-249
Cf-250
Cf-251
Cf-252
Cf-253
Cf-254
Es-253
Es-254aEs-254ma
Fm-254
Fm-255

10
0.1
1 000
0.1
0.1
1 000
0.1
0.1
10
1
1
0.1
0.1
0.1
0.1
100
1 000
1
0.1
1
0.1
1
100
1
100
0.1
10
10 000100

Parent radionuclides, and their progeny whose dose contributions are taken into account in
the dose calculations (thus requiring only the exemption level of the parent radionuclide to
be considered), are listed here:127

Fe-52
Zn-69m
Sr-90
Sr-91
Zr-95
Zr-97
Nb-97
Mo-99
Mo-101
Ru-103
Ru-105
Ru-106
Pd-103
Pd-109Ag-110m
Cd-109
Cd-115
Cd-115m
In-114m

Mn-52m
Zn-69
Y-90
Y-91m
Nb-95
Nb-97m, Nb-97
Nb-97m
Tc-99m
Tc-101
Rh-103m
Rh-105m
Rh-106
Rh-103m
Ag-109m
Ag-110Ag-109m
In-115m
In-115m
In-114

Sn-113
Sb-125
Te-127m
Te-129m
Te-131m
Te-132
Cs-137Ce-144
U-232
U-240
Np-237
Pu-244Am-242m
Am-243
Cm-247
Es-254
Es-254m

In-113m
Te-125m
Te-127
Te-129Te-131
I-132
Ba-137m
Pr-144, Pr-144m
Th-228, Ra-224, Rn-220,
Po-216, Pb-212, Bi-212,
Tl-208Np-240m, Np-240
Pa-233U-240, Np-240m, Np-240
Np-238
Np-239Pu-243
Bk-250Fm-254

Note: The exemption levels set out in Table I.1 (p. 111) and the exemption and clearance levels
set out in this table are subject to the following considerations: (a) they were derived
using a conservative model based on (i) the criteria of paras I.2 and I.11, respectively,and (ii) a series of limiting (bounding) scenarios for use and disposal (see Refs [25, 26]
in the case of Table I.1 and Ref. [27] in the case of this table); (b) if there is more than
one radionuclide, the derived exemption level or derived clearance level for the mixture
is determined as specified in paras I.7 and I.14.

TABLE I.3. LEVELS FOR CLEARANCE OF MATERIAL: ACTIVITY
CONCENTRATIONS OF RADIONUCLIDES OF NATURAL ORIGIN
Radionuclide

Activity concentration (Bq/g)

K-40

10

Each radionuclide in the uranium decay chain or
the thorium decay chain

1

128Schedule II
CATEGORIES FOR SEALED SOURCES
USED IN COMMON PRACTICES
II.1. Table II.1 shows categories for sealed sources used in common practices,
and Table II.2 shows the activity corresponding to a dangerous source (D value)
for selected radionuclides.

TABLE II.1. CATEGORIES FOR SEALED SOURCES USED IN COMMON
PRACTICES (cont.)
Category

Ratio of activity
in the source to activity
that is considered dangerousa(A/D)

Example of sourcesb and practices
Radioisotope thermoelectric generators;
Irradiators;

1

A/D ≥ 1000

Teletherapy sources;
Fixed, multibeam teletherapy(‘gamma knife’) sources

21000 > A/D ≥ 10

310 > A/D ≥ 1

Industrial gamma radiography sources;
High/medium dose rate brachytherapy sources
Fixed industrial gauges incorporatinghigh activity sources;
Well logging gauges
Low dose rate brachytherapy sources(except eye plaques and permanent implants);

4

1 > A/D ≥ 0.01

Industrial gauges not incorporating highactivity sources;
Bone densitometers;
Static eliminators

129

TABLE II.1. CATEGORIES FOR SEALED SOURCES USED IN COMMON
PRACTICES (cont.)
Category

Ratio of activity
in the source to activity
that is considered dangerousa(A/D)

0.01 > A/D
and
A > level for exemptionc

5

Example of sourcesb and practices
Low dose rate brachytherapy eye plaques andpermanent implant sources;
X ray fluorescence devices;Electron capture devices;
Mossbauer spectrometry sources;
Positron emission tomography check sources

a

b

c

A is the activity of the radionuclide in a source and D is the activity of that radionuclide
that is regarded as dangerous. A dangerous source is defined as one that could, if not undercontrol, give rise to exposure sufficient to cause severe deterministic effects. Values of D
for selected radionuclides are given in Table II.2 on the basis of the quantity of radioactive
material that could give rise to severe deterministic effects for given exposure scenarios andfor given dose criteria. This column of the table can, thus, be used to determine the categoryof a source, purely on the basis of the value of A/D. This may be appropriate if, for example:
the practice is not known or is not listed; if sources have a short half-life and/or are unsealed;or if sources are aggregated.
Factors other than A/D have been taken into consideration in assigning these sources to aparticular category [28].
Levels for exemption are given in Schedule I.

130

TABLE II.2. ACTIVITYa CORRESPONDING TO A DANGEROUS SOURCE(D VALUEb) FOR SELECTED RADIONUCLIDESRadionuclide

D value(TBq)

Am-241
Am-241/Be
Au-198
Cd-109
Cf-252
Cm-244
Co-57
Co-60
Cs-137
Fe-55
Gd-153
Ge-68
H-3
I-125
I-131
Ir-192
Kr-85

6 × 10–2
6 × 10–2
2 × 10–1
2 × 101
2 × 10–2
5 × 10–2
7 × 10–1
3 × 10–2
1 × 10–1
8 × 1021 × 100
7 × 10–2
2 × 103
2 × 10–1
2 × 10–1
8 × 10–2
3 × 101ab

Radionuclide

D value
(TBq)

Mo-99
Ni-63
P-32
Pd-103
Pm-147
Po-210
Pu-238
Pu-239/Be
Ra-226
Ru-106 (Rh-106)
Se-75
Sr-90 (Y-90)
Tc-99m
Tl-204
Tm-170
Yb-1693 × 10–1
6 × 101
1 × 101
9 × 101
4 × 101
6 × 10–2
6 × 10–2
6 × 10–2
4 × 10–2
3 × 10–1
2 × 10–1
1 × 100
7 × 10–1
2 × 101
2 × 101
3 × 10–1

Since this table does not state which dose criteria were used, these D values cannot be used
‘in reverse’ to derive possible doses from exposure due to sources of known activity.
Full details of the derivation of the D values and D values for additional radionuclides areprovided in Ref. [29].

131Schedule III
DOSE LIMITS FOR PLANNED EXPOSURE SITUATIONSOCCUPATIONAL EXPOSURE
III.1. For occupational exposure of workers over the age of 18 years, the dose
limits are:
(a)
(b)
(c)

An effective dose of 20 mSv per year averaged over five consecutive
years66 (100 mSv in 5 years) and of 50 mSv in any single year;
An equivalent dose to the lens of the eye of 20 mSv per year averaged over
five consecutive years (100 mSv in 5 years) and of 50 mSv in any single
year;
An equivalent dose to the extremities (hands and feet) or to the skin67 of
500 mSv in a year.

Additional restrictions apply to occupational exposure for a female worker who
has notified pregnancy or is breast-feeding (para. 3.114).
III.2. For occupational exposure of apprentices of 16 to 18 years of age who arebeing trained for employment involving radiation and for exposure of students ofage 16 to 18 who use sources in the course of their studies, the dose limits are:
(a)
(b)
(c)

An effective dose of 6 mSv in a year;
An equivalent dose to the lens of the eye of 20 mSv in a year;
An equivalent dose to the extremities (hands and feet) or to the skin67 of
150 mSv in a year.

66

The start of the averaging period shall be coincident with the first day of the relevant
annual period after the date of entry into force of these Standards, with no retrospective
averaging.
67
The equivalent dose limits for the skin apply to the average dose over 1 cm2 of the mosthighly irradiated area of the skin. The dose to the skin also contributes to the effective dose, thiscontribution being the average dose to the entire skin multiplied by the tissue weighting factor
for the skin.

132

PUBLIC EXPOSURE
III.3. For public exposure, the dose limits are:
(a)
(b)
(c)
(d)

An effective dose of 1 mSv in a year;
In special circumstances68, a higher value of effective dose in a single year
could apply, provided that the average effective dose over five consecutive
years does not exceed 1 mSv per year;
An equivalent dose to the lens of the eye of 15 mSv in a year;
An equivalent dose to the skin of 50 mSv in a year.

VERIFICATION OF COMPLIANCE WITH DOSE LIMITS
III.4. The effective dose limits specified in this schedule apply to the sum of therelevant doses from external exposure in the specified period and the relevant
committed doses from intakes in the same period; the period for calculating thecommitted dose shall normally be 50 years for intakes by adults and shall be up
to age 70 years for intakes by children.
III.5. For occupational exposure, the personal dose equivalent Hp(10)69 may
be used as an approximation of the effective dose from external exposure topenetrating radiation.
III.6. Values of the effective dose per unit air kerma free-in-air and per unit
particle fluence are given in Tables III.1A–III.1D [30].
III.7. Doses per unit intake (dose coefficients) for the estimation of thecommitted effective dose for ingestion and inhalation of radionuclides are given
in Tables III.2A–III.2H (p. 137) [37, 38].

68

For example, in authorized, justified and planned operational conditions that lead totransitory increases in exposures.
69
Hp(10) is the personal dose equivalent Hp(d) where d = 10 mm.

133TABLE III.1A. CONVERSION COEFFICIENTS FROM AIR KERMA
FREE-IN-AIR TO Hp(10,0°) IN AN INTERNATIONAL COMMISSION ON
RADIATION UNITS AND MEASUREMENTS ICRU SLAB (PHOTONS) [30]
Photon energy(MeV)

Hp(10,0o)/K(Sv/Gy)Photon energy(MeV)

Hp(10,0o)/K(Sv/Gy)

0.010

0.009

0.150

1.607

0.0125

0.098

0.200

1.492

0.015

0.264

0.300

1.369

0.0175

0.445

0.400

1.300

0.020

0.611

0.500

1.256

0.025

0.883

0.600

1.226

0.030

1.112

0.800

1.190

0.040

1.490

1.0

1.167

0.050

1.766

1.5

1.139

0.060

1.892

3.0

1.117

0.080

1.903

6.0

1.109

0.100

1.811

10.0

1.111

0.125

1.696

TABLE III.1B. CONVERSION COEFFICIENTS FROM AIR KERMA
FREE-IN-AIR TO Hp(0.07,0°) IN AN INTERNATIONAL COMMISSION ON
RADIATION UNITS AND MEASUREMENTS ICRU SLAB (PHOTONS) [30]
Photon energy(MeV)

Hp(10,0o)/K(Sv/Gy)Photon energy(MeV)

Hp(10,0o)/K(Sv/Gy)

0.005

0.750

0.100

1.669

0.010

0.947

0.150

1.518

0.015

0.981

0.200

1.432

0.020

1.045

0.300

1.336

0.030

1.230

0.400

1.280

0.040

1.444

0.500

1.244

0.050

1.632

0.600

1.220

0.060

1.716

0.800

1.189

1.732

1.000

1.173

0.080

134

TABLE III.1C. EFFECTIVE DOSE PER UNIT NEUTRON FLUENCE E/Φ
FOR MONOENERGETIC NEUTRONS INCIDENT IN INTERNATIONALORGANIZATION FOR STANDARDIZATION GEOMETRY ON AN ADULTANTHROPOMORPHIC COMPUTATIONAL PHANTOM [30]
Neutron energy(MeV)
1.00 × 10–9–8

1.00 × 10–8

2.53 × 10–71.00 × 10–72.00 × 10–7

E/Φ
(pSv·cm2)

Neutron energy
(MeV)

E/Φ
(pSv·cm2)2.40

1.50 × 10–1

35.2

2.89

–1

42.4

3.30

–1

3.00 × 10

54.7

4.13

5.00 × 10–1

75.0

4.59

–1

92.8

–1

108

2.00 × 10

7.00 × 10

5.20

9.00 × 10–61.00 × 10

5.63

01.00 × 10

116

2.00 × 10–6

5.96

1.20 × 100

130

5.00 × 10–6

6.28

2.00 × 100

178

–5

1.00 × 10

6.44

03.00 × 10

220

2.00 × 10–5

6.51

4.00 × 100

250

05.00 × 10

–5

6.51

5.00 × 10272–41.00 × 10

6.45

06.00 × 10282

2.00 × 10–4

6.32

7.00 × 100

290

05.00 × 10

–4

6.14

8.00 × 10297–31.00 × 10

6.04

09.00 × 10

303

2.00 × 10–3

6.05

1.00 × 101

309

6.52

1

1.20 × 10

322

7.70

1

1.40 × 10

333

10.2

1.50 × 101

338

12.7

1

1.60 × 10342

15.00 × 10–35.00 × 10–21.00 × 10–22.00 × 10–23.00 × 10

–2

17.3

1.80 × 10345–27.00 × 10

21.5

1

343

1.00 × 10–1

25.2

5.00 × 10

2.00 × 10

135

TABLE III.1D. REFERENCE CONVERSION COEFFICIENTS FROMFLUENCE TO DIRECTIONAL DOSE EQUIVALENT FOR MONOENERGETICELECTRONS AND NORMAL INCIDENCE [30]Electron energy(MeV)

H΄(0.07,0°)/Φ
(nSv·cm2)H΄(3,0°)/Φ
(nSv·cm2)H΄(10,0°)/Φ
(nSv·cm2)

0.07

0.221

0.08

1.056

0.09

1.527

0.10

1.661

0.1125

1.627

0.125

1.513

0.15

1.229

0.20

0.834

0.30

0.542

0.40

0.455

0.50

0.403

0.60

0.366

0.70

0.344

0.000

0.80

0.329

0.045

1.00

0.312

0.301

1.25

0.296

0.486

1.50

0.287

0.524

1.75

0.282

0.512

0.000

2.00

0.279

0.481

0.005

2.50

0.278

0.417

0.156

3.00

0.276

0.373

0.336

3.50

0.274

0.351

0.421

4.00

0.272

0.334

0.447

5.00

0.271

0.317

0.430

6.00

0.271

0.309

0.389

7.00

0.271

0.306

0.360

8.00

0.271

0.305

0.341

10.00

0.275

0.303

0.330

136

137

1.60 × 106 a

Be-10

F-18

Fluorine

C-11
C-14

1.83 h0.340 h5.73 × 103 a

53.3 dCarbon

4.3 × 10–11
4.6 × 10–11
6.7 × 10–9
1.9 × 10–8

e(g)5 μm

f1

F
M
S

1.000
1.000
1.000

3.0 × 10–11
5.7 × 10–11
6.0 × 10–11

5.4 × 10–11
8.9 × 10–11
9.3 × 10–11

1.000

1.000
1.000

0.005

0.005

1.000

4.8 × 10–11
5.2 × 10–11
9.1 × 10–9
3.2 × 10–8e(g)1 μm

12.3 a

0.005
0.005
0.005
0.005

f1
1.000

M
S
M
S

Type

Inhalation

12.3 aPhysicalhalf-life

Be-7

Beryllium

Tritiatedwater
Organicallybound tritium

HydrogenRadionuclideae(g)4.9 × 10–11

2.4 × 10–11
5.8 × 10–10

1.1 × 10–9

2.8 × 10–11

4.2 × 10–11

1.8 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

138

2.62 h

4.50 × 102 a

Si‑32

7.16 × 105 a

20.9 h

2.60 a15.0 hPhysicalhalf-life

Si‑31

Silicon

Al‑26

Aluminium

Mg-28

Magnesium

Na-22
Na-24

SodiumRadionuclidea

F
M
S
F
M
S

F
M

F
M

F
F

Type

0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010

0.500
0.500

1.000
1.000

f1

2.9 × 10–11
7.5 × 10–11
8.0 × 10–11
3.2 × 10–9
1.5 × 10–8
1.1 × 10–7

1.1 × 10–8
1.8 × 10–8

6.4 × 10–10
1.2 × 10–9

1.3 × 10–9
2.9 × 10–10e(g)1 μm

Inhalation

5.1 × 10–11
1.1 × 10–10
1.1 × 10–10
3.7 × 10–9
9.6 × 10–9
5.5 × 10–8

1.4 × 10–8
1.2 × 10–8

1.1 × 10–9
1.7 × 10–9

2.0 × 10–9
5.3 × 10–10

e(g)5 μm

0.010

0.010

0.010

0.500

1.000
1.000

f1

e(g)

5.6 × 10–10

1.6 × 10–10

3.5 × 10–9

2.2 × 10–9

3.2 × 10–9
4.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

139

F
F

0.620 h0.927 h1.28 × 109 a
12.4 h

Cl‑38

Cl‑39

K‑40
K‑42

Potassium

F
M
F
M
F
M

3.01 × 105 a87.4 d

F
M

F
M
F
M

Type

Cl‑36

Chlorine

S‑35(inorganic)
S‑35(organic)

87.4 d25.4 dP‑33

Sulphur

14.3 dPhysicalhalf-life

P‑32

Phosphorus

Radionuclidea

1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000

0.800
0.800

0.800
0.800
0.800
0.800

f1

2.1 × 10–9
1.3 × 10–10

3.4 × 10–10
6.9 × 10–9
2.7 × 10–11
4.7 × 10–11
2.7 × 10–11
4.8 × 10–11

5.3 × 10–11
1.3 × 10–9

8.0 × 10–10
3.2 × 10–9
9.6 × 10–11
1.4 × 10–9e(g)1 μm

Inhalation

3.0 × 10–9
2.0 × 10–10

4.9 × 10–10
5.1 × 10–9
4.6 × 10–11
7.3 × 10–11
4.8 × 10–11
7.6 × 10–11

8.0 × 10–11
1.1 × 10–9

1.1 × 10–9
2.9 × 10–9
1.4 × 10–10
1.3 × 10–9e(g)5 μm

1.000
1.000

1.000

1.000

1.000

0.800
0.100
1.000

0.800

0.800

f1

e(g)

6.2 × 10–9
4.3 × 10–10

8.5 × 10–11

1.2 × 10–10

9.3 × 10–10

1.4 × 10–10
1.9 × 10–10
7.7 × 10–10

2.4 × 10–10

2.4 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

140

Ti‑44

Titanium

Sc‑43
Sc‑44
Sc‑44m
Sc‑46
Sc‑47
Sc‑48
Sc‑49

Scandium

Ca‑41
Ca‑45
Ca‑47

Calcium

K‑43
K‑44
K‑45

Radionuclidea

47.3 a3.89 h
3.93 h
2.44 d83.8 d3.35 d1.82 d
0.956 h1.40 × 105 a
163 d4.53 d

22.6 h
0.369 h0.333 hPhysicalhalf-life

F
M
S

S
S
S
S
S
S
S

M
M
M

F
F
F

Type

0.010
0.010
0.010

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.300
0.300

1.000
1.000
1.000

f1

6.1 × 10–8
4.0 × 10–8
1.2 × 10–7

1.2 × 10–10
1.9 × 10–10
1.5 × 10–9
6.4 × 10–9
7.0 × 10–10
1.1 × 10–9
4.1 × 10–11

1.7 × 10–10
2.7 × 10–9
1.8 × 10–9

1.5 × 10
2.1 × 10–11
1.6 × 10–11–10e(g)1 μm

Inhalation

7.2 × 10–8
2.7 × 10–8
6.2 × 10–8

1.8 × 10–10
3.0 × 10–10
2.0 × 10–9
4.8 × 10–9
7.3 × 10–10
1.6 × 10–9
6.1 × 10–11

1.9 × 10–10
2.3 × 10–9
2.1 × 10–9

2.6 × 10
3.7 × 10–11
2.8 × 10–11–10e(g)5 μm0.010

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.300
0.300

1.000
1.000
1.000

f1

e(g)

5.8 × 10–9

1.9 × 10–10
3.5 × 10–10
2.4 × 10–9
1.5 × 10–9
5.4 × 10–10
1.7 × 10–9
8.2 × 10–11

2.9 × 10–10
7.6 × 10–10
1.6 × 10–9

2.5 × 10–10
8.4 × 10–11
5.4 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

141

16.2 d

330 d

V‑48

V‑49

23.0 h

0.702 h27.7 d

Cr‑48

Cr‑49

Cr‑51

Chromium

0.543 h3.08 hPhysicalhalf-life

V‑47

Vanadium

Ti‑45

Radionuclidea

F
M
S
F
M
S
F
M
S

F
M
F
M
F
M

F
M
S

Type

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010

f1

1.0 × 10–10
2.0 × 10–10
2.2 × 10–10
2.0 × 10–11
3.5 × 10–11
3.7 × 10–11
2.1 × 10–11
3.1 × 10–11
3.6 × 10–11

1.9 × 10–11
3.1 × 10–11
1.1 × 10–9
2.3 × 10–9
2.1 × 10–11
3.2 × 10–11

4.6 × 10
9.1 × 10–11
9.6 × 10–11–11e(g)1 μm

Inhalation

1.7 × 10–10
2.3 × 10–10
2.5 × 10–10
3.5 × 10–11
5.6 × 10–11
5.9 × 10–11
3.0 × 10–11
3.4 × 10–11
3.6 × 10–11

3.2 × 10–11
5.0 × 10–11
1.7 × 10–9
2.7 × 10–9
2.6 × 10–11
2.3 × 10–11

8.3 × 10
1.4 × 10–10
1.5 × 10–10–11e(g)5 μm

0.100
0.010

0.100
0.010

0.100
0.010

0.010

0.010

0.010

0.010

f1

e(g)

3.8 × 10–11
3.7 × 10–11

6.1 × 10–11
6.1 × 10–11

2.0 × 10–10
2.0 × 10–10

1.8 × 10–11

2.0 × 10–9

6.3 × 10–11

1.5 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

142

5.59 d

0.352 h3.70 × 106 a

312 d2.58 hMn‑52

Mn‑52m

Mn‑53

Mn‑54

Mn‑56

8.28 h2.70 a44.5 d

Fe‑52

Fe‑55

Fe‑59

Iron

0.770 hPhysicalhalf-life

Mn‑51

ManganeseRadionuclidea

F
M
F
M
F
M

F
M
F
M
F
M
F
M
F
M
F
M

Type

0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

4.1 × 10–10
6.3 × 10–10
7.7 × 10–10
3.7 × 10–10
2.2 × 10–9
3.5 × 10–9

2.4 × 10–11
4.3 × 10–11
9.9 × 10–10
1.4 × 10–9
2.0 × 10–11
3.0 × 10–11
2.9 × 10–11
5.2 × 10–11
8.7 × 10–10
1.5 × 10–9
6.9 × 10–11
1.3 × 10–10e(g)1 μm

Inhalation

6.9 × 10–10
9.5 × 10–10
9.2 × 10–10
3.3 × 10–10
3.0 × 10–9
3.2 × 10–9

4.2 × 10–11
6.8 × 10–11
1.6 × 10–9
1.8 × 10–9
3.5 × 10–11
5.0 × 10–11
3.6 × 10–11
3.6 × 10–11
1.1 × 10–9
1.2 × 10–9
1.2 × 10–10
2.0 × 10–10

e(g)5 μm

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

f1

e(g)

1.8 × 10–9

3.3 × 10–10

1.4 × 10–9

2.5 × 10–10

7.1 × 10–10

3.0 × 10–11

6.9 × 10–11

1.8 × 10–9

9.3 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)143

17.5 h78.7 d271 d70.8 d

9.15 h5.27 a0.174 h1.65 h

0.232 h

Co‑56

Co‑57

Co‑58

Co‑58m

Co‑60

Co‑60mCo‑61

Co‑62m1.00 × 10 a5

Physicalhalf-life

Co‑55

CobaltFe‑60

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M

Type

0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050

0.100
0.100

f1

5.1 × 10–10
5.5 × 10–10
4.6 × 10–9
6.3 × 10–9
5.2 × 10–10
9.4 × 10–10
1.5 × 10–9
2.0 × 10–9
1.3 × 10–11
1.6 × 10–11
9.6 × 10–9
2.9 × 10–8
1.1 × 10–12
1.3 × 10–12
4.8 × 10–11
5.1 × 10–11
2.1 × 10–11
2.2 × 10–11

2.8 × 10
1.3 × 10–7–7e(g)1 μm

Inhalation

7.8 × 10–10
8.3 × 10–10
4.0 × 10–9
4.9 × 10–9
3.9 × 10–10
6.0 × 10–10
1.4 × 10–9
1.7 × 10–9
1.5 × 10–11
1.7 × 10–11
7.1 × 10–9
1.7 × 10–8
1.2 × 10–12
1.2 × 10–12
7.1 × 10–11
7.5 × 10–11
3.6 × 10–11
3.7 × 10–11

3.3 × 10
1.2 × 10–7

–7

e(g)5 μm

0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050
0.100
0.050

0.100

f1

e(g)

1.0 × 10–9
1.1 × 10–9
2.5 × 10–9
2.3 × 10–9
2.1 × 10–10
1.9 × 10–10
7.4 × 10–10
7.0 × 10–10
2.4 × 10–11
2.4 × 10–11
3.4 × 10–9
2.5 × 10–9
1.7 × 10–12
1.7 × 10–12
7.4 × 10–11
7.4 × 10–11
4.7 × 10–11
4.7 × 10–11

1.1 × 10–7

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

144

1.50 d7.50 × 104 a

96.0 a2.52 h2.27 d

Ni‑57

Ni‑59

Ni‑63

Ni‑65

Ni‑66

0.387 h3.41 h

Cu‑60

Cu‑61

Copper6.10 dPhysicalhalf-life

Ni‑56

NickelRadionuclidea

F
M
S
F
M
S

F
M
F
M
F
M
F
M
F
M
F
M

Type

0.500
0.500
0.500
0.500
0.500
0.500

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1

2.4 × 10–11
3.5 × 10–11
3.6 × 10–11
4.0 × 10–11
7.6 × 10–11
8.0 × 10–11

5.1 × 10–10
8.6 × 10–10
2.8 × 10–10
5.1 × 10–10
1.8 × 10–10
1.3 × 10–10
4.4 × 10–10
4.4 × 10–10
4.4 × 10–11
8.7 × 10–11
4.5 × 10–10
1.6 × 10–9e(g)1 μm

Inhalation

4.4 × 10–11
6.0 × 10–11
6.2 × 10–11
7.3 × 10–11
1.2 × 10–10
1.2 × 10–10

7.9 × 10–10
9.6 × 10–10
5.0 × 10–10
7.6 × 10–10
2.2 × 10–10
9.4 × 10–11
5.2 × 10–10
3.1 × 10–10
7.5 × 10–11
1.3 × 10–10
7.6 × 10–10
1.9 × 10–9e(g)5 μm

0.500

0.500

0.050

0.050

0.050

0.050

0.050

0.050

f1

e(g)

1.2 × 10–10

7.0 × 10–11

3.0 × 10–9

1.8 × 10–10

1.5 × 10–10

6.3 × 10–11

8.7 × 10–10

8.6 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

145

0.253 h9.40 h3.26 d

Ga‑65

Ga‑66

Ga‑67

Gallium

Zn‑62
Zn‑63
Zn‑65
Zn‑69
Zn‑69mZn‑71mZn‑72

9.26 h
0.635 h244 d0.950 h13.8 h3.92 h
1.94 d

2.58 d

Cu‑67

Zinc

12.7 hPhysicalhalf-life

Cu‑64

Radionuclidea

F
M
F
M
F
M

S
S
S
S
S
S
S

F
M
S
F
M
S

Type

0.001
0.001
0.001
0.001
0.001
0.001

0.500
0.500
0.500
0.500
0.500
0.500
0.500

0.500
0.500
0.500
0.500
0.500
0.500

f1

1.2 × 10–11
1.8 × 10–11
2.7 × 10–10
4.6 × 10–10
6.8 × 10–11
2.3 × 10–10

4.7 × 10–10
3.8 × 10–11
2.9 × 10–9
2.8 × 10–11
2.6 × 10–10
1.6 × 10–10
1.2 × 10–9

3.8 × 10
1.1 × 10–10
1.2 × 10–10
1.1 × 10–10
5.2 × 10–10
5.8 × 10–10–11e(g)1 μm

Inhalation

2.0 × 10–11
2.9 × 10–11
4.7 × 10–10
7.1 × 10–10
1.1 × 10–10
2.8 × 10–10

6.6 × 10–10
6.1 × 10–11
2.8 × 10–9
4.3 × 10–11
3.3 × 10–10
2.4 × 10–10
1.5 × 10–9

6.8 × 10
1.5 × 10–10
1.5 × 10–10
1.8 × 10–10
5.3 × 10–10
5.8 × 10–10–11e(g)5 μm

0.001

0.001

0.001

0.500
0.500
0.500
0.500
0.500
0.500
0.500

0.500

0.500

f1

e(g)

1.9 × 10–10

1.2 × 10–9

3.7 × 10–11

9.4 × 10–10
7.9 × 10–11
3.9 × 10–9
3.1 × 10–11
3.3 × 10–10
2.4 × 10–10
1.4 × 10–9

3.4 × 10–10

1.2 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

146

0.353 h14.1 h

4.91 h

Ga‑70

Ga‑72

Ga‑73

2.27 h0.312 h288 d1.63 d11.8 d1.38 h

Ge‑66

Ge‑67

Ge‑68

Ge‑69

Ge‑71

Ge‑75

Germanium

1.13 hPhysicalhalf-life

Ga‑68

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M

F
M
F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

f1

5.7 × 10–11
9.2 × 10–11
1.6 × 10–11
2.6 × 10–11
5.4 × 10–10
1.3 × 10–8
1.4 × 10–10
2.9 × 10–10
5.0 × 10–12
1.0 × 10–11
1.6 × 10–11
3.7 × 10–11

2.8 × 10
5.1 × 10–11
9.3 × 10–12
1.6 × 10–11
3.1 × 10–10
5.5 × 10–10
5.8 × 10–11
1.5 × 10–10–11e(g)1 μm

Inhalation

9.9 × 10–11
1.3 × 10–10
2.8 × 10–11
4.2 × 10–11
8.3 × 10–10
7.9 × 10–9
2.5 × 10–10
3.7 × 10–10
7.8 × 10–12
1.1 × 10–11
2.7 × 10–11
5.4 × 10–11

4.9 × 10
8.1 × 10–11
1.6 × 10–11
2.6 × 10–11
5.6 × 10–10
8.4 × 10–10
1.0 × 10–10
2.0 × 10–10–11e(g)5 μm

1.000

1.000

1.000

1.000

1.000

1.000

0.001

0.001

0.001

0.001

f1

e(g)

4.6 × 10–11

1.2 × 10–11

2.4 × 10–10

1.3 × 10–9

6.5 × 10–11

1.0 × 10–10

2.6 × 10–10

1.1 × 10–9

3.1 × 10–11

1.0 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

147

0.683 h7.15 h

0.650 h

Se‑70

Se‑73

Se‑73mSelenium

As‑69
As‑70
As‑71
As‑72
As‑73
As‑74
As‑76
As‑77
As‑78

0.253 h0.876 h2.70 d1.08 d80.3 d17.8 d
1.10 d
1.62 d1.51 h1.45 h

Ge‑78

Arsenic

11.3 hPhysicalhalf-life

Ge‑77

Radionuclidea

F
M
F
M
F
M

M
M
M
M
M
M
M
M
M

F
M
F
M

Type

0.800
0.800
0.800
0.800
0.800
0.800

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

1.000
1.000
1.000
1.000

f1

4.5 × 10–11
7.3 × 10–11
8.6 × 10–11
1.6 × 10–10
9.9 × 10–12
1.8 × 10–11

2.2 × 10–11
7.2 × 10–11
4.0 × 10–10
9.2 × 10–10
9.3 × 10–10
2.1 × 10–9
7.4 × 10–10
3.8 × 10–10
9.2 × 10–11

1.5 × 10
3.6 × 10–10
4.8 × 10–11
9.7 × 10–11–10e(g)1 μm

Inhalation

8.2 × 10–11
1.2 × 10–10
1.5 × 10–10
2.4 × 10–10
1.7 × 10–11
2.7 × 10–11

3.5 × 10–11
1.2 × 10–10
5.0 × 10–10
1.3 × 10–9
6.5 × 10–10
1.8 × 10–9
9.2 × 10–10
4.2 × 10–10
1.4 × 10–10

2.5 × 10
4.5 × 10–10
8.1 × 10–11
1.4 × 10–10–10e(g)5 μm

0.800
0.050
0.800
0.050
0.800
0.050

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

1.000

1.000

f1

e(g)

1.2 × 10–10
1.4 × 10–10
2.1 × 10–10
3.9 × 10–10
2.8 × 10–11
4.1 × 10–11

5.7 × 10–11
1.3 × 10–10
4.6 × 10–10
1.8 × 10–9
2.6 × 10–10
1.3 × 10–9
1.6 × 10–9
4.0 × 10–10
2.1 × 10–10

1.2 × 10–10

3.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

148

6.50 × 104 a

0.308 h0.954 h0.375 h

Se‑79

Se‑81

Se‑81mSe‑83

0.422 h0.691 h1.63 h

16.2 h2.33 d

Br‑74

Br‑74m

Br‑75

Br‑76

Br‑77

Bromine120 d

Physicalhalf-life

Se‑75

Radionuclidea

F
M
F
M
F
M
F
M
F
M

F
M
F
M
F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

f1

2.8 × 10–11
4.1 × 10–11
4.2 × 10–11
6.5 × 10–11
3.1 × 10–11
5.5 × 10–11
2.6 × 10–10
4.2 × 10–10
6.7 × 10–11
8.7 × 10–11

5.0 × 10–11
6.8 × 10–11
7.5 × 10–11
1.1 × 10–10
5.6 × 10–11
8.5 × 10–11
4.5 × 10–10
5.8 × 10–10
1.2 × 10–10
1.3 × 10–10

1.4 × 10
1.7 × 10–9
1.6 × 10–9
3.1 × 10–9
1.4 × 10–11
2.4 × 10–11
3.0 × 10–11
6.8 × 10–11
3.4 × 10–11
5.3 × 10–11–9–9

1.0 × 10
1.4 × 10–9
1.2 × 10–9
2.9 × 10–9
8.6 × 10–12
1.5 × 10–11
1.7 × 10–11
4.7 × 10–11
1.9 × 10–11
3.3 × 10–11

e(g)5 μme(g)1 μm

Inhalation

1.000

1.000

1.000

1.000

1.000

0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050

f1

e(g)

9.6 × 10–11

4.6 × 10–10

7.9 × 10–11

1.4 × 10–10

8.4 × 10–11

2.6 × 10–9
4.1 × 10–10
2.9 × 10–9
3.9 × 10–10
2.7 × 10–11
2.7 × 10–11
5.3 × 10–11
5.9 × 10–11
4.7 × 10–11
5.1 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

149

1.47 d

2.39 h

0.530 h

Br‑82

Br‑83

Br‑84

Rb‑79
Rb‑81
Rb‑81m
Rb‑82m
Rb‑83
Rb‑84
Rb‑86
Rb‑87
Rb‑88
Rb‑89

0.382 h4.58 h
0.533 h6.20 h86.2 d32.8 d
18.6 d
4.70 × 1010 a
0.297 h0.253 h4.42 hBr‑80mRubidium0.290 hPhysicalhalf-life

Br‑80

Radionuclidea

F
F
F
F
F
F
F
F
F
F

F
M
F
M
F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

1.7 × 10–11
3.7 × 10–11
7.3 × 10–12
1.2 × 10–10
7.1 × 10–10
1.1 × 10–9
9.6 × 10–10
5.1 × 10–10
1.7 × 10–11
1.4 × 10–11

6.3 × 10
1.0 × 10–11
3.5 × 10–11
7.6 × 10–11
3.7 × 10–10
6.4 × 10–10
1.7 × 10–11
4.8 × 10–11
2.3 × 10–11
3.9 × 10–11–12e(g)1 μm

Inhalation

3.0 × 10–11
6.8 × 10–11
1.3 × 10–11
2.2 × 10–10
1.0 × 10–9
1.5 × 10–9
1.3 × 10–9
7.6 × 10–10
2.8 × 10–11
2.5 × 10–11

1.1 × 10
1.7 × 10–11
5.8 × 10–11
1.0 × 10–10
6.4 × 10–10
8.8 × 10–10
2.9 × 10–11
6.7 × 10–11
4.0 × 10–11
6.2 × 10–11–11e(g)5 μm

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000

1.000

1.000

1.000

1.000

f1

e(g)

5.0 × 10–11
5.4 × 10–11
9.7 × 10–12
1.3 × 10–10
1.9 × 10–9
2.8 × 10–9
2.8 × 10–9
1.5 × 10–9
9.0 × 10–11
4.7 × 10–11

8.8 × 10–11

4.3 × 10–11

5.4 × 10–10

1.1 × 10–10

3.1 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

150

1.67 h

0.425 h25.0 d1.35 d64.8 d

1.16 h2.80 h50.5 d29.1 a9.50 h

Sr‑81

Sr‑82

Sr‑83

Sr‑85

Sr‑85m

Sr‑87m

Sr‑89

Sr‑90

Sr‑91

Physicalhalf-life

Sr‑80

Strontium

Radionuclidea

F
S
F
S
F
S
F
S
F
S
F
S
F
S
F
S
F
S
F
S

Type
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010

f1
7.6 × 10–11
1.4 × 10–10
2.2 × 10–11
3.8 × 10–11
2.2 × 10–9
1.0 × 10–8
1.7 × 10–10
3.4 × 10–10
3.9 × 10–10
7.7 × 10–10
3.1 × 10–12
4.5 × 10–12
1.2 × 10–11
2.2 × 10–11
1.0 × 10–9
7.5 × 10–9
2.4 × 10–8
1.5 × 10–7
1.7 × 10–10
4.1 × 10–10e(g)1 μm

Inhalation

1.3 × 10–10
2.1 × 10–10
3.9 × 10–11
6.1 × 10–11
3.3 × 10–9
7.7 × 10–9
3.0 × 10–10
4.9 × 10–10
5.6 × 10–10
6.4 × 10–10
5.6 × 10–12
7.4 × 10–12
2.2 × 10–11
3.5 × 10–11
1.4 × 10–9
5.6 × 10–9
3.0 × 10–8
7.7 × 10–8
2.9 × 10–10
5.7 × 10–10

e(g)5 μm
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010

f1

e(g)
3.4 × 10–10
3.5 × 10–10
7.7 × 10–11
7.8 × 10–11
6.1 × 10–9
6.0 × 10–9
4.9 × 10–10
5.8 × 10–10
5.6 × 10–10
3.3 × 10–10
6.1 × 10–12
6.1 × 10–12
3.0 × 10–11
3.3 × 10–11
2.6 × 10–9
2.3 × 10–9
2.8 × 10–8
2.7 × 10–9
6.5 × 10–10
7.6 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

151

14.7 h0.800 h3.35 d107 d2.67 d

3.19 h

58.5 d0.828 h3.54 h

Y‑86m

Y‑87

Y‑88

Y‑90

Y‑90m

Y‑91

Y‑91m

Y‑92

2.71 hPhysicalhalf-life

Y‑86

Yttrium

Sr‑92

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
S

Type

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.010

f1

4.8 × 10–10
4.9 × 10–10
2.9 × 10–11
3.0 × 10–11
3.8 × 10–10
4.0 × 10–10
3.9 × 10–9
4.1 × 10–9
1.4 × 10–9
1.5 × 10–9
9.6 × 10–11
1.0 × 10–10
6.7 × 10–9
8.4 × 10–9
1.0 × 10–11
1.1 × 10–11
1.9 × 10–10
2.0 × 10–10

1.1 × 10
2.3 × 10–10–10e(g)1 μm

Inhalation

8.0 × 10–10
8.1 × 10–10
4.8 × 10–11
4.9 × 10–11
5.2 × 10–10
5.3 × 10–10
3.3 × 10–9
3.0 × 10–9
1.6 × 10–9
1.7 × 10–9
1.3 × 10–10
1.3 × 10–10
5.2 × 10–9
6.1 × 10–9
1.4 × 10–11
1.5 × 10–11
2.7 × 10–10
2.8 × 10–10

1.8 × 10
3.4 × 10–10–10e(g)5 μm

9.6 × 10–10
5.6 × 10–11
5.5 × 10–10
1.3 × 10–9
2.7 × 10–9
1.7 × 10–10
2.4 × 10–9
1.1 × 10–11
4.9 × 10–10

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

4.3 × 10–10
4.9 × 10–10e(g)1.0 × 10–4

0.300
0.010

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

152

0.318 h0.178 h

Y‑94

Y‑95

16.5 h83.4 d3.27 d1.53 × 106 a

64.0 d

Zr‑86

Zr‑88

Zr‑89

Zr‑93

Zr‑95

Zirconium

10.1 hPhysicalhalf-life

Y‑93

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

M
S
M
S
M
S

Type
–4

0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002

1.0 × 10
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

f1

3.0 × 10–10
4.3 × 10–10
4.5 × 10–10
3.5 × 10–9
2.5 × 10–9
3.3 × 10–9
3.1 × 10–10
5.3 × 10–10
5.5 × 10–10
2.5 × 10–8
9.6 × 10–9
3.1 × 10–9
2.5 × 10–9
4.5 × 10–9
5.5 × 10–9

4.1 × 10
4.3 × 10–10
2.8 × 10–11
2.9 × 10–11
1.6 × 10–11
1.7 × 10–11–10e(g)1 μm

Inhalation

5.2 × 10–10
6.8 × 10–10
7.0 × 10–10
4.1 × 10–9
1.7 × 10–9
1.8 × 10–9
5.2 × 10–10
7.2 × 10–10
7.5 × 10–10
2.9 × 10–8
6.6 × 10–9
1.7 × 10–9
3.0 × 10–9
3.6 × 10–9
4.2 × 10–9

5.7 × 10
6.0 × 10–10
4.4 × 10–11
4.6 × 10–11
2.5 × 10–11
2.6 × 10–11–10e(g)5 μm

4.6 × 10–11

1.0 × 10–4

0.002

0.002

0.002

0.002

8.8 × 10–10

2.8 × 10–10

7.9 × 10–10

3.3 × 10–10

8.6 × 10–10

8.1 × 10–11

1.0 × 10–4

0.002

1.2 × 10–9

1.0 × 10

e(g)
–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

153

0.238 h2.03 h1.10 h

14.6 h13.6 a2.03 × 104 a

35.1 d3.61 d23.3 hNb‑89

Nb‑89m

Nb‑90

Nb‑93m

Nb‑94

Nb‑95

Nb‑95mNb‑96

16.9 hPhysicalhalf-life

Nb‑88

Niobium

Zr‑97

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M
S

Type

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.002
0.002
0.002

f1

2.9 × 10–11
3.0 × 10–11
1.2 × 10–10
1.3 × 10–10
7.1 × 10–11
7.4 × 10–11
6.6 × 10–10
6.9 × 10–10
4.6 × 10–10
1.6 × 10–9
1.0 × 10–8
4.5 × 10–8
1.4 × 10–9
1.6 × 10–9
7.6 × 10–10
8.5 × 10–10
6.5 × 10–10
6.8 × 10–10

4.2 × 10
9.4 × 10–10
1.0 × 10–9–10e(g)1 μm

Inhalation

4.8 × 10–11
5.0 × 10–11
1.8 × 10–10
1.9 × 10–10
1.1 × 10–10
1.2 × 10–10
1.0 × 10–9
1.1 × 10–9
2.9 × 10–10
8.6 × 10–10
7.2 × 10–9
2.5 × 10–8
1.3 × 10–9
1.3 × 10–9
7.7 × 10–10
8.5 × 10–10
9.7 × 10–10
1.0 × 10–9

7.4 × 10
1.3 × 10–9
1.4 × 10–9–10e(g)5 μm

0.010

0.010

0.010

0.010

0.010

0.010

0.010

0.010

0.010

0.002

f1

e(g)

1.1 × 10–9

5.6 × 10–10

5.8 × 10–10

1.7 × 10–9

1.2 × 10–10

1.2 × 10–9

1.4 × 10–10

3.0 × 10–10

6.3 × 10–11

2.1 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

154

0.858 hNb‑98

3.50 × 103 a6.85 h

2.75 d

0.244 h

Mo‑93

Mo‑93m

Mo‑99

Mo‑1012.75 h

0.725 hTc‑93

Tc‑93mTechnetium

5.67 hMo‑90

Molybdenum

1.20 hPhysicalhalf-life

Nb‑97

Radionuclidea

F
M
F
M

F
S
F
S
F
S
F
S
F
S

M
S
M
S

Type

0.800
0.800
0.800
0.800

0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050

0.010
0.010
0.010
0.010

f1

3.4 × 10–11
3.6 × 10–11
1.5 × 10–11
1.7 × 10–11

1.7 × 10–10
3.7 × 10–10
1.0 × 10–9
2.2 × 10–9
1.0 × 10–10
1.8 × 10–10
2.3 × 10–10
9.7 × 10–10
1.5 × 10–11
2.7 × 10–11

4.4 × 10
4.7 × 10–11
5.9 × 10–11
6.1 × 10–11–11e(g)1 μm

Inhalation

6.2 × 10–11
6.5 × 10–11
2.6 × 10–11
3.1 × 10–11

2.9 × 10–10
5.6 × 10–10
1.4 × 10–9
1.2 × 10–9
1.9 × 10–10
3.0 × 10–10
3.6 × 10–10
1.1 × 10–9
2.7 × 10–11
4.5 × 10–11

6.9 × 10
7.2 × 10–11
9.6 × 10–11
9.9 × 10–11–11e(g)5 μm

0.800

0.800

0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050
0.800
0.050

0.010

0.010

f1

e(g)

2.4 × 10–11

4.9 × 10–11

3.1 × 10–10
6.2 × 10–10
2.6 × 10–9
2.0 × 10–10
1.6 × 10–10
2.8 × 10–10
7.4 × 10–10
1.2 × 10–9
4.2 × 10–11
4.2 × 10–11

1.1 × 10–10

6.8 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

155

4.88 h

0.867 h20.0 h

61.0 d

4.28 d

0.858 h2.60 × 106 a

87.0 d

4.20 × 106 a

2.13 × 105 a

6.02 hTc‑94m

Tc‑95

Tc‑95m

Tc‑96

Tc‑96m

Tc‑97

Tc‑97m

Tc‑98

Tc‑99

Tc‑99mPhysicalhalf-life

Tc‑94

Radionuclidea
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

f1
1.2 × 10
1.3 × 10–10
4.3 × 10–11
4.9 × 10–11
1.0 × 10–10
1.0 × 10–10
3.1 × 10–10
8.7 × 10–10
6.0 × 10–10
7.1 × 10–10
6.5 × 10–12
7.7 × 10–12
4.5 × 10–11
2.1 × 10–10
2.8 × 10–10
3.1 × 10–9
1.0 × 10–9
8.1 × 10–9
2.9 × 10–10
3.9 × 10–9
1.2 × 10–11
1.9 × 10–11–10e(g)1 μm

Inhalation

2.1 × 10
2.2 × 10–10
6.9 × 10–11
8.0 × 10–11
1.8 × 10–10
1.8 × 10–10
4.8 × 10–10
8.6 × 10–10
9.8 × 10–10
1.0 × 10–9
1.1 × 10–11
1.1 × 10–11
7.2 × 10–11
1.6 × 10–10
4.0 × 10–10
2.7 × 10–9
1.5 × 10–9
6.1 × 10–9
4.0 × 10–10
3.2 × 10–9
2.0 × 10–11
2.9 × 10–11–10e(g)5 μm

0.800

0.800

0.800

0.800

0.800

0.800

0.800

0.800

0.800

0.800

0.800

f1

e(g)

2.2 × 10–11

7.8 × 10–10

2.3 × 10–9

6.6 × 10–10

8.3 × 10–11

1.3 × 10–11

1.1 × 10–9

6.2 × 10–10

1.6 × 10–10

1.1 × 10–10

1.8 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

156

0.303 hTc‑1040.863 h2.90 d39.3 d

4.44 h1.01 a

Ru‑94

Ru‑97

Ru‑103Ru‑105

Ru‑106

Ruthenium

0.237 hPhysicalhalf-life

Tc‑101

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
F
M

Type

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.800
0.800
0.800
0.800

f1

2.7 × 10–11
4.4 × 10–11
4.6 × 10–11
6.7 × 10–11
1.1 × 10–10
1.1 × 10–10
4.9 × 10–10
2.3 × 10–9
2.8 × 10–9
7.1 × 10–11
1.7 × 10–10
1.8 × 10–10
8.0 × 10–9
2.6 × 10–8
6.2 × 10–8

8.7 × 10
1.3 × 10–11
2.4 × 10–11
3.0 × 10–11–12e(g)1 μm

Inhalation

4.9 × 10–11
7.2 × 10–11
7.4 × 10–11
1.2 × 10–10
1.6 × 10–10
1.6 × 10–10
6.8 × 10–10
1.9 × 10–9
2.2 × 10–9
1.3 × 10–10
2.4 × 10–10
2.5 × 10–10
9.8 × 10–9
1.7 × 10–8
3.5 × 10–8

1.5 × 10
2.1 × 10–11
3.9 × 10–11
4.8 × 10–11–11e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.800

0.800

f1

e(g)

7.0 × 10–9

2.6 × 10–10

7.3 × 10–10

1.5 × 10–10

9.4 × 10–11

8.1 × 10–11

1.9 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

157

16.0 d

4.70 h20.8 h3.20 a4.34 d

2.90 a207 d

Rh‑99mRh‑100Rh‑101

Rh‑101m

Rh‑102

Rh‑102m

Physicalhalf-life

Rh‑99

Rhodium

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1
3.3 × 10–10
7.3 × 10–10
8.3 × 10–10
3.0 × 10–11
4.1 × 10–11
4.3 × 10–11
2.8 × 10–10
3.6 × 10–10
3.7 × 10–10
1.4 × 10–9
2.2 × 10–9
5.0 × 10–9
1.0 × 10–10
2.0 × 10–10
2.1 × 10–10
7.3 × 10–9
6.5 × 10–9
1.6 × 10–8
1.5 × 10–9
3.8 × 10–9
6.7 × 10–9e(g)1 μm

Inhalation

4.9 × 10–10
8.2 × 10–10
8.9 × 10–10
5.7 × 10–11
7.2 × 10–11
7.3 × 10–11
5.1 × 10–10
6.2 × 10–10
6.3 × 10–10
1.7 × 10–9
1.7 × 10–9
3.1 × 10–9
1.7 × 10–10
2.5 × 10–10
2.7 × 10–10
8.9 × 10–9
5.0 × 10–9
9.0 × 10–9
1.9 × 10–9
2.7 × 10–9
4.2 × 10–9e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.050

0.050

f1

e(g)

1.2 × 10–9

2.6 × 10–9

2.2 × 10–10

5.5 × 10–10

7.1 × 10–10

6.6 × 10–11

5.1 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

158

1.47 d

2.20 h

0.362 hRh‑105

Rh‑106m

Rh‑107

3.63 d8.27 h

17.0 dPd‑100

Pd‑101

Pd‑103

Palladium

0.935 hPhysicalhalf-life

Rh‑103m

Radionuclidea

F
M
S
F
M
S
F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1

4.9 × 10–10
7.9 × 10–10
8.3 × 10–10
4.2 × 10–11
6.2 × 10–11
6.4 × 10–11
9.0 × 10–11
3.5 × 10–10
4.0 × 10–10

8.6 × 10
2.3 × 10–12
2.5 × 10–12
8.7 × 10–11
3.1 × 10–10
3.4 × 10–10
7.0 × 10–11
1.1 × 10–10
1.2 × 10–10
9.6 × 10–12
1.7 × 10–11
1.7 × 10–11–13e(g)1 μm

Inhalation

7.6 × 10–10
9.5 × 10–10
9.7 × 10–10
7.5 × 10–11
9.8 × 10–11
1.0 × 10–10
1.2 × 10–10
3.0 × 10–10
2.9 × 10–10

1.2 × 10
2.4 × 10–12
2.5 × 10–12
1.5 × 10–10
4.1 × 10–10
4.4 × 10–10
1.3 × 10–10
1.8 × 10–10
1.9 × 10–10
1.6 × 10–11
2.7 × 10–11
2.8 × 10–11–12e(g)5 μm

0.005

0.005

0.005

0.050

0.050

0.050

0.050

f1

e(g)

1.9 × 10–10

9.4 × 10–11

9.4 × 10–10

2.4 × 10–11

1.6 × 10–10

3.7 × 10–10

3.8 × 10–12

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

159

13.4 h

Pd‑1090.215 h1.09 h1.15 h

0.558 h41.0 dAg‑102

Ag‑103

Ag‑104Ag‑104m

Ag‑105

Silver6.50 × 10 a

6

Physicalhalf-life

Pd‑107

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S
F
M
S

Type

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.005
0.005
0.005
0.005
0.005
0.005

f1

1.4 × 10–11
1.8 × 10–11
1.9 × 10–11
1.6 × 10–11
2.7 × 10–11
2.8 × 10–11
3.0 × 10–11
3.9 × 10–11
4.0 × 10–11
1.7 × 10–11
2.6 × 10–11
2.7 × 10–11
5.4 × 10–10
6.9 × 10–10
7.8 × 10–10

2.6 × 10
8.0 × 10–11
5.5 × 10–10
1.2 × 10–10
3.4 × 10–10
3.6 × 10–10–11e(g)1 μm

Inhalation

2.4 × 10–11
3.2 × 10–11
3.2 × 10–11
2.8 × 10–11
4.3 × 10–11
4.5 × 10–11
5.7 × 10–11
6.9 × 10–11
7.1 × 10–11
3.1 × 10–11
4.4 × 10–11
4.5 × 10–11
8.0 × 10–10
7.0 × 10–10
7.3 × 10–10

3.3 × 10
5.2 × 10–11
2.9 × 10–10
2.1 × 10–10
4.7 × 10–10
5.0 × 10–10–11e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.005

0.005

f1

e(g)

4.7 × 10–10

5.4 × 10–11

6.0 × 10–11

4.3 × 10–11

4.0 × 10–11

5.5 × 10–10

3.7 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

160

0.399 h8.41 d

1.27 × 102 a

250 d7.45 d

3.12 h

0.333 hAg‑106m

Ag‑108m

Ag‑110m

Ag‑111

Ag‑112

Ag‑115

Physicalhalf-life

Ag‑106

Radionuclidea
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1
9.8 × 10
1.6 × 10–11
1.6 × 10–11
1.1 × 10–9
1.1 × 10–9
1.1 × 10–9
6.1 × 10–9
7.0 × 10–9
3.5 × 10–8
5.5 × 10–9
7.2 × 10–9
1.2 × 10–8
4.1 × 10–10
1.5 × 10–9
1.7 × 10–9
8.2 × 10–11
1.7 × 10–10
1.8 × 10–10
1.6 × 10–11
2.8 × 10–11
3.0 × 10–11–12e(g)1 μm

Inhalation

1.7 × 10
2.6 × 10–11
2.7 × 10–11
1.6 × 10–9
1.5 × 10–9
1.4 × 10–9
7.3 × 10–9
5.2 × 10–9
1.9 × 10–8
6.7 × 10–9
5.9 × 10–9
7.3 × 10–9
5.7 × 10–10
1.5 × 10–9
1.6 × 10–9
1.4 × 10–10
2.5 × 10–10
2.6 × 10–10
2.6 × 10–11
4.3 × 10–11
4.4 × 10–11–11e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.050

0.050

f1

e(g)

6.0 × 10–11

4.3 × 10–10

1.3 × 10–9

2.8 × 10–9

2.3 × 10–9

1.5 × 10–9

3.2 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

161

0.961 h6.49 h1.27 a9.30 × 1015 a

13.6 a2.23 d44.6 d

Cd‑107

Cd‑109

Cd‑113

Cd‑113m

Cd‑115

Cd‑115m

Physicalhalf-life

Cd‑104

Cadmium

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1
2.7 × 10–11
3.6 × 10–11
3.7 × 10–11
2.3 × 10–11
8.1 × 10–11
8.7 × 10–11
8.1 × 10–9
6.2 × 10–9
5.8 × 10–9
1.2 × 10–7
5.3 × 10–8
2.5 × 10–8
1.1 × 10–7
5.0 × 10–8
3.0 × 10–8
3.7 × 10–10
9.7 × 10–10
1.1 × 10–9
5.3 × 10–9
5.9 × 10–9
7.3 × 10–9e(g)1 μm

Inhalation

5.0 × 10–11
6.2 × 10–11
6.3 × 10–11
4.2 × 10–11
1.0 × 10–10
1.1 × 10–10
9.6 × 10–9
5.1 × 10–9
4.4 × 10–9
1.4 × 10–7
4.3 × 10–8
2.1 × 10–8
1.3 × 10–7
4.0 × 10–8
2.4 × 10–8
5.4 × 10–10
1.2 × 10–9
1.3 × 10–9
6.4 × 10–9
5.5 × 10–9
5.5 × 10–9e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.050

0.050

f1

e(g)

3.3 × 10–9

1.4 × 10–9

2.3 × 10–8

2.5 × 10–8

2.0 × 10–9

6.2 × 10–11

5.8 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

162

3.36 h

Cd‑117m

4.20 h

4.90 h1.15 h2.83 d0.240 h1.66 h49.5 dIn‑109In‑110In‑110m

In‑111

In‑112

In‑113m

In‑114m

Indium2.49 hPhysicalhalf-life

Cd‑117

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M

F
M
S
F
M
S

Type

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.050
0.050
0.050
0.050
0.050
0.050

f1

3.2 × 10–11
4.4 × 10–11
1.2 × 10–10
1.4 × 10–10
3.1 × 10–11
5.0 × 10–11
1.3 × 10–10
2.3 × 10–10
5.0 × 10–12
7.8 × 10–12
1.0 × 10–11
2.0 × 10–11
9.3 × 10–9
5.9 × 10–9

7.3 × 10
1.6 × 10–10
1.7 × 10–10
1.0 × 10–10
2.0 × 10–10
2.1 × 10–10–11e(g)1 μm

Inhalation

5.7 × 10–11
7.3 × 10–11
2.2 × 10–10
2.5 × 10–10
5.5 × 10–11
8.1 × 10–11
2.2 × 10–10
3.1 × 10–10
8.6 × 10–12
1.3 × 10–11
1.9 × 10–11
3.2 × 10–11
1.1 × 10–8
5.9 × 10–9

1.3 × 10
2.4 × 10–10
2.5 × 10–10
1.9 × 10–10
3.1 × 10–10
3.2 × 10–10–10e(g)5 μm

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.050

0.050

f1

e(g)

4.1 × 10–9

2.8 × 10–11

1.0 × 10–11

2.9 × 10–10

1.0 × 10–10

2.4 × 10–10

6.6 × 10–11

2.8 × 10–10

2.8 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

163

4.49 h

0.902 h0.730 h1.94 h

0.300 hIn‑115m

In‑116m

In‑117

In‑117m

In‑119m

4.00 h

0.588 h115 d13.6 dSn‑110Sn‑111

Sn‑113

Sn‑117m

Tin

5.10 × 10 a

15

Physicalhalf-life

In‑115

Radionuclidea

F
M
F
M
F
M
F
M

F
M
F
M
F
M
F
M
F
M
F
M

Type

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

1.1 × 10–10
1.6 × 10–10
8.3 × 10–12
1.4 × 10–11
5.4 × 10–10
2.5 × 10–9
2.9 × 10–10
2.3 × 10–9

3.9 × 10
1.5 × 10–7
2.5 × 10–11
6.0 × 10–11
3.0 × 10–11
4.8 × 10–11
1.6 × 10–11
3.0 × 10–11
3.1 × 10–11
7.3 × 10–11
1.1 × 10–11
1.8 × 10–11–7e(g)1 μm

Inhalation

1.9 × 10–10
2.6 × 10–10
1.5 × 10–11
2.2 × 10–11
7.9 × 10–10
1.9 × 10–9
3.9 × 10–10
2.2 × 10–9

4.5 × 10
1.1 × 10–7
4.5 × 10–11
8.7 × 10–11
5.5 × 10–11
8.0 × 10–11
2.8 × 10–11
4.8 × 10–11
5.5 × 10–11
1.1 × 10–10
1.8 × 10–11
2.9 × 10–11–7

e(g)5 μm

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.020

f1

e(g)

7.1 × 10–10

7.3 × 10–10

2.3 × 10–11

3.5 × 10–10

4.7 × 10–11

1.2 × 10–10

3.1 × 10–11

6.4 × 10–11

8.6 × 10–11

3.2 × 10–8

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

164

55.0 a129 d0.668 h9.64 d

1.00 × 105 a2.10 h

0.985 hSn‑121m

Sn‑123

Sn‑123m

Sn‑125

Sn‑126

Sn‑127

Sn‑128

Sb‑1150.530 h1.13 dSn‑121

Antimony

293 dPhysicalhalf-life

Sn‑119m

Radionuclidea

F
M

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type

0.100
0.010

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

9.2 × 10–12
1.4 × 10–11

2.9 × 102.0 × 10–9
6.4 × 10–11
2.2 × 10–10
8.0 × 10–10
4.2 × 10–9
1.2 × 10–9
7.7 × 10–9
1.4 × 10–11
2.8 × 10–11
9.2 × 10–10
3.0 × 10–9
1.1 × 10–8
2.7 × 10–8
6.9 × 10–11
1.3 × 10–10
5.4 × 10–11
9.6 × 10–11–10e(g)1 μm

Inhalation

1.7 × 10–11
2.3 × 10–11

3.6 × 10
1.5 × 10–9
1.0 × 10–10
2.8 × 10–10
9.7 × 10–10
3.3 × 10–9
1.6 × 10–9
5.6 × 10–9
2.4 × 10–11
4.4 × 10–11
1.3 × 10–9
2.8 × 10–9
1.4 × 10–8
1.8 × 10–8
1.2 × 10–10
2.0 × 10–10
9.5 × 10–11
1.5 × 10–10–10e(g)5 μm

0.100

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.020

0.020

f1

e(g)

2.4 × 10–11

1.5 × 10–10

2.0 × 10–10

4.7 × 10–9

3.1 × 10–9

3.8 × 10–11

2.1 × 10–9

3.8 × 10–10

2.3 × 10–10

3.4 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

165

0.263 h1.00 h2.80 h5.00 h

1.59 d0.265 h5.76 d2.70 d60.2 d

0.337 h2.77 aSb‑116m

Sb‑117

Sb‑118m

Sb‑119Sb‑120Sb‑120m

Sb‑122

Sb‑124

Sb‑124m

Sb‑125

Physicalhalf-life

Sb‑116

Radionuclidea
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010

f1
9.9 × 10
1.4 × 10–11
3.5 × 10–11
5.0 × 10–11
9.3 × 10–12
1.7 × 10–11
1.0 × 10–10
1.3 × 10–10
2.5 × 10–11
3.7 × 10–11
4.9 × 10–12
7.4 × 10–12
5.9 × 10–10
1.0 × 10–9
3.9 × 10–10
1.0 × 10–9
1.3 × 10–9
6.1 × 10–9
3.0 × 10–12
5.5 × 10–12
1.4 × 10–9
4.5 × 10–9–12e(g)1 μm

Inhalation

1.8 × 10
2.3 × 10–11
6.4 × 10–11
8.5 × 10–11
1.7 × 10–11
2.7 × 10–11
1.9 × 10–10
2.3 × 10–10
4.5 × 10–11
5.9 × 10–11
8.5 × 10–12
1.2 × 10–11
9.8 × 10–10
1.3 × 10–9
6.3 × 10–10
1.2 × 10–9
1.9 × 10–9
4.7 × 10–9
5.3 × 10–12
8.3 × 10–12
1.7 × 10–9
3.3 × 10–9–11e(g)5 μm

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

f1

e(g)

1.1 × 10–9

8.0 × 10–12

2.5 × 10–9

1.7 × 10–9

1.2 × 10–9

1.4 × 10–11

8.1 × 10–11

2.1 × 10–10

1.8 × 10–11

6.7 × 10–11

2.6 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

166

0.317 h3.85 d

9.01 h

0.173 h4.32 h

0.667 h0.383 hSb‑126m

Sb‑127

Sb‑128

Sb‑128m

Sb‑129Sb‑130Sb‑1312.49 h

17.0 dTe‑116

Te‑121

Tellurium

12.4 dPhysicalhalf-life

Sb‑126

Radionuclidea

F
M
F
M

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type

0.300
0.300
0.300
0.300

0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010
0.100
0.010

f1

6.3 × 10–11
1.1 × 10–10
2.5 × 10–10
3.9 × 10–10

1.2 × 10–10
1.7 × 10–10
3.9 × 10–10
4.4 × 10–10

1.7 × 10
3.2 × 10–9
2.3 × 10–11
3.3 × 10–11
7.4 × 10–10
1.7 × 10–9
4.6 × 10–10
6.7 × 10–10
1.9 × 10–11
2.6 × 10–11
2.0 × 10–10
3.5 × 10–10
6.3 × 10–11
9.1 × 10–11
5.9 × 10–11
8.3 × 10–11–9–9

1.1 × 10
2.7 × 10–9
1.3 × 10–11
2.0 × 10–11
4.6 × 10–10
1.6 × 10–9
2.5 × 10–10
4.2 × 10–10
1.1 × 10–11
1.5 × 10–11
1.1 × 10–10
2.4 × 10–10
3.5 × 10–11
5.4 × 10–11
3.7 × 10–11
5.2 × 10–11

e(g)5 μme(g)1 μm

Inhalation

0.300

0.300

0.100

0.100

0.100

0.100

0.100

0.100

0.100

0.100

f1

e(g)

4.3 × 10–10

1.7 × 10–10

1.0 × 10–10

9.1 × 10–11

4.2 × 10–10

3.3 × 10–11

7.6 × 10–10

1.7 × 10–9

3.6 × 10–11

2.4 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

167

154 d

1.00 × 1013 a

120 d

58.0 d9.35 h109 d1.16 h33.6 d

0.417 h1.25 d3.26 dTe‑123

Te‑123m

Te‑125m

Te‑127

Te‑127m

Te‑129

Te‑129m

Te‑131

Te‑131m

Te‑132

Physicalhalf-life

Te‑121m

Radionuclidea
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300

f1
2.3 × 10
3.6 × 10–9
5.0 × 10–9
2.8 × 10–9
1.2 × 10–9
3.4 × 10–9
6.7 × 10–10
2.9 × 10–9
7.2 × 10–11
1.8 × 10–10
2.0 × 10–9
6.2 × 10–9
2.9 × 10–11
5.7 × 10–11
1.8 × 10–9
5.4 × 10–9
4.6 × 10–11
6.1 × 10–11
1.2 × 10–9
1.6 × 10–9
2.4 × 10–9
3.0 × 10–9

–9–9

1.8 × 10
4.2 × 10–9
4.0 × 10–9
2.6 × 10–9
9.7 × 10–10
3.9 × 10–9
5.1 × 10–10
3.3 × 10–9
4.2 × 10–11
1.2 × 10–10
1.6 × 10–9
7.2 × 10–9
1.7 × 10–11
3.8 × 10–11
1.3 × 10–9
6.3 × 10–9
2.3 × 10–11
3.8 × 10–11
8.7 × 10–10
1.1 × 10–9
1.8 × 10–9
2.2 × 10–9e(g)5 μme(g)1 μm

Inhalation

0.300

0.300

0.300

0.300

0.300

0.300

0.300

0.300

0.300

0.300

0.300

f1

e(g)

3.7 × 10–9

1.9 × 10–9

8.7 × 10–11

3.0 × 10–9

6.3 × 10–11

2.3 × 10–9

1.7 × 10–10

8.7 × 10–10

1.4 × 10–9

4.4 × 10–9

2.3 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

168

0.696 hTe‑134

I‑120
I‑120m
I‑121
I‑123
I‑124
I‑125
I‑126
I‑128
I‑129
I‑130
I‑131
I‑132
I‑132m
I‑133

1.35 h
0.883 h2.12 h13.2 h
4.18 d60.1 d
13.0 d
0.416 h1.57 × 107 a
12.4 h8.04 d2.30 h
1.39 h20.8 h

0.923 hTe‑133m

Iodine0.207 hPhysicalhalf-life

Te‑133

Radionuclidea

F
F
F
F
F
F
F
F
F
F
F
F
F
F

F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.300
0.300
0.300
0.300
0.300
0.300

f1

1.0 × 10–10
8.7 × 10–11
2.8 × 10–11
7.6 × 10–11
4.5 × 10–9
5.3 × 10–9
1.0 × 10–8
1.4 × 10–11
3.7 × 10–8
6.9 × 10–10
7.6 × 10–9
9.6 × 10–11
8.1 × 10–11
1.5 × 10–9

2.0 × 10
2.7 × 10–11
8.4 × 10–11
1.2 × 10–10
5.0 × 10–11
7.1 × 10–11–11e(g)1 μm

Inhalation

1.9 × 10–10
1.4 × 10–10
3.9 × 10–11
1.1 × 10–10
6.3 × 10–9
7.3 × 10–9
1.4 × 10–8
2.2 × 10–11
5.1 × 10–8
9.6 × 10–10
1.1 × 10–8
2.0 × 10–10
1.1 × 10–10
2.1 × 10–9

3.8 × 10
4.4 × 10–11
1.2 × 10–10
1.9 × 10–10
8.3 × 10–11
1.1 × 10–10–11e(g)5 μm

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.300

0.300

0.300

f1

e(g)

3.4 × 10–10
2.1 × 10–10
8.2 × 10–11
2.1 × 10–10
1.3 × 10–8
1.5 × 10–8
2.9 × 10–8
4.6 × 10–11
1.1 × 10–7
2.0 × 10–9
2.2 × 10–8
2.9 × 10–10
2.2 × 10–10
4.3 × 10–9

1.1 × 10–10

2.8 × 10–10

7.2 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

169

Ba‑126
Ba‑128
Ba‑131

BariumCs‑125
Cs‑127
Cs‑129Cs‑130Cs‑131
Cs‑132
Cs‑134
Cs‑134m
Cs‑135
Cs‑135m
Cs‑136
Cs‑137
Cs‑138

Caesium

I‑134
I‑135

Radionuclidea

1.61 h
2.43 d11.8 d0.750 h6.25 h1.34 d
0.498 h9.69 d6.48 d
2.06 a2.90 h2.30 × 106 a
0.883 h13.1 d30.0 a0.536 h0.876 h6.61 hPhysicalhalf-life

F
F
F

F
F
F
F
F
F
F
F
F
F
F
F
F

F
F

Type

0.100
0.100
0.100

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000

f1

7.8 × 10–11
8.0 × 10–10
2.3 × 10–10

1.3 × 10–11
2.2 × 10–11
4.5 × 10–11
8.4 × 10–12
2.8 × 10–11
2.4 × 10–10
6.8 × 10–9
1.5 × 10–11
7.1 × 10–10
1.3 × 10–11
1.3 × 10–9
4.8 × 10–9
2.6 × 10–11

4.8 × 10
3.3 × 10–10–11e(g)1 μm

Inhalation

1.2 × 10–10
1.3 × 10–9
3.5 × 10–10

2.3 × 10–11
4.0 × 10–11
8.1 × 10–11
1.5 × 10–11
4.5 × 10–11
3.8 × 10–10
9.6 × 10–9
2.6 × 10–11
9.9 × 10–10
2.4 × 10–11
1.9 × 10–9
6.7 × 10–9
4.6 × 10–11

7.9 × 10
4.6 × 10–10–11e(g)5 μm

0.100
0.100
0.100

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000

f1

e(g)

2.6 × 10–10
2.7 × 10–9
4.5 × 10–10

3.5 × 10–11
2.4 × 10–11
6.0 × 10–11
2.8 × 10–11
5.8 × 10–11
5.0 × 10–10
1.9 × 10–8
2.0 × 10–11
2.0 × 10–9
1.9 × 10–11
3.0 × 10–9
1.3 × 10–8
9.2 × 10–11

1.1 × 10–10
9.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

170

0.983 h4.80 h19.5 h6.00 × 104 a

1.35 × 1011 a

1.68 dLa‑132

La‑135

La‑137

La‑138

La‑1400.243 h10.7 a1.62 d
1.20 d1.38 h12.7 d0.305 h0.177 hPhysicalhalf-life

La‑131Lanthanum

Ba‑131m
Ba‑133
Ba‑133m
Ba‑135m
Ba‑139Ba‑140Ba‑141
Ba‑142

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M

F
F
F
F
F
F
F
F

Type

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

1.4 × 10–11
2.3 × 10–11
1.1 × 10–10
1.7 × 10–10
1.1 × 10–11
1.5 × 10–11
8.6 × 10–9
3.4 × 10–9
1.5 × 10–7
6.1 × 10–8
6.0 × 10–10
1.1 × 10–9

4.1 × 10
1.5 × 10–9
1.9 × 10–10
1.5 × 10–10
3.5 × 10–11
1.0 × 10–9
2.2 × 10–11
1.6 × 10–11–12e(g)1 μm

Inhalation

2.4 × 10–11
3.6 × 10–11
2.0 × 10–10
2.8 × 10–10
2.0 × 10–11
2.5 × 10–11
1.0 × 10–8
2.3 × 10–9
1.8 × 10–7
4.2 × 10–8
1.0 × 10–9
1.5 × 10–9

6.4 × 10
1.8 × 10–9
2.8 × 10–10
2.3 × 10–10
5.5 × 10–11
1.6 × 10–9
3.5 × 10–11
2.7 × 10–11–12e(g)5 μm

3.0 × 10–11

5.0 × 10–4

1.1 × 10–9
2.0 × 10–9

5.0 × 10–4
5.0 × 10–4

8.1 × 10–11

3.9 × 10–10

5.0 × 10–4

5.0 × 10–4

3.5 × 10–11

4.9 × 10–12
1.0 × 10–9
5.5 × 10–10
4.5 × 10–10
1.2 × 10–10
2.5 × 10–9
7.0 × 10–11
3.5 × 10–11e(g)5.0 × 10–4

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

171

1.54 h

0.237 hLa‑142

La‑1433.00 d

17.6 h9.00 h

1.43 d138 d32.5 d1.38 dCe‑134Ce‑135

Ce‑137

Ce‑137m

Ce‑139Ce‑141

Ce‑143

Cerium3.93 hPhysicalhalf-life

La‑141

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M
F
M
F
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

1.3 × 10–9
1.3 × 10–9
4.9 × 10–10
5.1 × 10–10
1.0 × 10–11
1.1 × 10–11
4.0 × 10–10
4.3 × 10–10
1.6 × 10–9
1.8 × 10–9
3.1 × 10–9
3.6 × 10–9
7.4 × 10–10
8.1 × 10–10

6.7 × 10
1.5 × 10–10
5.6 × 10–11
9.3 × 10–11
1.2 × 10–11
2.2 × 10–11–11e(g)1 μm

Inhalation

1.5 × 10–9
1.6 × 10–9
7.3 × 10–10
7.6 × 10–10
1.8 × 10–11
1.9 × 10–11
5.5 × 10–10
5.9 × 10–10
1.3 × 10–9
1.4 × 10–9
2.7 × 10–9
3.1 × 10–9
9.5 × 10–10
1.0 × 10–9

1.1 × 10
2.2 × 10–10
1.0 × 10–10
1.5 × 10–10
2.0 × 10–11
3.3 × 10–11–10e(g)5 μm

7.9 × 10–10
2.5 × 10–11
5.4 × 10–10
2.6 × 10–10
7.1 × 10–10
1.1 × 10–9

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.6 × 10–11

5.0 × 10–4

2.5 × 10–9

1.8 × 10–10

5.0 × 10–4

5.0 × 10–4

3.6 × 10–10

5.0 × 10

e(g)
–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

172

0.218 h1.28 h2.10 h

4.51 h19.1 h0.243 h13.6 d

0.288 h5.98 h

Pr‑137

Pr‑138m

Pr‑139Pr‑142

Pr‑142m

Pr‑143

Pr‑144

Pr‑145284 dPhysicalhalf-life

Pr‑136

Praseodymium

Ce‑144

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

M
S

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4

f1

1.4 × 10–11
1.5 × 10–11
2.1 × 10–11
2.2 × 10–11
7.6 × 10–11
7.9 × 10–11
1.9 × 10–11
2.0 × 10–11
5.3 × 10–10
5.6 × 10–10
6.7 × 10–12
7.1 × 10–12
2.1 × 10–9
2.3 × 10–9
1.8 × 10–11
1.9 × 10–11
1.6 × 10–10
1.7 × 10–10

3.4 × 10
4.9 × 10–8–8e(g)1 μm

Inhalation

2.4 × 10–11
2.5 × 10–11
3.4 × 10–11
3.5 × 10–11
1.3 × 10–10
1.3 × 10–10
2.9 × 10–11
3.0 × 10–11
7.0 × 10–10
7.4 × 10–10
8.9 × 10–12
9.4 × 10–12
1.9 × 10–9
2.2 × 10–9
2.9 × 10–11
3.0 × 10–11
2.5 × 10–10
2.6 × 10–10

2.3 × 10
2.9 × 10–8–8e(g)5 μm
–43.3 × 10–11
4.0 × 10–11
1.3 × 10–10
3.1 × 10–11
1.3 × 10–9
1.7 × 10–11
1.2 × 10–9
5.0 × 10–11
3.9 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.2 × 10–9e(g)5.0 × 10–4

5.0 × 10f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

173

0.844 h5.04 h

0.495 h5.50 h

2.49 h

11.0 d1.73 h

0.207 hNd‑138

Nd‑139Nd‑139m

Nd‑141

Nd‑147

Nd‑149Nd‑1510.227 hPhysicalhalf-life

Nd‑136

NeodymiumPr‑147

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

M
S

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4

f1

5.3 × 10–11
5.6 × 10–11
2.4 × 10–10
2.6 × 10–10
1.0 × 10–11
1.1 × 10–11
1.5 × 10–10
1.6 × 10–10
5.1 × 10–12
5.3 × 10–12
2.0 × 10–9
2.3 × 10–9
8.5 × 10–11
9.0 × 10–11
1.7 × 10–11
1.8 × 10–11

1.8 × 10
1.9 × 10–11–11e(g)1 μm

Inhalation

8.5 × 10–11
8.9 × 10–11
3.7 × 10–10
3.8 × 10–10
1.7 × 10–11
1.7 × 10–11
2.5 × 10–10
2.5 × 10–10
8.5 × 10–12
8.8 × 10–12
1.9 × 10–9
2.1 × 10–9
1.2 × 10–10
1.3 × 10–10
2.8 × 10–11
2.9 × 10–11

2.9 × 10
3.0 × 10–11–11e(g)5 μm
–49.9 × 10–11
6.4 × 10–10
2.0 × 10–11
2.5 × 10–10
8.3 × 10–12
1.1 × 10–9
1.2 × 10–10
3.0 × 10–11

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

3.3 × 10–11e(g)5.0 × 10–4

5.0 × 10f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

174

0.348 h

265 d

363 d

17.7 a5.53 a2.62 a5.37 d41.3 d

2.21 d

2.68 h

Pm‑143Pm‑144Pm‑145

Pm‑146

Pm‑147

Pm‑148Pm‑148m

Pm‑149Pm‑150Physicalhalf-life

Pm‑141

Promethium

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1
1.5 × 10–11
1.6 × 10–11
1.4 × 10–9
1.3 × 10–9
7.8 × 10–9
7.0 × 10–9
3.4 × 10–9
2.1 × 10–9
1.9 × 10–8
1.6 × 10–8
4.7 × 10–9
4.6 × 10–9
2.0 × 10–9
2.1 × 10–9
4.9 × 10–9
5.4 × 10–9
6.6 × 10–10
7.2 × 10–10
1.3 × 10–10
1.4 × 10–10e(g)1 μm

Inhalation

2.4 × 10–11
2.5 × 10–11
9.6 × 10–10
8.3 × 10–10
5.4 × 10–9
3.9 × 10–9
2.4 × 10–9
1.2 × 10–9
1.3 × 10–8
9.0 × 10–9
3.5 × 10–9
3.2 × 10–9
2.1 × 10–9
2.2 × 10–9
4.1 × 10–9
4.3 × 10–9
7.6 × 10–10
8.2 × 10–10
2.0 × 10–10
2.1 × 10–10

e(g)5 μm

3.6 × 10–11
2.3 × 10–10
9.7 × 10–10
1.1 × 10–10
9.0 × 10–10
2.6 × 10–10
2.7 × 10–9
1.8 × 10–9
9.9 × 10–10
2.6 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4e(g)5.0 × 10–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

175

Eu‑145
Eu‑146
Eu‑147
Eu‑148
Eu‑149Eu‑150Europium

Sm‑141
Sm‑141m
Sm‑142
Sm‑145
Sm‑146
Sm‑147
Sm‑151
Sm‑153
Sm‑155
Sm‑156

SamariumPm‑151

Radionuclidea

5.94 d
4.61 d24.0 d54.5 d93.1 d34.2 a0.170 h0.377 h1.21 h340 d1.03 × 108 a
1.06 × 1011 a
90.0 a1.95 d
0.368 h9.40 h

1.18 dPhysicalhalf-life

M
M
M
M
M
M

M
M
M
M
M
M
M
M
M
M

M
S

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4

f1

5.6 × 10–10
8.2 × 10–10
1.0 × 10–9
2.7 × 10–9
2.7 × 10–10
5.0 × 10–8

1.6 × 10–11
3.4 × 10–11
7.4 × 10–11
1.5 × 10–9
9.9 × 10–6
8.9 × 10–6
3.7 × 10–9
6.1 × 10–10
1.7 × 10–11
2.1 × 10–10

4.2 × 10
4.5 × 10–10–10e(g)1 μm

Inhalation

7.3 × 10–10
1.2 × 10–9
1.0 × 10–9
2.3 × 10–9
2.3 × 10–10
3.4 × 10–8

2.7 × 10–11
5.6 × 10–11
1.1 × 10–10
1.1 × 10–9
6.7 × 10–6
6.1 × 10–6
2.6 × 10–9
6.8 × 10–10
2.8 × 10–11
2.8 × 10–10

6.1 × 10
6.4 × 10–10–10e(g)5 μm
–45.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10f1

e(g)7.5 × 10–10
1.3 × 10–9
4.4 × 10–10
1.3 × 10–9
1.0 × 10–10
1.3 × 10–9

3.9 × 10–11
6.5 × 10–11
1.9 × 10–10
2.1 × 10–10
5.4 × 10–8
4.9 × 10–8
9.8 × 10–11
7.4 × 10–10
2.9 × 10–11
2.5 × 10–10

7.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

176

0.382 h48.3 d

1.59 d93.0 a9.40 d120 d

Gd‑146

Gd‑147

Gd‑148

Gd‑149Gd‑151

12.6 h13.3 a9.32 h8.80 a4.96 a15.2 d15.1 h
0.765 hPhysicalhalf-life

Gd‑145Gadolinium

Eu‑150m
Eu‑152
Eu‑152m
Eu‑154Eu‑155
Eu‑156
Eu‑157
Eu‑158

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M

M
M
M
M
M
M
M
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

1.5 × 10–11
2.1 × 10–11
4.4 × 10–9
6.0 × 10–9
2.7 × 10–10
4.1 × 10–10
2.5 × 10–5
1.1 × 10–5
2.6 × 10–10
7.0 × 10–10
7.8 × 10–10
8.1 × 10–10

1.9 × 10
3.9 × 10–8
2.2 × 10–10
5.0 × 10–8
6.5 × 10–9
3.3 × 10–9
3.2 × 10–10
4.8 × 10–11–10e(g)1 μm

Inhalation

2.6 × 10–11
3.5 × 10–11
5.2 × 10–9
4.6 × 10–9
4.5 × 10–10
5.9 × 10–10
3.0 × 10–5
7.2 × 10–6
4.5 × 10–10
7.9 × 10–10
9.3 × 10–10
6.5 × 10–10

2.8 × 10
2.7 × 10–8
3.2 × 10–10
3.5 × 10–8
4.7 × 10–9
3.0 × 10–9
4.4 × 10–10
7.5 × 10–11–10e(g)5 μm
–44.4 × 10–11
9.6 × 10–10
6.1 × 10–10
5.5 × 10–8
4.5 × 10–10
2.0 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

3.8 × 10–10
1.4 × 10–9
5.0 × 10–10
2.0 × 10–9
3.2 × 10–10
2.2 × 10–9
6.0 × 10–10
9.4 × 10–11e(g)5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

177

18.6 h

Gd‑159Tb‑147
Tb‑149Tb‑150Tb‑151
Tb‑153
Tb‑154
Tb‑155
Tb‑156
Tb‑156m
Tb‑156mʹ
Tb‑157
Tb‑158
Tb‑160Tb‑1611.65 h4.15 h3.27 h
17.6 h2.34 d
21.4 h5.32 d5.34 d
1.02 d
5.00 h
7.1 × 101 a
1.80 × 102 a
72.3 d
6.91 d242 d

Gd‑153

Terbium

1.08 × 10 a

14

Physicalhalf-life

Gd‑152

Radionuclidea

M
M
M
M
M
M
M
M
M
M
M
M
M
M

F
M
F
M
F
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

7.9 × 10–11
4.3 × 10–9
1.1 × 10–10
2.3 × 10–10
2.0 × 10–10
3.8 × 10–10
2.1 × 10–10
1.2 × 10–9
2.0 × 10–10
9.2 × 10–11
1.1 × 10–9
4.3 × 10–8
6.6 × 10–9
1.2 × 10–9

1.9 × 10
7.4 × 10–6
2.1 × 10–9
1.9 × 10–9
1.1 × 10–10
2.7 × 10–10–5e(g)1 μm

Inhalation

1.2 × 10–10
3.1 × 10–9
1.8 × 10–10
3.3 × 10–10
2.4 × 10–10
6.0 × 10–10
2.5 × 10–10
1.4 × 10–9
2.3 × 10–10
1.3 × 10–10
7.9 × 10–10
3.0 × 10–8
5.4 × 10–9
1.2 × 10–9

2.2 × 10
5.0 × 10–6
2.5 × 10–9
1.4 × 10–9
1.8 × 10–10
3.9 × 10–10–5e(g)5 μm
–4

1.6 × 10–10
2.5 × 10–10
2.5 × 10–10
3.4 × 10–10
2.5 × 10–10
6.5 × 10–10
2.1 × 10–10
1.2 × 10–9
1.7 × 10–10
8.1 × 10–11
3.4 × 10–11
1.1 × 10–9
1.6 × 10–9
7.2 × 10–10

4.9 × 10–10

5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

2.7 × 10–10

4.1 × 10–8e(g)5.0 × 10–4

5.0 × 10f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

178

Er‑161

Erbium

Ho‑155
Ho‑157
Ho‑159Ho‑161
Ho‑162
Ho‑162m
Ho‑164
Ho‑164m
Ho‑166
Ho‑166m
Ho‑167

Holmium

Dy‑155
Dy‑157
Dy‑159Dy‑165
Dy‑166

DysprosiumRadionuclidea

3.24 h0.800 h0.210 h0.550 h2.50 h
0.250 h1.13 h
0.483 h0.625 h1.12 d
1.20 × 103 a
3.10 h

10.0 h8.10 h144 d2.33 h
3.40 dPhysicalhalf-life

M

M
M
M
M
M
M
M
M
M
M
M

M
M
M
M
M

Type

5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

5.1 × 10–11

2.0 × 10–11
4.5 × 10–12
6.3 × 10–12
6.3 × 10–12
2.9 × 10–12
2.2 × 10–11
8.6 × 10–12
1.2 × 10–11
6.6 × 10–10
1.1 × 10–7
7.1 × 10–11

8.0 × 10–11
3.2 × 10–11
3.5 × 10–10
6.1 × 10–11
1.8 × 10–9e(g)1 μm

Inhalation

8.5 × 10–11

3.2 × 10–11
7.6 × 10–12
1.0 × 10–11
1.0 × 10–11
4.5 × 10–12
3.3 × 10–11
1.3 × 10–11
1.6 × 10–11
8.3 × 10–10
7.8 × 10–8
1.0 × 10–10

1.2 × 10–10
5.5 × 10–11
2.5 × 10–10
8.7 × 10–11
1.8 × 10–9e(g)5 μm

5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

e(g)

8.0 × 10–11

3.7 × 10–11
6.5 × 10–12
7.9 × 10–12
1.3 × 10–11
3.3 × 10–12
2.6 × 10–11
9.5 × 10–12
1.6 × 10–11
1.4 × 10–9
2.0 × 10–9
8.3 × 10–11

1.3 × 10–10
6.1 × 10–11
1.0 × 10–10
1.1 × 10–10
1.6 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

179

0.315 h2.36 d

0.292 hYb‑166

Yb‑1670.362 h7.70 h
9.24 d129 d1.92 a2.65 d8.24 h
0.253 h10.4 h
9.30 d7.52 h2.05 dPhysicalhalf-life

Yb‑162

Ytterbium

Tm‑162
Tm‑166
Tm‑167
Tm‑170Tm‑171
Tm‑172
Tm‑173
Tm‑175

Thulium

Er‑165
Er‑169Er‑171
Er‑172

Radionuclidea

M
S
M
S
M
S

M
M
M
M
M
M
M
M

M
M
M
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

1.4 × 10–11
1.4 × 10–11
7.2 × 10–10
7.6 × 10–10
6.5 × 10–12
6.9 × 10–12

1.6 × 10–11
1.8 × 10–10
1.1 × 10–9
6.6 × 10–9
1.3 × 10–9
1.1 × 10–9
1.8 × 10–10
1.9 × 10–11

8.3 × 10
9.8 × 10–10
2.2 × 10–10
1.1 × 10–9–12e(g)1 μm

Inhalation

2.2 × 10–11
2.3 × 10–11
9.1 × 10–10
9.5 × 10–10
9.0 × 10–12
9.5 × 10–12

2.7 × 10–11
2.8 × 10–10
1.0 × 10–9
5.2 × 10–9
9.1 × 10–10
1.4 × 10–9
2.6 × 10–10
3.1 × 10–11

1.4 × 10
9.2 × 10–10
3.0 × 10–10
1.2 × 10–9–11e(g)5 μm
–42.3 × 10–11
9.5 × 10–10
6.7 × 10–12

5.0 × 10–4
5.0 × 10–4

2.9 × 10–11
2.8 × 10–10
5.6 × 10–10
1.3 × 10–9
1.1 × 10–10
1.7 × 10–9
3.1 × 10–10
2.7 × 10–11

1.9 × 10–11
3.7 × 10–10
3.6 × 10–10
1.0 × 10–9e(g)5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)180

4.19 d

1.90 h1.23 h

Yb‑175

Yb‑177

Yb‑1781.42 d2.00 d8.22 d6.70 d1.37 a3.31 aLu‑169Lu‑170Lu‑171

Lu‑172

Lu‑173

Lu‑174

Lutetium

32.0 dPhysicalhalf-life

Yb‑169Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S

M
S
M
S
M
S
M
S

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

3.5 × 10–10
3.8 × 10–10
6.4 × 10–10
6.7 × 10–10
7.6 × 10–10
8.3 × 10–10
1.4 × 10–9
1.5 × 10–9
2.0 × 10–9
2.3 × 10–9
4.0 × 10–9
3.9 × 10–9

2.4 × 10
2.8 × 10–9
6.3 × 10–10
7.0 × 10–10
6.4 × 10–11
6.9 × 10–11
7.1 × 10–11
7.6 × 10–11–9e(g)1 μm

Inhalation

4.7 × 10–10
4.9 × 10–10
9.3 × 10–10
9.5 × 10–10
8.8 × 10–10
9.3 × 10–10
1.7 × 10–9
1.8 × 10–9
1.5 × 10–9
1.4 × 10–9
2.9 × 10–9
2.5 × 10–9

2.1 × 10
2.4 × 10–9
6.4 × 10–10
7.0 × 10–10
8.8 × 10–11
9.4 × 10–11
1.0 × 10–10
1.1 × 10–10–9e(g)5 μm

9.9 × 10–10
6.7 × 10–10
1.3 × 10–9
2.6 × 10–10
2.7 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

1.2 × 10–10

5.0 × 10–4

5.0 × 10–4

9.7 × 10–11

5.0 × 10–4

4.6 × 10–10

4.4 × 10–10

5.0 × 10–4

5.0 × 10–4

7.1 × 10–10

5.0 × 10

e(g)
–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

181

3.60 × 1010 a

3.68 h

6.71 d161 d0.473 h0.378 h4.59 hLu‑176

Lu‑176m

Lu‑177

Lu‑177m

Lu‑178

Lu‑178m

Lu‑17916.0 h

1.87 aHf‑170

Hf‑172

Hafnium

142 dPhysicalhalf-life

Lu‑174m

Radionuclidea

F
M
F
M

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type
–4

0.002
0.002
0.002
0.002

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

1.7 × 10–10
3.2 × 10–10
3.2 × 10–8
1.9 × 10–8

3.4 × 10
3.8 × 10–9
6.6 × 10–8
5.2 × 10–8
1.1 × 10–10
1.2 × 10–10
1.0 × 10–9
1.1 × 10–9
1.2 × 10–8
1.5 × 10–8
2.5 × 10–11
2.6 × 10–11
3.3 × 10–11
3.5 × 10–11
1.1 × 10–10
1.2 × 10–10–9e(g)1 μm

Inhalation

2.9 × 10–10
4.3 × 10–10
3.7 × 10–8
1.3 × 10–8

2.4 × 10
2.6 × 10–9
4.6 × 10–8
3.0 × 10–8
1.5 × 10–10
1.6 × 10–10
1.0 × 10–9
1.1 × 10–9
1.0 × 10–8
1.2 × 10–8
3.9 × 10–11
4.1 × 10–11
5.4 × 10–11
5.6 × 10–11
1.6 × 10–10
1.6 × 10–10–9e(g)5 μm
–45.3 × 10–10
1.7 × 10–9
4.7 × 10–11
3.8 × 10–11
2.1 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.002

1.0 × 10–9

4.8 × 10–10

1.7 × 10–10

5.0 × 10–4

0.002

1.8 × 10–9

5.3 × 10–10e(g)5.0 × 10–4

5.0 × 10f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

182

24.0 h

70.0 d

0.856 h31.0 a25.1 d5.50 h42.4 d

9.00 × 106 a

1.02 h1.07 h4.12 hHf‑175

Hf‑177m

Hf‑178m

Hf‑179m

Hf‑180m

Hf‑181

Hf‑182

Hf‑182m

Hf‑183

Hf‑184

Physicalhalf-life

Hf‑173

Radionuclidea
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002

f1
7.9 × 10
1.6 × 10–10
7.2 × 10–10
1.1 × 10–9
4.7 × 10–11
9.2 × 10–11
2.6 × 10–7
1.1 × 10–7
1.1 × 10–9
3.6 × 10–9
6.4 × 10–11
1.4 × 10–10
1.4 × 10–9
4.7 × 10–9
3.0 × 10–7
1.2 × 10–7
2.3 × 10–11
4.7 × 10–11
2.6 × 10–11
5.8 × 10–11
1.3 × 10–10
3.3 × 10–10–11e(g)1 μm

Inhalation

1.3 × 10
2.2 × 10–10
8.7 × 10–10
8.8 × 10–10
8.4 × 10–11
1.5 × 10–10
3.1 × 10–7
7.8 × 10–8
1.4 × 10–9
3.2 × 10–9
1.2 × 10–10
2.0 × 10–10
1.8 × 10–9
4.1 × 10–9
3.6 × 10–7
8.3 × 10–8
4.0 × 10–11
7.1 × 10–11
4.4 × 10–11
8.3 × 10–11
2.3 × 10–10
4.5 × 10–10–10e(g)5 μm

0.002

0.002

0.002

0.002

0.002

0.002

0.002

0.002

0.002

0.002

0.002

f1

e(g)

5.2 × 10–10

7.3 × 10–11

4.2 × 10–11

3.0 × 10–9

1.1 × 10–9

1.7 × 10–10

1.2 × 10–9

4.7 × 10–9

8.1 × 10–11

4.1 × 10–10

2.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

183

0.613 h3.65 h1.20 h10.5 h8.08 h2.36 d

2.20 h1.82 a1.00 × 1013 a

8.10 hTa‑173

Ta‑174

Ta‑175

Ta‑176

Ta‑177

Ta‑178

Ta‑179Ta‑180Ta‑180m

Physicalhalf-life

Ta‑172

Tantalum

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

f1
3.4 × 10–11
3.6 × 10–11
1.1 × 10–10
1.2 × 10–10
4.2 × 10–11
4.4 × 10–11
1.3 × 10–10
1.4 × 10–10
2.0 × 10–10
2.1 × 10–10
9.3 × 10–11
1.0 × 10–10
6.6 × 10–11
6.9 × 10–11
2.0 × 10–10
5.2 × 10–10
6.0 × 10–9
2.4 × 10–8
4.4 × 10–11
4.7 × 10–11

e(g)1 μm

Inhalation

5.5 × 10–11
5.7 × 10–11
1.6 × 10–10
1.6 × 10–10
6.3 × 10–11
6.6 × 10–11
2.0 × 10–10
2.0 × 10–10
3.2 × 10–10
3.3 × 10–10
1.2 × 10–10
1.3 × 10–10
1.0 × 10–10
1.1 × 10–10
1.3 × 10–10
2.9 × 10–10
4.6 × 10–9
1.4 × 10–8
5.8 × 10–11
6.2 × 10–11

e(g)5 μm

0.001

0.001

0.001

0.001

0.001

0.001

0.001

0.001

0.001

0.001

f1

e(g)

5.4 × 10–11

8.4 × 10–10

6.5 × 10–11

7.8 × 10–11

1.1 × 10–10

3.1 × 10–10

2.1 × 10–10

5.7 × 10–11

1.9 × 10–10

5.3 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

184

0.264 h5.10 d8.70 h

0.816 h0.175 hTa‑182m

Ta‑183

Ta‑184

Ta‑185

Ta‑1862.30 h2.25 h21.7 d

0.625 h

W‑176

W‑177

W‑178

W‑179

Tungsten

115 dPhysicalhalf-life

Ta‑182

Radionuclidea

F

F

F

F

M
S
M
S
M
S
M
S
M
S
M
S

Type

0.300

0.300

0.300

0.300

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

f1

7.6 × 10–11
4.6 × 10–11
1.2 × 10–10
1.8 × 10–12

4.4 × 10–11
2.6 × 10–11
7.6 × 10–11
9.9 × 10–13

5.8 × 10
7.4 × 10–9
3.4 × 10–11
3.6 × 10–11
1.8 × 10–9
2.0 × 10–9
6.0 × 10–10
6.3 × 10–10
6.8 × 10–11
7.2 × 10–11
3.0 × 10–11
3.1 × 10–11–9–9

7.2 × 10
9.7 × 10–9
2.1 × 10–11
2.2 × 10–11
1.8 × 10–9
2.0 × 10–9
4.1 × 10–10
4.4 × 10–10
4.6 × 10–11
4.9 × 10–11
1.8 × 10–11
1.9 × 10–11

e(g)5 μme(g)1 μm

Inhalation

0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010

0.001

0.001

0.001

0.001

0.001

0.001

f1

e(g)

1.0 × 10–10
1.1 × 10–10
5.8 × 10–11
6.1 × 10–11
2.2 × 10–10
2.5 × 10–10
3.3 × 10–12
3.3 × 10–12

3.3 × 10–11

6.8 × 10–11

6.8 × 10–10

1.3 × 10–9

1.2 × 10–11

1.5 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

185

75.1 d23.9 h69.4 d

W‑185

W‑187

W‑188

0.233 h0.220 h20.0 h

2.67 d12.7 h

38.0 dRe‑177

Re‑178

Re‑181

Re‑182

Re‑182m

Re‑184

Rhenium

121 dPhysicalhalf-life

W‑181

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M

F

F

F

F

Type

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

0.300

0.300

0.300

0.300

f1

3.3 × 10–10
8.4 × 10–10

2.0 × 10–10
5.9 × 10–10

1.0 × 10–11
1.4 × 10–11
1.1 × 10–11
1.5 × 10–11
1.9 × 10–10
2.5 × 10–10
6.8 × 10–10
1.3 × 10–9
1.5 × 10–10
2.0 × 10–10
4.6 × 10–10
1.8 × 10–9

1.7 × 10–11
2.2 × 10–11
1.8 × 10–11
2.4 × 10–11
3.0 × 10–10
3.7 × 10–10
1.1 × 10–9
1.7 × 10–9
2.4 × 10–10
3.0 × 10–10
7.0 × 10–10
1.8 × 10–9

2.2 × 10–10

4.3 × 10

1.4 × 10–10

2.8 × 10–11e(g)5 μm

–11e(g)1 μm

Inhalation

0.800

0.800

0.800

0.800

0.800

0.800

0.300
0.010
0.300
0.010
0.300
0.010
0.300
0.010

f1

e(g)

1.0 × 10–9

2.7 × 10–10

1.4 × 10–9

4.2 × 10–10

2.5 × 10–11

2.2 × 10–11

7.6 × 10–11
8.2 × 10–11
4.4 × 10–10
5.0 × 10–10
6.3 × 10–10
7.1 × 10–10
2.1 × 10–9
2.3 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

186

3.78 d2.00 × 105 a

5.00 × 1010 a

17.0 h0.3 h1.01 dRe‑186

Re‑186m

Re‑187

Re‑188

Re‑188m

Re‑1890.366 h1.75 hOs‑180Os‑181

Osmium165 d

Physicalhalf-life

Re‑184m

Radionuclidea

F
M
S
F
M
S

F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type

0.010
0.010
0.010
0.010
0.010
0.010

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

f1

8.8 × 10–12
1.4 × 10–11
1.5 × 10–11
3.6 × 10–11
6.3 × 10–11
6.6 × 10–11

6.1 × 10
6.1 × 10–9
5.3 × 10–10
1.1 × 10–9
8.5 × 10–10
1.1 × 10–8
1.9 × 10–12
6.0 × 10–12
4.7 × 10–10
5.5 × 10–10
1.0 × 10–11
1.4 × 10–11
2.7 × 10–10
4.3 × 10–10–10e(g)1 μm

Inhalation

1.6 × 10–11
2.4 × 10–11
2.5 × 10–11
6.4 × 10–11
9.6 × 10–11
1.0 × 10–10

8.8 × 10
4.8 × 10–9
7.3 × 10–10
1.2 × 10–9
1.2 × 10–9
7.9 × 10–9
2.6 × 10–12
4.6 × 10–12
6.6 × 10–10
7.4 × 10–10
1.6 × 10–11
2.0 × 10–11
4.3 × 10–10
6.0 × 10–10–10e(g)5 μm

0.010

0.010

0.800

0.800

0.800

0.800

0.800

0.800

0.800

f1

e(g)

8.9 × 10–11

1.7 × 10–11

7.8 × 10–10

3.0 × 10–11

1.4 × 10–9

5.1 × 10–12

2.2 × 10–9

1.5 × 10–9

1.5 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

187

22.0 h

94.0 d

6.00 h

15.4 d

13.0 h1.25 d

6.00 aOs‑185

Os‑189m

Os‑191

Os‑191m

Os‑193

Os‑194

Physicalhalf-life

Os‑182

Radionuclidea
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1
1.9 × 10
3.7 × 10–10
3.9 × 10–10
1.1 × 10–9
1.2 × 10–9
1.5 × 10–9
2.7 × 10–12
5.1 × 10–12
5.4 × 10–12
2.5 × 10–10
1.5 × 10–9
1.8 × 10–9
2.6 × 10–11
1.3 × 10–10
1.5 × 10–10
1.7 × 10–10
4.7 × 10–10
5.1 × 10–10
1.1 × 10–8
2.0 × 10–8
7.9 × 10–8

–10e(g)1 μm

Inhalation

3.2 × 10
5.0 × 10–10
5.2 × 10–10
1.4 × 10–9
1.0 × 10–9
1.1 × 10–9
5.2 × 10–12
7.6 × 10–12
7.9 × 10–12
3.5 × 10–10
1.3 × 10–9
1.5 × 10–9
4.1 × 10–11
1.3 × 10–10
1.4 × 10–10
2.8 × 10–10
6.4 × 10–10
6.8 × 10–10
1.3 × 10–8
1.3 × 10–8
4.2 × 10–8

–10e(g)5 μm

0.010

0.010

0.010

0.010

0.010

0.010

0.010

f1

e(g)

2.4 × 10–9

8.1 × 10–10

9.6 × 10–11

5.7 × 10–10

1.8 × 10–11

5.1 × 10–10

5.6 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

188

0.250 h3.02 h

14.0 h15.8 h

1.75 h10.5 h1.73 dIr‑184

Ir‑185

Ir‑186

Ir‑186m

Ir‑187

Ir‑188

Physicalhalf-life

Ir‑182

Iridium

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1
1.5 × 10–11
2.4 × 10–11
2.5 × 10–11
6.7 × 10–11
1.1 × 10–10
1.2 × 10–10
8.8 × 10–11
1.8 × 10–10
1.9 × 10–10
1.8 × 10–10
3.2 × 10–10
3.3 × 10–10
2.5 × 10–11
4.3 × 10–11
4.5 × 10–11
4.0 × 10–11
7.5 × 10–11
7.9 × 10–11
2.6 × 10–10
4.1 × 10–10
4.3 × 10–10e(g)1 μm

Inhalation

2.6 × 10–11
3.9 × 10–11
4.0 × 10–11
1.2 × 10–10
1.8 × 10–10
1.9 × 10–10
1.5 × 10–10
2.5 × 10–10
2.6 × 10–10
3.3 × 10–10
4.8 × 10–10
5.0 × 10–10
4.5 × 10–11
6.9 × 10–11
7.1 × 10–11
7.2 × 10–11
1.1 × 10–10
1.2 × 10–10
4.4 × 10–10
6.0 × 10–10
6.2 × 10–10

e(g)5 μm

0.010

0.010

0.010

0.010

0.010

0.010

0.010

f1

e(g)

6.3 × 10–10

1.2 × 10–10

6.1 × 10–11

4.9 × 10–10

2.6 × 10–10

1.7 × 10–10

4.8 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

189

13.3 d12.1 d

3.10 h1.20 h

74.0 d

2.41 × 102 a

11.9 dIr‑190Ir‑190m

Ir‑190mʹ

Ir‑192

Ir‑192m

Ir‑193m

Physicalhalf-life

Ir‑189Radionuclidea
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1
1.1 × 10
4.8 × 10–10
5.5 × 10–10
7.9 × 10–10
2.0 × 10–9
2.3 × 10–9
5.3 × 10–11
8.3 × 10–11
8.6 × 10–11
3.7 × 10–12
9.0 × 10–12
1.0 × 10–11
1.8 × 10–9
4.9 × 10–9
6.2 × 10–9
4.8 × 10–9
5.4 × 10–9
3.6 × 10–8
1.0 × 10–10
1.0 × 10–9
1.2 × 10–9–10e(g)1 μm

Inhalation

1.7 × 10
4.1 × 10–10
4.6 × 10–10
1.2 × 10–9
2.3 × 10–9
2.5 × 10–9
9.7 × 10–11
1.4 × 10–10
1.4 × 10–10
5.6 × 10–12
1.0 × 10–11
1.1 × 10–11
2.2 × 10–9
4.1 × 10–9
4.9 × 10–9
5.6 × 10–9
3.4 × 10–9
1.9 × 10–8
1.6 × 10–10
9.1 × 10–10
1.0 × 10–9–10e(g)5 μm

0.010

0.010

0.010

0.010

0.010

0.010

0.010

f1

e(g)

2.7 × 10–10

3.1 × 10–10

1.4 × 10–9

8.0 × 10–12

1.2 × 10–10

1.2 × 10–9

2.4 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

190

2.50 h3.80 hIr‑195

Ir‑195m

Pt‑186
Pt‑188Pt‑189Pt‑191
Pt‑193
Pt‑193m
Pt‑195m
Pt‑1972.00 h10.2 d10.9 h2.80 d50.0 a4.33 d
4.02 d18.3 h

171 d

Ir‑194m

Platinum19.1 hPhysicalhalf-life

Ir‑194

Radionuclidea

F
F
F
F
F
F
F
F

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1

3.6 × 10–11
4.3 × 10–10
4.1 × 10–11
1.1 × 10–10
2.1 × 10–11
1.3 × 10–10
1.9 × 10–10
9.1 × 10–11

2.2 × 10
5.3 × 10–10
5.6 × 10–10
5.4 × 10–9
8.5 × 10–9
1.2 × 10–8
2.6 × 10–11
6.7 × 10–11
7.2 × 10–11
6.5 × 10–11
1.6 × 10–10
1.7 × 10–10–10e(g)1 μm

Inhalation

6.6 × 10–11
6.3 × 10–10
7.3 × 10–11
1.9 × 10–10
2.7 × 10–11
2.1 × 10–10
3.1 × 10–10
1.6 × 10–10

3.6 × 10
7.1 × 10–10
7.5 × 10–10
6.5 × 10–9
6.5 × 10–9
8.2 × 10–9
4.5 × 10–11
9.6 × 10–11
1.0 × 10–10
1.1 × 10–10
2.3 × 10–10
2.4 × 10–10–10e(g)5 μm

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.010

0.010

0.010

0.010

f1

e(g)

9.3 × 10–11
7.6 × 10–10
1.2 × 10–10
3.4 × 10–10
3.1 × 10–11
4.5 × 10–10
6.3 × 10–10
4.0 × 10–10

2.1 × 10–10

1.0 × 10–10

2.1 × 10–9

1.3 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

191

17.6 h

1.64 d183 d2.69 d2.30 d

3.14 dAu‑194

Au‑195

Au‑198

Au‑198m

Au‑1991.57 h
0.513 h12.5 hPhysicalhalf-life

Au‑193Gold

Pt‑197m
Pt‑199Pt‑200Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
F
F

Type

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.010
0.010
0.010

f1

3.9 × 10–11
1.1 × 10–10
1.2 × 10–10
1.5 × 10–10
2.4 × 10–10
2.5 × 10–10
7.1 × 10–11
1.0 × 10–9
1.6 × 10–9
2.3 × 10–10
7.6 × 10–10
8.4 × 10–10
3.4 × 10–10
1.7 × 10–9
1.9 × 10–9
1.1 × 10–10
6.8 × 10–10
7.5 × 10–10

2.5 × 10
1.3 × 10–11
2.4 × 10–10–11e(g)1 μm

Inhalation

7.1 × 10–11
1.5 × 10–10
1.6 × 10–10
2.8 × 10–10
3.7 × 10–10
3.8 × 10–10
1.2 × 10–10
8.0 × 10–10
1.2 × 10–9
3.9 × 10–10
9.8 × 10–10
1.1 × 10–9
5.9 × 10–10
2.0 × 10–9
1.9 × 10–9
1.9 × 10–10
6.8 × 10–10
7.6 × 10–10

4.3 × 10
2.2 × 10–11
4.0 × 10–10–11e(g)5 μm

0.100

0.100

0.100

0.100

0.100

0.100

0.010
0.010
0.010

f1

e(g)

4.4 × 10–10

1.3 × 10–9

1.0 × 10–9

2.5 × 10–10

4.2 × 10–10

1.3 × 10–10

8.4 × 10–11
3.9 × 10–11
1.2 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

192

Hg‑193(organic)
Hg‑193(inorganic)
Hg‑193m(organic)
Hg‑193m(inorganic)
Hg‑194(organic)
Hg‑194(inorganic)F
M
F

11.1 h

2.60 × 102 a2.60 × 102 a
F
M

F
M
F

3.50 h11.1 hF0.440 hAu‑201

F
M
S
F
M
S
F
M
S

Type

3.50 h18.7 hAu‑200m

Mercury0.807 hPhysicalhalf-life

Au‑200Radionuclidea

0.020
0.020

0.020
0.020
0.400

0.020
0.020
0.400

0.400

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

2.3 × 10–10
3.8 × 10–10
1.9 × 10–8

1.2 × 10–10
2.6 × 10–10
1.5 × 10–8

1.5 × 10–8
5.3 × 10–9

5.0 × 10–11
1.0 × 10–10
2.0 × 10–10

2.8 × 10–11
7.5 × 10–11
1.1 × 10–10

1.3 × 10–8
7.8 × 10–9

4.7 × 10–11

3.0 × 10
5.3 × 10–11
5.6 × 10–11
5.7 × 10–10
9.8 × 10–10
1.0 × 10–9
1.6 × 10–11
2.8 × 10–11
2.9 × 10–11–11e(g)5 μm

2.6 × 10–11

1.7 × 10
3.5 × 10–11
3.6 × 10–11
3.2 × 10–10
6.9 × 10–10
7.3 × 10–10
9.2 × 10–12
1.7 × 10–11
1.8 × 10–11–11e(g)1 μm

Inhalation

1.000
0.400
0.020

1.000
0.400
0.020

1.000
0.400
0.020

0.100

0.100

0.100

f1

e(g)

5.1 × 10–8
2.1 × 10–8
1.4 × 10–9

1.3 × 10–10
3.0 × 10–10
4.0 × 10–10

3.1 × 10–11
6.6 × 10–11
8.2 × 10–11

2.4 × 10–11

1.1 × 10–9

6.8 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

193

Hg‑195(organic)
Hg‑195(inorganic)
Hg‑195m(organic)
Hg‑195m(inorganic)
Hg‑197(organic)
Hg‑197(inorganic)
Hg‑197m(organic)
Hg‑197m(inorganic)
Hg‑199m(organic)
Hg‑199m(inorganic)
Hg‑203(organic)

Radionuclidea

F
M
F
F
M
F
F
M
F

1.73 d2.67 d23.8 h

46.6 d0.710 h0.710 h23.8 h

2.67 d

F
M
F

F
M
F

9.90 h1.73 dFType9.90 hPhysicalhalf-life

0.020
0.020
0.400

0.020
0.020
0.400

0.020
0.020
0.400

0.020
0.020
0.400

0.020
0.020
0.400

0.400

f1

4.8 × 10–11
9.2 × 10–11
2.2 × 10–10
2.6 × 10–10
6.5 × 10–10
8.5 × 10–11
1.0 × 10–10
2.8 × 10–10
1.8 × 10–10
2.1 × 10–10
6.6 × 10–10
2.7 × 10–11
2.7 × 10–11
5.2 × 10–11
7.5 × 10–10

1.5 × 10–10
5.1 × 10–10
5.0 × 10–11
6.0 × 10–11
2.9 × 10–10
1.0 × 10–10
1.2 × 10–10
5.1 × 10–10
1.6 × 10–11
1.6 × 10–11
3.3 × 10–11
5.7 × 10–10

4.4 × 10

2.7 × 10–11
7.2 × 10–11
1.3 × 10–10

2.4 × 10–11e(g)5 μm

–11e(g)1 μm

Inhalation

1.000
0.400

1.000
0.400
0.020

1.000
0.400
0.020

1.000
0.400
0.020

1.000
0.400
0.020

1.000
0.400
0.020

f1

e(g)

1.9 × 10–9
1.1 × 10–9

2.8 × 10–11
3.1 × 10–11
3.1 × 10–11

1.5 × 10–10
3.4 × 10–10
4.7 × 10–10

9.9 × 10–11
1.7 × 10–10
2.3 × 10–10

2.2 × 10–10
4.1 × 10–10
5.6 × 10–10

3.4 × 10–11
7.5 × 10–11
9.7 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

194

Pb‑195m
Pb‑198
Pb‑199Pb‑200Pb‑201

Lead

Tl‑194Tl‑194m
Tl‑195
Tl‑197
Tl‑198Tl‑198m
Tl‑199Tl‑200Tl‑201
Tl‑202
Tl‑204

Thallium

Hg‑203(inorganic)

Radionuclidea

0.263 h2.40 h
1.50 h21.5 h
9.40 h

0.550 h0.546 h1.16 h2.84 h5.30 h
1.87 h
7.42 h1.09 d
3.04 d12.2 d3.78 a46.6 dPhysicalhalf-life

F
F
F
F
F

F
F
F
F
F
F
F
F
F
F
F

F
M

Type

0.200
0.200
0.200
0.200
0.200

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.020
0.020

f1

1.7 × 10–11
4.7 × 10–11
2.6 × 10–11
1.5 × 10–10
6.5 × 10–11

4.8 × 10–12
2.0 × 10–11
1.6 × 10–11
1.5 × 10–11
6.6 × 10–11
4.0 × 10–11
2.0 × 10–11
1.4 × 10–10
4.7 × 10–11
2.0 × 10–10
4.4 × 10–10

4.7 × 10
2.3 × 10–9–10e(g)1 μm

Inhalation

3.0 × 10–11
8.7 × 10–11
4.8 × 10–11
2.6 × 10–10
1.2 × 10–10

8.9 × 10–12
3.6 × 10–11
3.0 × 10–11
2.7 × 10–11
1.2 × 10–10
7.3 × 10–11
3.7 × 10–11
2.5 × 10–10
7.6 × 10–11
3.1 × 10–10
6.2 × 10–10

5.9 × 10
1.9 × 10–9–10e(g)5 μm

0.200
0.200
0.200
0.200
0.200

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.020

f1

e(g)

2.9 × 10–11
1.0 × 10–10
5.4 × 10–11
4.0 × 10–10
1.6 × 10–10

8.1 × 10–12
4.0 × 10–11
2.7 × 10–11
2.3 × 10–11
7.3 × 10–11
5.4 × 10–11
2.6 × 10–11
2.0 × 10–10
9.5 × 10–11
4.5 × 10–10
1.3 × 10–9

5.4 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

195

0.606 h1.80 h

1.67 h11.8 h15.3 d6.24 dBi‑201

Bi‑202

Bi‑203

Bi‑205

Bi‑2063.00 × 10 a3.62 h2.17 d1.43 × 107 a
3.25 h22.3 a0.601 h10.6 h
0.447 h5

Physicalhalf-life

Bi‑200

BismuthPb‑202
Pb‑202m
Pb‑203
Pb‑205
Pb‑209Pb‑210Pb‑211
Pb‑212
Pb‑214

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M

F
F
F
F
F
F
F
F
F

Type

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

f1

2.4 × 10–11
3.4 × 10–11
4.7 × 10–11
7.0 × 10–11
4.6 × 10–11
5.8 × 10–11
2.0 × 10–10
2.8 × 10–10
4.0 × 10–10
9.2 × 10–10
7.9 × 10–10
1.7 × 10–9

1.1 × 10
6.7 × 10–11
9.1 × 10–11
3.4 × 10–10
1.8 × 10–11
8.9 × 10–7
3.9 × 10–9
1.9 × 10–8
2.9 × 10–9–8e(g)1 μm

Inhalation

4.2 × 10–11
5.6 × 10–1
8.3 × 10–11
1.1 × 10–10
8.4 × 10–11
1.0 × 10–10
3.6 × 10–10
4.5 × 10–10
6.8 × 10–10
1.0 × 10–9
1.3 × 10–9
2.1 × 10–9

1.4 × 10
1.2 × 10–10
1.6 × 10–10
4.1 × 10–10
3.2 × 10–11
1.1 × 10–6
5.6 × 10–9
3.3 × 10–8
4.8 × 10–9–8e(g)5 μm

0.050

0.050

0.050

0.050

0.050

0.050

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

f1

e(g)

1.9 × 10–9

9.0 × 10–10

4.8 × 10–10

8.9 × 10–11

1.2 × 10–10

5.1 × 10–11

8.7 × 10–9
1.3 × 10–10
2.4 × 10–10
2.8 × 10–10
5.7 × 10–11
6.8 × 10–7
1.8 × 10–10
5.9 × 10–9
1.4 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

196

5.01 d3.00 × 106 a

1.01 h

0.761 h0.332 hBi‑210Bi‑210m

Bi‑212

Bi‑213

Bi‑2140.612 h1.80 h5.83 h138 d

Po‑203

Po‑205

Po‑207

Po‑210

Polonium38.0 aPhysicalhalf-life

Bi‑207

Radionuclidea

F
M
F
M
F
M
F
M

F
M
F
M
F
M
F
M
F
M
F
M

Type

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1

2.5 × 10–11
3.6 × 10–11
3.5 × 10–11
6.4 × 10–11
6.3 × 10–11
8.4 × 10–11
6.0 × 10–7
3.0 × 10–6

5.2 × 10
5.2 × 10–9
1.1 × 10–9
8.4 × 10–8
4.5 × 10–8
3.1 × 10–6
9.3 × 10–9
3.0 × 10–8
1.1 × 10–8
2.9 × 10–8
7.2 × 10–9
1.4 × 10–8

–10e(g)1 μm

Inhalation

4.5 × 10–11
6.1 × 10–11
6.0 × 10–11
8.9 × 10–11
1.2 × 10–10
1.5 × 10–10
7.1 × 10–7
2.2 × 10–6

8.4 × 10
3.2 × 10–9
1.4 × 10–9
6.0 × 10–8
5.3 × 10–8
2.1 × 10–6
1.5 × 10–8
3.9 × 10–8
1.8 × 10–8
4.1 × 10–8
1.2 × 10–8
2.1 × 10–8

–10e(g)5 μm

0.100

0.100

0.100

0.100

0.050

0.050

0.050

0.050

0.050

0.050

f1

e(g)

2.4 × 10–7

1.4 × 10–10

5.9 × 10–11

5.2 × 10–11

1.1 × 10–10

2.0 × 10–10

2.6 × 10–10

1.5 × 10–8

1.3 × 10–9

1.3 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

197

Ac‑224

ActiniumRa‑223
Ra‑224
Ra‑225
Ra‑226
Ra‑227
Ra‑228Radium

Fr‑222
Fr‑2232.90 h

11.4 d
3.66 d
14.8 d
1.60 × 103 a
0.703 h5.75 a0.240 h0.363 h7.21 hAt‑211

Francium1.80 hPhysicalhalf-life

At‑207

Astatine

Radionuclidea

F
M
S

M
M
M
M
M
M

F
F

F
M
F
M

Type

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.200
0.200
0.200
0.200
0.200
0.200

1.000
1.000

1.000
1.000
1.000
1.000

f1

1.1 × 10–8
1.0 × 10–7
1.2 × 10–7

6.9 × 10–6
2.9 × 10–6
5.8 × 10–6
3.2 × 10–6
2.8 × 10–10
2.6 × 10–6

1.4 × 10–8
9.1 × 10–10

3.5 × 10–10
2.1 × 10–9
1.6 × 10–8
9.8 × 10–8e(g)1 μm

Inhalation

1.3 × 10–8
8.9 × 10–8
9.9 × 10–8

5.7 × 10–6
2.4 × 10–6
4.8 × 10–6
2.2 × 10–6
2.1 × 10–10
1.7 × 10–6

2.1 × 10–8
1.3 × 10–9

4.4 × 10–10
1.9 × 10–9
2.7 × 10–8
1.1 × 10–7

e(g)5 μm

5.0 × 10–4

0.200
0.200
0.200
0.200
0.200
0.200

1.000
1.000

1.000

1.000

f1

e(g)

7.0 × 10–10

1.0 × 10–7
6.5 × 10–8
9.5 × 10–8
2.8 × 10–7
8.4 × 10–11
6.7 × 10–7

7.1 × 10–10
2.3 × 10–9

1.1 × 10–8

2.3 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

198

1.21 d21.8 a6.13 h

Ac‑226

Ac‑227

Ac‑2280.515 h18.7 d

1.91 a7.34 × 103 a

Th‑226

Th‑227

Th‑228

Th‑229

Thorium

10.0 dPhysicalhalf-life

Ac‑225

Radionuclidea

M
S
M
S
M
S
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type
–4

5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

5.5 × 10–8
5.9 × 10–8
7.8 × 10–6
9.6 × 10–6
3.1 × 10–5
3.9 × 10–5
9.9 × 10–5
6.5 × 10–5

8.7 × 10
6.9 × 10–6
7.9 × 10–6
9.5 × 10–8
1.1 × 10–6
1.2 × 10–6
5.4 × 10–4
2.1 × 10–4
6.6 × 10–5
2.5 × 10–8
1.6 × 10–8
1.4 × 10–8–7e(g)1 μm

Inhalation

7.4 × 10–8
7.8 × 10–8
6.2 × 10–6
7.6 × 10–6
2.3 × 10–5
3.2 × 10–5
6.9 × 10–5
4.8 × 10–5

1.0 × 10
5.7 × 10–6
6.5 × 10–6
2.2 × 10–7
9.2 × 10–7
1.0 × 10–6
6.3 × 10–4
1.5 × 10–4
4.7 × 10–5
2.9 × 10–8
1.2 × 10–8
1.2 × 10–8

–6e(g)5 μm

1.1 × 10–6

4.3 × 10–10

5.0 × 10–4

5.0 × 10–4

3.5 × 10–10
3.6 × 10–10
8.9 × 10–9
8.4 × 10–9
7.0 × 10–8
3.5 × 10–8
4.8 × 10–7
2.0 × 10–7

1.0 × 10–8

5.0 × 10–4

5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4

2.4 × 10–8

5.0 × 10

e(g)
–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

199

1.06 d

1.40 × 1010 a

24.1 dTh‑231

Th‑232

Th‑234

0.638 h22.0 h

17.4 d3.27 × 104 a

1.31 d

27.0 dPa‑227

Pa‑228

Pa‑230

Pa‑231

Pa‑232

Pa‑233

Protactinium

7.70 × 10 a4

Physicalhalf-life

Th‑230Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S

M
S
M
S
M
S
M
S

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 102.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4

f1

7.0 × 10–8
7.6 × 10–8
5.9 × 10–8
6.9 × 10–8
5.6 × 10–7
7.1 × 10–7
1.3 × 10–4
3.2 × 10–5
9.5 × 10–9
3.2 × 10–9
3.1 × 10–9
3.7 × 10–9

4.0 × 10
1.3 × 10–5
2.9 × 10–10
3.2 × 10–10
4.2 × 10–5
2.3 × 10–5
6.3 × 10–9
7.3 × 10–9–5e(g)1 μm

Inhalation

9.0 × 10–8
9.7 × 10–8
4.6 × 10–8
5.1 × 10–8
4.6 × 10–7
5.7 × 10–7
8.9 × 10–5
1.7 × 10–5
6.8 × 10–9
2.0 × 10–9
2.8 × 10–9
3.2 × 10–9

2.8 × 10
7.2 × 10–6
3.7 × 10–10
4.0 × 10–10
2.9 × 10–5
1.2 × 10–5
5.3 × 10–9
5.8 × 10–9–5

e(g)5 μm
–47.2 × 10–10
8.7 × 10–10

5.0 × 10–4
5.0 × 10–4

9.2 × 10–10

5.0 × 10–4

7.1 × 10–7

7.8 × 10–10

5.0 × 10–4

5.0 × 10–4

4.5 × 10–10

2.1 × 10–7
8.7 × 10–8
3.4 × 10–10
3.4 × 10–10
2.2 × 10–7
9.2 × 10–8
3.4 × 10–9
3.4 × 10–9e(g)5.0 × 10–4

5.0 × 102.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4
5.0 × 10–4
2.0 × 10–4

f1

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

200

20.8 d

4.20 d72.0 a1.58 × 105 a

2.44 × 105 a

7.04 × 108 a

U‑231

U‑232

U‑233

U‑234

U‑235

6.70 hPhysicalhalf-life

U‑230

Uranium

Pa‑234

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

M
S

Type
–4

0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002

5.0 × 10
5.0 × 10–4

f1

3.6 × 10–7
1.2 × 10–5
1.5 × 10–5
8.3 × 10–11
3.4 × 10–10
3.7 × 10–10
4.0 × 10–6
7.2 × 10–6
3.5 × 10–5
5.7 × 10–7
3.2 × 10–6
8.7 × 10–6
5.5 × 10–7
3.1 × 10–6
8.5 × 10–6
5.1 × 10–7
2.8 × 10–6
7.7 × 10–6

3.8 × 10
4.0 × 10–10–10e(g)1 μm

Inhalation

4.2 × 10–7
1.0 × 10–5
1.2 × 10–5
1.4 × 10–10
3.7 × 10–10
4.0 × 10–10
4.7 × 10–6
4.8 × 10–6
2.6 × 10–5
6.6 × 10–7
2.2 × 10–6
6.9 × 10–6
6.4 × 10–7
2.1 × 10–6
6.8 × 10–6
6.0 × 10–7
1.8 × 10–6
6.1 × 10–6

5.5 × 10
5.8 × 10–10–10e(g)5 μm
–4

0.020
0.002

0.020
0.002

0.020
0.002

0.020
0.002

0.020
0.002

0.020
0.002

5.0 × 10f1

e(g)4.6 × 10–8
8.3 × 10–9

4.9 × 10–8
8.3 × 10–9

5.0 × 10–8
8.5 × 10–9

3.3 × 10–7
3.7 × 10–8

2.8 × 10–10
2.8 × 10–10

5.5 × 10–8
2.8 × 10–8

5.1 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

201

4.47 × 109 a

0.392 h14.1 h

U‑238

U‑239

U‑240

Np‑232
Np‑233
Np‑234
Np‑235
Np‑236

0.245 h0.603 h4.40 d1.08 a1.15 × 105 a6.75 dU‑237

Neptunium

2.34 × 10 a

7

Physicalhalf-life

U‑236Radionuclidea

M
M
M
M
M

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002

f1

4.7 × 10–11
1.7 × 10–12
5.4 × 10–10
4.0 × 10–10
3.0 × 10–6

5.2 × 10
2.9 × 10–6
7.9 × 10–6
1.9 × 10–10
1.6 × 10–9
1.8 × 10–9
4.9 × 10–7
2.6 × 10–6
7.3 × 10–6
1.1 × 10–11
2.3 × 10–11
2.4 × 10–11
2.1 × 10–10
5.3 × 10–10
5.7 × 10–10–7e(g)1 μm

Inhalation

3.5 × 10–11
3.0 × 10–12
7.3 × 10–10
2.7 × 10–10
2.0 × 10–6

6.1 × 10
1.9 × 10–6
6.3 × 10–6
3.3 × 10–10
1.5 × 10–9
1.7 × 10–9
5.8 × 10–7
1.6 × 10–6
5.7 × 10–6
1.8 × 10–11
3.3 × 10–11
3.5 × 10–11
3.7 × 10–10
7.9 × 10–10
8.4 × 10–10–7e(g)5 μm

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.020
0.002

0.020
0.002

0.020
0.002

0.020
0.002

0.020
0.002

f1

e(g)

9.7 × 10–12
2.2 × 10–12
8.1 × 10–10
5.3 × 10–11
1.7 × 10–8

1.1 × 10–9
1.1 × 10–9

2.7 × 10–11
2.8 × 10–11

4.4 × 10–8
7.6 × 10–9

7.6 × 10–10
7.7 × 10–10

4.6 × 10–8
7.9 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

202

8.80 h

0.422 h2.85 a45.3 d87.7 aPu‑235

Pu‑236

Pu‑237

Pu‑23822.5 h2.14 × 106 a
2.12 d2.36 d1.08 hPhysicalhalf-life

Pu‑234

Plutonium

Np‑236m
Np‑237
Np‑238
Np‑239Np‑240Radionuclidea

M
S

M
S

M
S

M
S

M
S

M
M
M
M
M

Type
–4

1.9 × 10–8
2.2 × 10–8
1.5 × 10–12
1.6 × 10–12
1.8 × 10–5
9.6 × 10–6
3.3 × 10–10
3.6 × 10–10
4.3 × 10–5
1.5 × 10–5

5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
1.0 × 10–5

5.0 × 10
2.1 × 10–5
2.0 × 10–9
9.0 × 10–10
8.7 × 10–11–9e(g)1 μm

5.0 × 10–4
1.0 × 10–5

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

Inhalation

3.0 × 10–5
1.1 × 10–5

2.9 × 10–10
3.0 × 10–10

1.3 × 10–5
7.4 × 10–6

2.5 × 10–12
2.6 × 10–12

1.6 × 10–8
1.8 × 10–8

3.6 × 10
1.5 × 10–5
1.7 × 10–9
1.1 × 10–9
1.3 × 10–10–9e(g)5 μm
–45.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

e(g)

1.6 × 10–10
1.5 × 10–10
1.6 × 10–10
2.1 × 10–12
2.1 × 10–12
2.1 × 10–12
8.6 × 10–8
6.3 × 10–9
2.1 × 10–8
1.0 × 10–10
1.0 × 10–10
1.0 × 10–10
2.3 × 10–7
8.8 × 10–9
4.9 × 10–8

1.9 × 10–10
1.1 × 10–7
9.1 × 10–10
8.0 × 10–10
8.2 × 10–11

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

203

M
S
M
S
M
S
M
S
M
S

6.54 × 103 a

14.4 a3.76 × 105 a4.95 h8.26 × 107 a

10.5 hPu‑240Pu‑241

Pu‑242

Pu‑243

Pu‑244Pu‑245

M
S

M
S

Type

2.41 × 10 a4

Physicalhalf-life

Pu‑239Radionuclidea–4

4.4 × 10–5
1.3 × 10–5
4.5 × 10–10
4.8 × 10–10

5.0 × 10–4
1.0 × 10–5

8.2 × 10–11
8.5 × 10–11

5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
1.0 × 10–5

4.4 × 10–5
1.4 × 10–5

8.5 × 10–7
1.6 × 10–7

5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
1.0 × 10–5

4.7 × 10–5
1.5 × 10–5

4.7 × 10
1.5 × 10–5–5e(g)1 μm

5.0 × 10–4
1.0 × 10–5

5.0 × 10
1.0 × 10–5

f1

Inhalation

6.1 × 10–10
6.5 × 10–10

3.0 × 10–5
7.4 × 10–6

1.1 × 10–10
1.1 × 10–10

3.1 × 10–5
7.7 × 10–6

5.8 × 10–7
8.4 × 10–8

3.2 × 10–5
8.3 × 10–6

3.2 × 10
8.3 × 10–6

–5

e(g)5 μm
–45.0 × 10
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4
5.0 × 10–4
1.0 × 10–5
1.0 × 10–4

f1

e(g)
2.5 × 10–7
9.0 × 10–9
5.3 × 10–8
2.5 × 10–7
9.0 × 10–9
5.3 × 10–8
4.7 × 10–9
1.1 × 10–10
9.6 × 10–10
2.4 × 10–7
8.6 × 10–9
5.0 × 10–8
8.5 × 10–11
8.5 × 10–11
8.5 × 10–11
2.4 × 10–7
1.1 × 10–8
5.2 × 10–8
7.2 × 10–10
7.2 × 10–10
7.2 × 10–10

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)204

Cm‑238
Cm‑240CuriumAm‑237
Am‑238
Am‑239Am‑240Am‑241
Am‑242
Am‑242m
Am‑243
Am‑244
Am‑244m
Am‑245
Am‑246
Am‑246m

AmericiumPu‑246

Radionuclidea

2.40 h
27.0 d

1.22 h
1.63 h11.9 h2.12 d
4.32 × 102 a
16.0 h1.52 × 102 a
7.38 × 103 a
10.1 h
0.433 h2.05 h
0.650 h0.417 h10.9 dPhysicalhalf-life

M
M

M
M
M
M
M
M
M
M
M
M
M
M
M

M
S

Type
–4

5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
1.0 × 10–5

f1

4.1 × 10–9
2.9 × 10–6

2.5 × 10–11
8.5 × 10–11
2.2 × 10–10
4.4 × 10–10
3.9 × 10–5
1.6 × 10–8
3.5 × 10–5
3.9 × 10–5
1.9 × 10–9
7.9 × 10–11
5.3 × 10–11
6.8 × 10–11
2.3 × 10–11

7.0 × 10
7.6 × 10–9–9e(g)1 μm

Inhalation

4.8 × 10–9
2.3 × 10–6

3.6 × 10–11
6.6 × 10–11
2.9 × 10–10
5.9 × 10–10
2.7 × 10–5
1.2 × 10–8
2.4 × 10–5
2.7 × 10–5
1.5 × 10–9
6.2 × 10–11
7.6 × 10–11
1.1 × 10–10
3.8 × 10–11

6.5 × 10
7.0 × 10–9–9e(g)5 μm
–45.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
1.0 × 10–5
1.0 × 10–4

f1

e(g)

8.0 × 10–11
7.6 × 10–9

1.8 × 10–11
3.2 × 10–11
2.4 × 10–10
5.8 × 10–10
2.0 × 10–7
3.0 × 10–10
1.9 × 10–7
2.0 × 10–7
4.6 × 10–10
2.9 × 10–11
6.2 × 10–11
5.8 × 10–11
3.4 × 10–11

3.3 × 10–9
3.3 × 10–9
3.3 × 10–9

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

205

Cf‑244
Cf‑246
Cf‑248

Californium

Bk‑245
Bk‑246
Bk‑247
Bk‑249
Bk‑250Berkelium

Cm‑241
Cm‑242
Cm‑243
Cm‑244
Cm‑245
Cm‑246
Cm‑247
Cm‑248
Cm‑249Cm‑250Radionuclidea

0.323 h1.49 d334 d4.94 d1.83 d1.38 × 103 a
320 d3.22 h32.8 d163 d28.5 a18.1 a8.50 × 103 a4.73 × 103 a
1.56 × 107 a
3.39 × 105 a
1.07 h
6.90 × 103 a

Physicalhalf-life

M
M
M

M
M
M
M
M

M
M
M
M
M
M
M
M
M
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

1.3 × 10–8
4.2 × 10–7
8.2 × 10–6

2.0 × 10–9
3.4 × 10–10
6.5 × 10–5
1.5 × 10–7
9.6 × 10–10

3.4 × 10
4.8 × 10–6
2.9 × 10–5
2.5 × 10–5
4.0 × 10–5
4.0 × 10–5
3.6 × 10–5
1.4 × 10–4
3.2 × 10–11
7.9 × 10–4

–8e(g)1 μm

Inhalation

1.8 × 10–8
3.5 × 10–7
6.1 × 10–6

1.8 × 10–9
4.6 × 10–10
4.5 × 10–5
1.0 × 10–7
7.1 × 10–10

2.6 × 10
3.7 × 10–6
2.0 × 10–5
1.7 × 10–5
2.7 × 10–5
2.7 × 10–5
2.5 × 10–5
9.5 × 10–5
5.1 × 10–11
5.4 × 10–4

–8e(g)5 μm
–45.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

e(g)

7.0 × 10–11
3.3 × 10–9
2.8 × 10–8

5.7 × 10–10
4.8 × 10–10
3.5 × 10–7
9.7 × 10–10
1.4 × 10–10

9.1 × 10–10
1.2 × 10–8
1.5 × 10–7
1.2 × 10–7
2.1 × 10–7
2.1 × 10–7
1.9 × 10–7
7.7 × 10–7
3.1 × 10–11
4.4 × 10–6

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

206

Fm‑252
Fm‑253
Fm‑254
Fm‑255
Fm‑257

Fermium

Es‑250Es‑251
Es‑253
Es‑254
Es‑254m

Einsteinium

Cf‑249Cf‑250
Cf‑251
Cf‑252
Cf‑253
Cf‑254

Radionuclidea

22.7 h3.00 d3.24 h20.1 h101 d2.10 h1.38 d20.5 d276 d1.64 d3.50 × 10 a13.1 a8.98 × 102 a2.64 a17.8 d60.5 d2

Physicalhalf-life

M
M
M
M
M

M
M
M
M
M

M
M
M
M
M
M

Type
–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

3.0 × 10–7
3.7 × 10–7
5.6 × 10–8
2.5 × 10–7
6.6 × 10–6

5.9 × 10–10
2.0 × 10–9
2.5 × 10–6
8.0 × 10–6
4.4 × 10–7

6.6 × 10
3.2 × 10–5
6.7 × 10–5
1.8 × 10–5
1.2 × 10–6
3.7 × 10–5–5e(g)1 μm

Inhalation

2.6 × 10–7
3.0 × 10–7
7.7 × 10–8
2.6 × 10–7
5.2 × 10–6

4.2 × 10–10
1.7 × 10–9
2.1 × 10–6
6.0 × 10–6
3.7 × 10–7

4.5 × 10
2.2 × 10–5
4.6 × 10–5
1.3 × 10–5
1.0 × 10–6
2.2 × 10–5

–5e(g)5 μm
–45.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1

e(g)

2.7 × 10–9
9.1 × 10–10
4.4 × 10–10
2.5 × 10–9
1.5 × 10–8

2.1 × 10–11
1.7 × 10–10
6.1 × 10–9
2.8 × 10–8
4.2 × 10–9

3.5 × 10–7
1.6 × 10–7
3.6 × 10–7
9.0 × 10–8
1.4 × 10–9
4.0 × 10–7

Ingestion

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

207

5.20 h
55.0 dPhysicalhalf-life

M
M

Type
5.0 × 10–4
5.0 × 10–4

f1
2.3 × 10–8
5.5 × 10–6

e(g)1 μm

Inhalation

2.0 × 10–8
4.4 × 10–6

e(g)5 μm
5.0 × 10–4
5.0 × 10–4

f1

e(g)
1.2 × 10–10
1.3 × 10–8

Ingestionm and mʹ denote metastable states of the radionuclide. The metastable state mʹ is of higher energy than the metastable state m.
Note: Types F, M and S denote fast, moderate and slow absorption from the lung, respectively. f1: gut transfer factor; e(g): effective dose per unit
intake by age group.

a

Md‑257
Md‑258Mendelevium

Radionuclidea

TABLE III.2A. WORKERS: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA INHALATION ANDINGESTION (Sv/Bq) (cont.)

TABLE III.2B. COMPOUNDS AND VALUES OF GUT TRANSFER FACTOR
f1 USED TO CALCULATE COMMITTED EFFECTIVE DOSE PER UNITINTAKE VIA INGESTION FOR WORKERS (cont.)
Element

Gut transfer factor f1

Compounds

Hydrogen

1.000
1.000

Tritiated water (ingested)
Organically bound tritium

Beryllium

0.005

All compounds

Carbon1.000

Labelled organic compounds

Fluorine

1.000

All compounds

Sodium1.000

All compounds

Magnesium

0.500

All compounds

Aluminium

0.010

All compounds

Silicon0.010

All compounds

Phosphorus

0.800

All compounds

Sulphur

0.800
0.100
1.000

Inorganic compounds
Elemental sulphur
Organic sulphur

Chlorine

1.000

All compounds

Potassium

1.000

All compounds

Calcium

0.300

All compounds–4

Scandium

1.0 × 10

Titanium

0.010

All compounds

Vanadium

0.010

All compounds

Chromium

0.100
0.010

Hexavalent compounds
Trivalent compounds

Manganese

0.100

All compounds

Iron

0.100

All compounds

Cobalt

0.100
0.050

All unspecified compounds
Oxides, hydroxides andinorganic compounds

Nickel0.050

All compounds

Copper0.500

All compounds

208

All compounds

TABLE III.2B. COMPOUNDS AND VALUES OF GUT TRANSFER FACTOR
f1 USED TO CALCULATE COMMITTED EFFECTIVE DOSE PER UNITINTAKE VIA INGESTION FOR WORKERS (cont.)
Element

Gut transfer factor f1

Compounds

Zinc

0.500

All compounds

Gallium0.001

All compounds

Germanium

1.000

All compounds

Arsenic

0.500

All compounds

Selenium

0.800
0.050

All unspecified compounds
Elemental selenium and selenides

Bromine1.000

All compounds

Rubidium

1.000

All compounds

Strontium

0.300
0.010

All unspecified compounds
Strontium titanate (SrTiO3)

Yttrium

1.0 × 10–4

All compounds

Zirconium

0.002

All compounds

Niobium

0.010

All compounds

Molybdenum

0.800
0.050

All unspecified compounds
Molybdenum sulphideTechnetium

0.800

All compounds

Ruthenium

0.050

All compounds

Rhodium

0.050

All compounds

Palladium0.005

All compounds

Silver0.050

All compounds

Cadmium

0.050

All inorganic compounds

Indium0.020

All compounds

Tin

0.020

All compounds

Antimony

0.100

All compounds

Tellurium

0.300

All compounds

Iodine1.000

All compounds

Caesium

1.000

All compounds

209

TABLE III.2B. COMPOUNDS AND VALUES OF GUT TRANSFER FACTOR
f1 USED TO CALCULATE COMMITTED EFFECTIVE DOSE PER UNITINTAKE VIA INGESTION FOR WORKERS (cont.)
Element

Gut transfer factor f1

Barium0.100

Compounds
All compounds

5.0 × 10–4

All compounds

Cerium

5.0 × 10

–4All compounds

Praseodymium

5.0 × 10–4

All compounds

5.0 × 10

–4All compounds

Promethium

5.0 × 10

–4All compounds

Samarium

5.0 × 10–4

All compounds

Europium

5.0 × 10

–4All compounds

Gadolinium

5.0 × 10–4

All compounds

Terbium

5.0 × 10–4

All compounds

Dysprosium

5.0 × 10

–4All compounds

Holmium

5.0 × 10–4

All compounds

Erbium

5.0 × 10

–4All compounds

Thulium

5.0 × 10–4

All compounds

Ytterbium

5.0 × 10–4

All compounds

Lutetium

5.0 × 10

–4All compounds

Hafnium

0.002

All compounds

Tantalum

0.001

All compounds

Tungsten

0.300
0.010

All unspecified compounds
Tungstic acid

Rhenium

0.800

All compounds

Osmium0.010

All compounds

Iridium

0.010

All compounds

Platinum

0.010

All compounds

Gold

0.100

All compounds

Mercury0.020

All inorganic compounds

Lanthanum

Neodymium210

TABLE III.2B. COMPOUNDS AND VALUES OF GUT TRANSFER FACTOR
f1 USED TO CALCULATE COMMITTED EFFECTIVE DOSE PER UNITINTAKE VIA INGESTION FOR WORKERS (cont.)
Element

Gut transfer factor f1

Mercury

1.000

Methyl mercury

0.400

All unspecified
organic compounds

Thallium

1.000

All compounds

Lead

0.200

All compounds

Bismuth0.050

All compounds

Polonium

0.100

All compounds

Astatine

1.000

All compounds

Francium

1.000

All compounds

Radium

0.200

Actinium

5.0 × 10

Compounds

All compounds–4

All compounds–4

Thorium

5.0 × 102.0 × 10–4

All unspecified compounds
Oxides and hydroxides

Protactinium

5.0 × 10–4

All compounds

Uranium

0.020
0.002

Neptunium

5.0 × 10–4

All compounds

Plutonium

5.0 × 10–4
1.0 × 10–4
1.0 × 10–5

All unspecified compounds
Nitrates
Insoluble oxides

Americium

5.0 × 10–4

All compounds

Curium

5.0 × 10

–4All compounds

Berkelium

5.0 × 10–4

All compounds

Californium

5.0 × 10

–4All compounds

Einsteinium

5.0 × 10–4

All compounds

Fermium

5.0 × 10–4

All compounds–4

All compounds

Mendelevium

5.0 × 10

All unspecified compounds
Most tetravalent compounds,
e.g. UO2, U3O8, UF4

211

212

Absorption
type(s)

M
S

F
M
S

F

F
M

F
M

F
M
S

F
M

Element

Beryllium

Fluorine

SodiumMagnesium

Aluminium

SiliconPhosphorus

0.800
0.800

0.010
0.010
0.010

0.010
0.010

0.500
0.500

1.000

1.000
1.000
1.000

0.005
0.005

Gut transfer
factor f1

All unspecified compounds
Some phosphates: determined by combining cation

All unspecified compounds
Oxides, hydroxides, carbides and nitrates
Aluminosilicate glass aerosol

All unspecified compounds
Oxides, hydroxides, carbides, halides, nitrates and metallic aluminium

All unspecified compounds
Oxides, hydroxides, carbides, halides and nitrates

All compounds

Determined by combining cation
Determined by combining cation
Determined by combining cation

All unspecified compounds
Oxides, halides and nitrates

Compounds

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

213

Absorption
type(s)

F
M

F
M

F

M

S

F
M
S

F
M

F
M
S

Element

Sulphur

Chlorine

Potassium

Calcium

Scandium

Titanium

Vanadium

Chromium

0.100
0.100
0.100

0.010
0.010

All unspecified compounds
Halides and nitrates
Oxides and hydroxides

All unspecified compounds
Oxides, hydroxides, carbides and halides

All unspecified compounds
Oxides, hydroxides, carbides, halides and nitrates
Strontium titanate (SrTiO3)

All compounds

1.0 × 10–4
0.010
0.010
0.010

All compounds

All compounds

Determined by combining cation
Determined by combining cation

Sulphides and sulphates: determined by combining cation
Elemental sulphur; Sulphides and sulphates: determined by combining cation

Compounds

0.300

1.000

1.000
1.000

0.800
0.800

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

214

F
M

F
M

M
S

F
M

F
M
S

S

F
M

F
M

Iron

CobaltNickelCopperZinc

Gallium

Germanium

Absorption
type(s)Manganese

Element

1.000
1.000

0.001
0.001

0.500

0.500
0.500
0.500

0.050
0.050

0.100
0.050

0.100
0.100

0.100
0.100

Gut transfer
factor f1

All unspecified compounds
Oxides, sulphides and halides

All unspecified compounds
Oxides, hydroxides, carbides, halides and nitrates

All compounds

All unspecified inorganic compounds
Sulphides, halides and nitrates
Oxides and hydroxides

All unspecified compounds
Oxides, hydroxides and carbides

All unspecified compounds
Oxides, hydroxides, halides and nitrates

All unspecified compounds
Oxides, hydroxides and halides

All unspecified compounds
Oxides, hydroxides, halides and nitrates

Compounds

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

215

Absorption
type(s)

M

F
M

F
M

F

F
S

M
S

F
M
S

M
S

Element

Arsenic

Selenium

BromineRubidium

Strontium

Yttrium

Zirconium

Niobium

0.010
0.010

All unspecified compounds
Oxides and hydroxides

All unspecified compounds
Oxides, hydroxides, halides and nitrates
Zirconium carbide

All unspecified compounds
Oxides and hydroxides

1.0 × 10–4
1.0 × 10–4
0.002
0.002
0.002

All unspecified compounds
Strontium titanate (SrTiO3)

All compounds

Determined by combining cation
Determined by combining cation

All unspecified inorganic compounds
Elemental selenium, oxides, hydroxides and carbides

All compounds

Compounds

0.300
0.010

1.000

1.000
1.000

0.800
0.800

0.500

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

216

F
S

F
M

F
M
S

F
M
S

F
M
S

F
M
S

Technetium

Ruthenium

Rhodium

Palladium

Silver

Absorption
type(s)Molybdenum

Element

0.050
0.050
0.050

0.005
0.005
0.005

All unspecified compounds and metallic silver
Nitrates and sulphides
Oxides, hydroxides and carbides

All unspecified compounds
Nitrates and halides
Oxides and hydroxides

All unspecified compounds
Halides
Oxides and hydroxides

All unspecified compounds
Halides
Oxides and hydroxides

0.050
0.050
0.050
0.050
0.050
0.050

All unspecified compounds
Oxides, hydroxides, halides and nitrates

All unspecified compounds
Molybdenum sulphide, oxides and hydroxides

Compounds

0.800
0.800

0.800
0.050

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

217

Absorption
type(s)

F
M
S

F
M

F
M

F
M

F
M

F

F

F

Element

Cadmium

IndiumTin

Antimony

Tellurium

IodineCaesium

Barium

0.100

1.000

1.000

0.300
0.300

0.100
0.010

0.020
0.020

0.020
0.020

0.050
0.050
0.050

Gut transfer
factor f1

All compounds

All compounds

All compounds

All unspecified compounds
Oxides, hydroxides and nitrates

All unspecified compounds
Oxides, hydroxides, halides, sulphides, sulphates and nitrates

All unspecified compounds
Stannic phosphate, sulphides, oxides, hydroxides, halides and nitrates

All unspecified compounds
Oxides, hydroxides, halides and nitrates

All unspecified compounds
Sulphides, halides and nitrates
Oxides and hydroxides

Compounds

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

218

F
M

M
S

M
S

M
S

M
S

M

M

F
M

M

CeriumPraseodymium

Neodymium

Promethium

Samarium

Europium

Gadolinium

Terbium

Absorption
type(s)Lanthanum

Element

Compounds
All unspecified compounds
Oxides and hydroxides
All unspecified compounds
Oxides, hydroxides and fluorides
All unspecified compounds
Oxides, hydroxides, carbides and fluorides
All unspecified compounds
Oxides, hydroxides, carbides and fluorides
All unspecified compounds
Oxides, hydroxides, carbides and fluorides
All compounds
All compounds
All unspecified compounds
Oxides, hydroxides and fluorides
All compounds

Gut transfer
factor f1
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

219

M

M

M

M

M
S

M
S

F
M

M
S

F

Holmium

ErbiumThulium

Ytterbium

Lutetium

Hafnium

Tantalum

TungstenAbsorption
type(s)Dysprosium

Element

All unspecified compounds
All compounds
All compounds
All unspecified compounds
Oxides, hydroxides and fluorides
All unspecified compounds
Oxides, hydroxides and fluorides

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.300

0.001
0.001

All compounds

All unspecified compounds
Elemental tantalum, oxides, hydroxides, halides, carbides, nitrates and nitrides

All unspecified compounds
Oxides, hydroxides, halides, carbides and nitrates

All compounds

5.0 × 10–4

0.002
0.002

Compounds

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

220

Absorption
type(s)

F
M

F
M
S

F
M
S

F

F
M
S

F
M

F

F

Element

Rhenium

OsmiumIridium

PlatinumGold

Mercury

Mercury

Thallium

1.000

0.400

0.020
0.020

0.100
0.100
0.100

0.010

0.010
0.010
0.010

0.010
0.010
0.010

0.800
0.800

Gut transfer
factor f1

All compounds

All organic compounds

Sulphates
Oxides, hydroxides, halides, nitrates and sulphides

All unspecified compounds
Halides and nitrates
Oxides and hydroxides

All compounds

All unspecified compounds
Metallic iridium, halides and nitrates
Oxides and hydroxides

All unspecified compounds
Halides and nitrates
Oxides and hydroxides

All unspecified compounds
Oxides, hydroxides, halides and nitrates

Compounds

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

221

F

F
M

F
M

F
M

F

M

F
M
S

M
S

BismuthPolonium

Astatine

Francium

RadiumActinium

Thorium

Absorption
type(s)Lead

Element

All unspecified compounds
Halides and nitrates
Oxides and hydroxides
All unspecified compounds
Oxides and hydroxides

5.0 × 10–4
2.0 × 10–4

All compounds

All compounds

Determined by combining cation
Determined by combining cation

All unspecified compounds
Oxides, hydroxides and nitrates

Bismuth nitrate
All unspecified compounds

All compounds

Compounds

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.200

1.000

1.000
1.000

0.100
0.100

0.050
0.050

0.200

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

222

M
S

F
M
S

M

M
S

M

M

M

M

M

Uranium

Neptunium

Plutonium

Americium

CuriumBerkelium

Californium

Einsteinium

Absorption
type(s)Protactinium

Element

All compounds
All unspecified compounds
Insoluble oxides
All compounds
All compounds
All compounds
All compounds
All compounds

5.0 × 10–4
5.0 × 10–4
1.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

Most hexavalent compounds, e.g. UF6, UO2F2 and UO2(NO3)2
Less soluble compounds, e.g. UO3, UF4, UCl4 and most other hexavalent compounds
Highly insoluble compounds, e.g. UO2 and U3O8

All unspecified compounds
Oxides and hydroxides

5.0 × 10–4
5.0 × 10–4
0.020
0.020
0.002

Compounds

Gut transfer
factor f1

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

223

M

M

Fermium

Mendelevium

Compounds
All compounds
All compounds

Gut transfer
factor f1
5.0 × 10–4
5.0 × 10–4

Note: Types F, M and S denote fast, moderate and slow absorption from the lung, respectively.

Absorption
type(s)Element

TABLE III.2C. COMPOUNDS, LUNG ABSORPTION TYPES AND VALUES OF GUT TRANSFER FACTOR f1 USEDTO CALCULATE COMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATION FOR WORKERS (cont.)

224

Na‑22
Na‑24

SodiumF‑18

Fluorine

C‑11
C‑14

CarbonBe‑7Be-10Beryllium

Tritiatedwater
Organicallybound tritium

HydrogenRadionuclidea

2.60 a15.0 h1.83 h0.340 h5.73 × 103 a

1.000
1.000

1.000

1.000
1.000

0.020
0.020

1.000

12.3 a53.3 d
1.60 × 106 a

1.000

f1

2.1 × 10–8
3.5 × 10–9

5.2 × 10–10

2.6 × 10–10
1.4 × 10–9

1.000
1.000

1.000

1.000
1.000

0.005
0.005

1.000

1.2 × 10–10

1.8 × 10–10
1.4 × 10–8

1.000

e(g)

f1 forg>1a

6.4 × 10–11

Age ≤ 1 a

12.3 aPhysicalhalf-life

1.5 × 10–8
2.3 × 10–9

3.0 × 10–10

1.5 × 10–10
1.6 × 10–9

1.3 × 10–10
8.0 × 10–9

1.2 × 10–10

4.8 × 10–11e(g)Age 1–2 a

8.4 × 10–9
1.2 × 10–9

1.5 × 10–10

7.3 × 10–11
9.9 × 10–10

7.7 × 10–11
4.1 × 10–9

7.3 × 10–11

3.1 × 10–11

e(g)

2–7 a

5.5 × 10–9
7.7 × 10–10

9.1 × 10–11

4.3 × 10–11
8.0 × 10–10

5.3 × 10–11
2.4 × 10–9

5.7 × 10–11

2.3 × 10–11

e(g)7–12 a3.7 × 10–9
5.2 × 10–10

6.2 × 10–11

3.0 × 10–11
5.7 × 10–10

3.5 × 10–11
1.4 × 10–9

4.2 × 10–11

1.8 × 10–11

e(g)12–17 a3.2 × 10–9
4.3 × 10–10

4.9 × 10–11

2.4 × 10–11
5.8 × 10–10

2.8 × 10–11
1.1 × 10–9

4.2 × 10–11

1.8 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

225

S‑35
(inorganic)
S‑35(organic)

Sulphur

P‑32
P‑33

Phosphorus

Si‑31
Si‑32

Silicon

Al‑26

Aluminium

Mg‑28

Magnesium

Radionuclidea

1.000

1.000

87.4 d

1.000
1.000

0.020
0.020

0.020

1.000

f1

e(g)

1.000
1.000

7.7 × 10–9

0.800
0.800

0.010
0.010

0.010

0.500

f1 forg>1a

1.3 × 10–9

3.1 × 10–8
2.7 × 10–9

1.9 × 10–9
7.3 × 10–9

3.4 × 10–8

1.2 × 10–8

Age ≤ 1 a87.4 d

14.3 d25.4 d2.62 h
4.50 × 102 a

7.16 × 105 a

20.9 hPhysicalhalf-life

5.4 × 10–9

8.7 × 10–10

1.9 × 10–8
1.8 × 10–9

1.0 × 10–9
4.1 × 10–9

2.1 × 10–8

1.4 × 10–8e(g)Age 1–2 a

2.7 × 10–9

4.4 × 10–10

9.4 × 10–9
9.1 × 10–10

5.1 × 10–10
2.0 × 10–9

1.1 × 10–8

7.4 × 10–9

e(g)

2–7 a

1.6 × 10–9

2.7 × 10–10

5.3 × 10–9
5.3 × 10–10

3.0 × 10–10
1.2 × 10–9

7.1 × 10–9

4.5 × 10–9e(g)7–12 a9.5 × 10–10

1.6 × 10–10

3.1 × 10–9
3.1 × 10–10

1.8 × 10–10
7.0 × 10–10

4.3 × 10–9

2.7 × 10–9e(g)12–17 a7.7 × 10–10

1.3 × 10–10

2.4 × 10–9
2.4 × 10–10

1.6 × 10–10
5.6 × 10–10

3.5 × 10–9

2.2 × 10–9

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

226

Sc‑43
Sc‑44
Sc‑44mScandium

Ca‑41
Ca‑45
Ca‑47

Calciumb

K‑40
K‑42
K‑43
K‑44
K‑45

Potassium

Cl‑36
Cl‑38
Cl‑39

Chlorine

Radionuclidea

3.89 h
3.93 h
2.44 d

1.40 × 105 a
163 d4.53 d

1.28 × 109 a
12.4 h22.6 h
0.369 h0.333 h3.01 × 105 a
0.620 h0.927 hPhysicalhalf-life

0.001
0.001
0.001

0.600
0.600
0.600

1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000

f1

e(g)

1.8 × 10–9
3.5 × 10–9
2.4 × 10–8

1.2 × 10–9
1.1 × 10–8
1.3 × 10–8

6.2 × 10–8
5.1 × 10–9
2.3 × 10–9
1.0 × 10–9
6.2 × 10–10

9.8 × 10–9
1.4 × 10–9
9.7 × 10–10

Age ≤ 1 a

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.300
0.300

1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000

f1 forg>1a

1.2 × 10–9
2.2 × 10–9
1.6 × 10–8

5.2 × 10–10
4.9 × 10–9
9.3 × 10–9

4.2 × 10–8
3.0 × 10–9
1.4 × 10–9
5.5 × 10–10
3.5 × 10–10

6.3 × 10–9
7.7 × 10–10
5.5 × 10–10e(g)Age 1–2 a

6.1 × 10–10
1.2 × 10–9
8.3 × 10–9

3.9 × 10–10
2.6 × 10–9
4.9 × 10–9

2.1 × 10–8
1.5 × 10–9
7.6 × 10–10
2.7 × 10–10
1.7 × 10–10

3.2 × 10–9
3.8 × 10–10
2.7 × 10–10

e(g)

2–7 a

3.7 × 10–10
7.1 × 10–10
5.1 × 10–9

4.8 × 10–10
1.8 × 10–9
3.0 × 10–9

1.3 × 10–8
8.6 × 10–10
4.7 × 10–10
1.6 × 10–10
9.9 × 10–11

1.9 × 10–9
2.2 × 10–10
1.6 × 10–10

e(g)7–12 a2.3 × 10–10
4.4 × 10–10
3.1 × 10–9

5.0 × 10–10
1.3 × 10–9
1.8 × 10–9

7.6 × 10–9
5.4 × 10–10
3.0 × 10–10
1.1 × 10–10
6.8 × 10–11

1.2 × 10–9
1.5 × 10–10
1.1 × 10–10

e(g)12–17 a1.9 × 10–10
3.5 × 10–10
2.4 × 10–9

1.9 × 10–10
7.1 × 10–10
1.6 × 10–9

6.2 × 10–9
4.3 × 10–10
2.5 × 10–10
8.4 × 10–11
5.4 × 10–11

9.3 × 10–10
1.2 × 10–10
8.5 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

227

23.0 h

0.702 h27.7 d

Cr‑49

Cr‑51

0.543 h16.2 d330 d47.3 a3.08 h83.8 d3.35 d1.82 d
0.956 hPhysicalhalf-life

Cr‑48

Chromium

V‑47
V‑48
V‑49

Vanadium

Ti‑44
Ti‑45

Titanium

Sc‑46
Sc‑47
Sc‑48
Sc‑49

Radionuclidea

0.200
0.020
0.200
0.020
0.200
0.020

0.020
0.020
0.020

0.020
0.020

0.001
0.001
0.001
0.001

f1
1.1 × 10–8
6.1 × 10–9
1.3 × 10–8
1.0 × 10–9

1.4 × 10–9
1.4 × 10–9
6.8 × 10–10
6.8 × 10–10
3.5 × 10–10
3.3 × 10–10

7.3 × 10–10
1.5 × 10–8
2.2 × 10–10

0.100
0.010
0.100
0.010
0.100
0.010

0.010
0.010
0.010

0.010
0.010

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

e(g)5.5 × 10–8
1.6 × 10–9

f1 forg>1a

Age ≤ 1 a

9.9 × 10–10
9.9 × 10–10
3.9 × 10–10
3.9 × 10–10
2.3 × 10–10
2.2 × 10–10

4.1 × 10–10
1.1 × 10–8
1.4 × 10–10

3.1 × 10–8
9.8 × 10–10

7.9 × 10–9
3.9 × 10–9
9.3 × 10–9
5.7 × 10–10e(g)Age 1–2 a

5.7 × 10–10
5.7 × 10–10
2.0 × 10–10
2.0 × 10–10
1.2 × 10–10
1.2 × 10–10

2.0 × 10–10
5.9 × 10–9
6.9 × 10–11

1.7 × 10–8
5.0 × 10–10

4.4 × 10–9
2.0 × 10–9
5.1 × 10–9
2.8 × 10–10

e(g)

2–7 a

3.8 × 10–10
3.8 × 10–10
1.1 × 10–10
1.1 × 10–10
7.8 × 10–11
7.5 × 10–11

1.2 × 10–10
3.9 × 10–9
4.0 × 10–11

1.1 × 10–8
3.1 × 10–10

2.9 × 10–9
1.2 × 10–9
3.3 × 10–9
1.6 × 10–10

e(g)7–12 a2.5 × 10–10
2.5 × 10–10
7.7 × 10–11
7.7 × 10–11
4.8 × 10–11
4.6 × 10–11

8.0 × 10–11
2.5 × 10–9
2.3 × 10–11

6.9 × 10–9
1.9 × 10–10

1.8 × 10–9
6.8 × 10–10
2.1 × 10–9
1.0 × 10–10

e(g)12–17 a2.0 × 10–10
2.0 × 10–10
6.1 × 10–11
6.1 × 10–11
3.8 × 10–11
3.7 × 10–11

6.3 × 10–11
2.0 × 10–9
1.8 × 10–11

5.8 × 10–9
1.5 × 10–10

1.5 × 10–9
5.4 × 10–10
1.7 × 10–9
8.2 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

228

Co‑55
Co‑56
Co‑57
Co‑58
Co‑58mCo‑60

Cobaltd

Fe‑52
Fe‑55
Fe‑59
Fe‑60

Ironc

Mn‑51
Mn‑52
Mn‑52m
Mn‑53
Mn‑54
Mn‑56

ManganeseRadionuclidea

17.5 h78.7 d271 d70.8 d
9.15 h5.27 a8.28 h2.70 a44.5 d
1.00 × 105 a

0.770 h5.59 d
0.352 h3.70 × 106 a
312 d2.58 hPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600

0.600
0.600
0.600
0.600

0.200
0.200
0.200
0.200
0.200
0.200

f1

e(g)

6.0 × 10–9
2.5 × 10–8
2.9 × 10–9
7.3 × 10–9
2.0 × 10–10
5.4 × 10–8

1.3 × 10–8
7.6 × 10–9
3.9 × 10–8
7.9 × 10–7

1.1 × 10–9
1.2 × 10–8
7.8 × 10–10
4.1 × 10–10
5.4 × 10–9
2.7 × 10–9

Age ≤ 1 a

0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.100
0.100

0.100
0.100
0.100
0.100
0.100
0.100

f1 forg>1a

5.5 × 10–9
1.5 × 10–8
1.6 × 10–9
4.4 × 10–9
1.5 × 10–10
2.7 × 10–8

9.1 × 10–9
2.4 × 10–9
1.3 × 10–8
2.7 × 10–7

6.1 × 10–10
8.8 × 10–9
4.4 × 10–10
2.2 × 10–10
3.1 × 10–9
1.7 × 10–9e(g)Age 1–2 a

2.9 × 10–9
8.8 × 10–9
8.9 × 10–10
2.6 × 10–9
7.8 × 10–11
1.7 × 10–8

4.6 × 10–9
1.7 × 10–9
7.5 × 10–9
2.7 × 10–7

3.0 × 10–10
5.1 × 10–9
2.2 × 10–10
1.1 × 10–10
1.9 × 10–9
8.5 × 10–10

e(g)

2–7 a

1.8 × 10–9
5.8 × 10–9
5.8 × 10–10
1.7 × 10–9
4.7 × 10–11
1.1 × 10–8

2.8 × 10–9
1.1 × 10–9
4.7 × 10–9
2.5 × 10–7

1.8 × 10–10
3.4 × 10–9
1.3 × 10–10
6.5 × 10–11
1.3 × 10–9
5.1 × 10–10

e(g)7–12 a1.1 × 10–9
3.8 × 10–9
3.7 × 10–10
1.1 × 10–9
2.8 × 10–11
7.9 × 10–9

1.7 × 10–9
7.7 × 10–10
3.1 × 10–9
2.3 × 10–7

1.2 × 10–10
2.2 × 10–9
8.8 × 10–11
3.7 × 10–11
8.7 × 10–10
3.2 × 10–10

e(g)12–17 a1.0 × 10–9
2.5 × 10–9
2.1 × 10–10
7.4 × 10–10
2.4 × 10–11
3.4 × 10–9

1.4 × 10–9
3.3 × 10–10
1.8 × 10–9
1.1 × 10–7

9.3 × 10–11
1.8 × 10–9
6.9 × 10–11
3.0 × 10–11
7.1 × 10–10
2.5 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

229

Zn‑62
Zn‑63
Zn‑65

Zinc

Cu‑60
Cu‑61
Cu‑64
Cu‑67

Copper

Ni‑56
Ni‑57
Ni‑59
Ni‑63
Ni‑65
Ni‑66

Nickel

Co‑60mCo‑61
Co‑62mRadionuclidea

9.26 h
0.635 h244 d0.387 h3.41 h12.7 h
2.58 d6.10 d1.50 d7.50 × 104 a
96.0 a2.52 h2.27 d0.174 h1.65 h
0.232 hPhysicalhalf-life

1.000
1.000
1.000

1.000
1.000
1.000
1.000

0.100
0.100
0.100
0.100
0.100
0.100

0.600
0.600
0.600

f1
2.2 × 10–11
8.2 × 10–10
5.3 × 10–10

4.2 × 10–9
8.7 × 10–10
3.6 × 10–8

7.0 × 10–10
7.1 × 10–10
5.2 × 10–10
2.1 × 10–9

0.500
0.500
0.500

0.500
0.500
0.500
0.500

0.050
0.050
0.050
0.050
0.050
0.050

0.100
0.100
0.100

e(g)

5.3 × 10–9
6.8 × 10–9
6.4 × 10–10
1.6 × 10–9
2.1 × 10–9
3.3 × 10–8

f1 forg>1a

Age ≤ 1 a

6.5 × 10–9
5.2 × 10–10
1.6 × 10–8

4.2 × 10–10
7.5 × 10–10
8.3 × 10–10
2.4 × 10–9

4.0 × 10–9
4.9 × 10–9
3.4 × 10–10
8.4 × 10–10
1.3 × 10–9
2.2 × 10–8

1.2 × 10–11
5.1 × 10–10
3.0 × 10–10e(g)Age 1–2 a

3.3 × 10–9
2.6 × 10–10
9.7 × 10–9

2.2 × 10–10
3.9 × 10–10
4.2 × 10–10
1.2 × 10–9

2.3 × 10–9
2.7 × 10–9
1.9 × 10–10
4.6 × 10–10
6.3 × 10–10
1.1 × 10–8

5.7 × 10–12
2.5 × 10–10
1.5 × 10–10

e(g)

2–7 a

2.0 × 10–9
1.5 × 10–10
6.4 × 10–9

1.3 × 10–10
2.3 × 10–10
2.5 × 10–10
7.2 × 10–10

1.6 × 10–9
1.7 × 10–9
1.1 × 10–10
2.8 × 10–10
3.8 × 10–10
6.6 × 10–9

3.2 × 10–12
1.4 × 10–10
8.7 × 10–11

e(g)7–12 a

1.2 × 10–9
1.0 × 10–10
4.5 × 10–9

8.9 × 10–11
1.5 × 10–10
1.5 × 10–10
4.2 × 10–10

1.1 × 10–9
1.1 × 10–9
7.3 × 10–11
1.8 × 10–10
2.3 × 10–10
3.7 × 10–9

2.2 × 10–12
9.2 × 10–11
6.0 × 10–11

e(g)12–17 a9.4 × 10–10
7.9 × 10–11
3.9 × 10–9

7.0 × 10–11
1.2 × 10–10
1.2 × 10–10
3.4 × 10–10

8.6 × 10–10
8.7 × 10–10
6.3 × 10–11
1.5 × 10–10
1.8 × 10–10
3.0 × 10–9

1.7 × 10–12
7.4 × 10–11
4.7 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

230

Ge‑66
Ge‑67
Ge‑68
Ge‑69
Ge‑71
Ge‑75

Germanium

Ga‑65
Ga‑66
Ga‑67
Ga‑68
Ga‑70
Ga‑72
Ga‑73

2.27 h0.312 h288 d1.63 d11.8 d1.38 h

0.253 h9.40 h3.26 d
1.13 h
0.353 h14.1 h
4.91 h

1.94 dZn‑72

Gallium

0.950 h13.8 h3.92 hPhysicalhalf-life

Zn‑69
Zn‑69mZn‑71mRadionuclidea

1.000
1.000
1.000
1.000
1.000
1.000

0.010
0.010
0.010
0.010
0.010
0.010
0.010

1.000

1.000
1.000
1.000

f1

0.500

3.5 × 10–10
1.3 × 10–9
1.4 × 10–9
8.7 × 10–9

8.3 × 10–10
7.7 × 10–10
1.2 × 10–8
2.0 × 10–9
1.2 × 10–10
5.5 × 10–10
1.000
1.000
1.000
1.000
1.000
1.000

0.001
0.001
0.001
0.001
0.001
0.001
0.001

0.500
0.500
0.500

e(g)

4.3 × 10–10
1.2 × 10–8
1.8 × 10–9
1.2 × 10–9
3.9 × 10–10
1.0 × 10–8
3.0 × 10–9

f1 forg>1a

Age ≤ 1 a

5.3 × 10–10
4.2 × 10–10
8.0 × 10–9
1.3 × 10–9
7.8 × 10–11
3.1 × 10–10

2.4 × 10–10
7.9 × 10–9
1.2 × 10–9
6.7 × 10–10
2.2 × 10–10
6.8 × 10–9
1.9 × 10–9

8.6 × 10–9

2.2 × 10–10
2.3 × 10–9
1.5 × 10–9e(g)Age 1–2 a

2.9 × 10–10
2.1 × 10–10
4.2 × 10–9
7.1 × 10–10
4.0 × 10–11
1.5 × 10–10

1.2 × 10–10
4.0 × 10–9
6.4 × 10–10
3.4 × 10–10
1.0 × 10–10
3.6 × 10–9
9.3 × 10–10

4.5 × 10–9

1.1 × 10–10
1.2 × 10–9
7.8 × 10–10

e(g)

2–7 a

1.9 × 10–10
1.2 × 10–10
2.6 × 10–9
4.6 × 10–10
2.4 × 10–11
8.7 × 10–11

6.9 × 10–11
2.5 × 10–9
4.0 × 10–10
2.0 × 10–10
5.9 × 10–11
2.2 × 10–9
5.5 × 10–10

2.8 × 10–9

6.0 × 10–11
7.0 × 10–10
4.8 × 10–10

e(g)7–12 a1.3 × 10–10
8.2 × 10–11
1.6 × 10–9
3.0 × 10–10
1.5 × 10–11
5.9 × 10–11

4.7 × 10–11
1.5 × 10–9
2.4 × 10–10
1.3 × 10–10
4.0 × 10–11
1.4 × 10–9
3.3 × 10–10

1.7 × 10–9

3.9 × 10–11
4.1 × 10–10
3.0 × 10–10

e(g)12–17 a1.0 × 10–10
6.5 × 10–11
1.3 × 10–9
2.4 × 10–10
1.2 × 10–11
4.6 × 10–11

3.7 × 10–11
1.2 × 10–9
1.9 × 10–10
1.0 × 10–10
3.1 × 10–11
1.1 × 10–9
2.6 × 10–10

1.4 × 10–9

3.1 × 10–11
3.3 × 10–10
2.4 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

231

Se‑70
Se‑73
Se‑73m
Se‑75
Se‑79
Se‑81

Selenium

As‑69
As‑70
As‑71
As‑72
As‑73
As‑74
As‑76
As‑77
As‑78

Arsenic

Ge‑77
Ge‑78

Radionuclidea

0.683 h7.15 h
0.650 h120 d6.50 × 104 a
0.308 h0.253 h0.876 h2.70 d1.08 d80.3 d17.8 d110 d1.62 d1.51 h11.3 h1.45 hPhysicalhalf-life

1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000

f1
3.0 × 10–9
1.2 × 10–9

1.0 × 10–9
1.6 × 10–9
2.6 × 10–10
2.0 × 10–8
4.1 × 10–8
3.4 × 10–10
0.800
0.800
0.800
0.800
0.800
0.800

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

1.000
1.000

e(g)

6.6 × 10–10
1.2 × 10–9
2.8 × 10–9
1.1 × 10–8
2.6 × 10–9
1.0 × 10–8
1.0 × 10–8
2.7 × 10–9
2.0 × 10–9

f1 forg>1a

Age ≤ 1 a

7.1 × 10–10
1.4 × 10–9
1.8 × 10–10
1.3 × 10–8
2.8 × 10–8
1.9 × 10–10

3.7 × 10–10
7.8 × 10–10
2.8 × 10–9
1.2 × 10–8
1.9 × 10–9
8.2 × 10–9
1.1 × 10–8
2.9 × 10–9
1.4 × 10–9

1.8 × 10–9
7.0 × 10–10e(g)Age 1–2 a

3.6 × 10–10
7.4 × 10–10
9.5 × 10–11
8.3 × 10–9
1.9 × 10–8
9.0 × 10–11

1.8 × 10–10
4.1 × 10–10
1.5 × 10–9
6.3 × 10–9
9.3 × 10–10
4.3 × 10–9
5.8 × 10–9
1.5 × 10–9
7.0 × 10–10

9.9 × 10–10
3.6 × 10–10

e(g)

2–7 a

2.2 × 10–10
4.8 × 10–10
5.9 × 10–11
6.0 × 10–9
1.4 × 10–8
5.1 × 10–11

1.1 × 10–10
2.5 × 10–10
9.3 × 10–10
3.8 × 10–9
5.6 × 10–10
2.6 × 10–9
3.4 × 10–9
8.7 × 10–10
4.1 × 10–10

6.2 × 10–10
2.2 × 10–10

e(g)7–12 a

1.5 × 10–10
2.5 × 10–10
3.5 × 10–11
3.1 × 10–9
4.1 × 10–9
3.4 × 10–11

7.2 × 10–11
1.7 × 10–10
5.7 × 10–10
2.3 × 10–9
3.2 × 10–10
1.6 × 10–9
2.0 × 10–9
5.0 × 10–10
2.7 × 10–10

4.1 × 10–10
1.5 × 10–10

e(g)12–17 a1.2 × 10–10
2.1 × 10–10
2.8 × 10–11
2.6 × 10–9
2.9 × 10–9
2.7 × 10–11

5.7 × 10–11
1.3 × 10–10
4.6 × 10–10
1.8 × 10–9
2.6 × 10–10
1.3 × 10–9
1.6 × 10–9
4.0 × 10–10
2.1 × 10–10

3.3 × 10–10
1.2 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

232

Rb‑79
Rb‑81
Rb‑81m
Rb‑82m
Rb‑83
Rb‑84

Rubidium

Br‑74
Br‑74m
Br‑75
Br‑76
Br‑77
Br‑80
Br‑80m
Br‑82
Br‑83
Br‑84

BromineSe‑81mSe‑83

Radionuclidea

0.382 h4.58 h
0.533 h6.20 h86.2 d32.8 d

0.422 h0.691 h1.63 h
16.2 h2.33 d0.290 h4.42 h1.47 d
2.39 h
0.530 h0.954 h0.375 hPhysicalhalf-life

1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000

f1
6.0 × 10–10
4.6 × 10–10

5.7 × 10–10
5.4 × 10–10
1.1 × 10–10
8.7 × 10–10
1.1 × 10–8
2.0 × 10–8
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.800
0.800

e(g)

9.0 × 10–10
1.5 × 10–9
8.5 × 10–10
4.2 × 10–9
6.3 × 10–10
3.9 × 10–10
1.4 × 10–9
3.7 × 10–9
5.3 × 10–10
1.0 × 10–9

f1 forg>1a

Age ≤ 1 a

3.2 × 10–10
3.2 × 10–10
6.2 × 10–11
5.9 × 10–10
8.4 × 10–9
1.4 × 10–8

5.2 × 10–10
8.5 × 10–10
4.9 × 10–10
2.7 × 10–9
4.4 × 10–10
2.1 × 10–10
8.0 × 10–10
2.6 × 10–9
3.0 × 10–10
5.8 × 10–10

3.7 × 10–10
2.9 × 10–10e(g)Age 1–2 a

1.6 × 10–10
1.6 × 10–10
3.1 × 10–11
3.4 × 10–10
4.9 × 10–9
7.9 × 10–9

2.6 × 10–10
4.3 × 10–10
2.5 × 10–10
1.4 × 10–9
2.5 × 10–10
1.0 × 10–10
3.9 × 10–10
1.5 × 10–9
1.4 × 10–10
2.8 × 10–10

1.8 × 10–10
1.5 × 10–10

e(g)

2–7 a

9.2 × 10–11
1.0 × 10–10
1.8 × 10–11
2.2 × 10–10
3.2 × 10–9
5.0 × 10–9

1.5 × 10–10
2.5 × 10–10
1.5 × 10–10
8.7 × 10–10
1.7 × 10–10
5.8 × 10–11
2.3 × 10–10
9.5 × 10–10
8.3 × 10–11
1.6 × 10–10

1.1 × 10–10
8.7 × 10–11

e(g)7–12 a6.3 × 10–11
6.7 × 10–11
1.2 × 10–11
1.5 × 10–10
2.2 × 10–9
3.3 × 10–9

1.1 × 10–10
1.7 × 10–10
9.9 × 10–11
5.6 × 10–10
1.1 × 10–10
3.9 × 10–11
1.4 × 10–10
6.4 × 10–10
5.5 × 10–11
1.1 × 10–10

6.7 × 10–11
5.9 × 10–11

e(g)12–17 a5.0 × 10–11
5.4 × 10–11
9.7 × 10–12
1.3 × 10–10
1.9 × 10–9
2.8 × 10–9

8.4 × 10–11
1.4 × 10–10
7.9 × 10–11
4.6 × 10–10
9.6 × 10–11
3.1 × 10–11
1.1 × 10–10
5.4 × 10–10
4.3 × 10–11
8.8 × 10–11

5.3 × 10–11
4.7 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

233

Y‑86
Y‑86m
Y‑87

Yttrium

Sr‑80
Sr‑81
Sr‑82
Sr‑83
Sr‑85
Sr‑85m
Sr‑87m
Sr‑89
Sr‑90
Sr‑91
Sr‑92

Strontiume

Rb‑86
Rb‑87
Rb‑88
Rb‑89

Radionuclidea

14.7 h0.800 h3.35 d

1.67 h
0.425 h25.0 d1.35 d64.8 d
1.16 h2.80 h50.5 d29.1 a9.50 h2.71 h18.7 d
4.70 × 1010 a
0.297 h0.253 hPhysicalhalf-life

0.001
0.001
0.001

0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600

1.000
1.000
1.000
1.000

f1
3.1 × 10–8
1.5 × 10–8
1.1 × 10–9
5.4 × 10–10

7.6 × 10–9
4.5 × 10–10
4.6 × 10–9

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300

1.000
1.000
1.000
1.000

e(g)

3.7 × 10–9
8.4 × 10–10
7.2 × 10–8
3.4 × 10–9
7.7 × 10–9
4.5 × 10–11
2.4 × 10–10
3.6 × 10–8
2.3 × 10–7
5.2 × 10–9
3.4 × 10–9

f1 forg>1a

Age ≤ 1 a

5.2 × 10–9
3.1 × 10–10
3.2 × 10–9

2.3 × 10–9
4.9 × 10–10
4.1 × 10–8
2.7 × 10–9
3.1 × 10–9
3.0 × 10–11
1.7 × 10–10
1.8 × 10–8
7.3 × 10–8
4.0 × 10–9
2.7 × 10–9

2.0 × 10–8
1.0 × 10–8
6.2 × 10–10
3.0 × 10–10e(g)Age 1–2 a

2.9 × 10–9
1.7 × 10–10
1.8 × 10–9

1.1 × 10–9
2.4 × 10–10
2.1 × 10–8
1.4 × 10–9
1.7 × 10–9
1.7 × 10–11
9.0 × 10–11
8.9 × 10–9
4.7 × 10–8
2.1 × 10–9
1.4 × 10–9

9.9 × 10–9
5.2 × 10–9
3.0 × 10–10
1.5 × 10–10

e(g)

2–7 a

1.9 × 10–9
1.1 × 10–10
1.1 × 10–9

6.5 × 10–10
1.4 × 10–10
1.3 × 10–8
9.1 × 10–10
1.5 × 10–9
1.1 × 10–11
5.6 × 10–11
5.8 × 10–9
6.0 × 10–8
1.2 × 10–9
8.2 × 10–10

5.9 × 10–9
3.1 × 10–9
1.7 × 10–10
8.6 × 10–11

e(g)7–12 a

1.2 × 10–9
7.1 × 10–11
7.0 × 10–10

4.2 × 10–10
9.6 × 10–11
8.7 × 10–9
5.7 × 10–10
1.3 × 10–9
7.8 × 10–12
3.6 × 10–11
4.0 × 10–9
8.0 × 10–8
7.4 × 10–10
4.8 × 10–10

3.5 × 10–9
1.8 × 10–9
1.2 × 10–10
5.9 × 10–11

e(g)12–17 a9.6 × 10–10
5.6 × 10–11
5.5 × 10–10

3.4 × 10–10
7.7 × 10–11
6.1 × 10–9
4.9 × 10–10
5.6 × 10–10
6.1 × 10–12
3.0 × 10–11
2.6 × 10–9
2.8 × 10–8
6.5 × 10–10
4.3 × 10–10

2.8 × 10–9
1.5 × 10–9
9.0 × 10–11
4.7 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

234

Nb‑88
Nb‑89
Nb‑89m

Niobium

Zr‑86
Zr‑88
Zr‑89
Zr‑93
Zr‑95
Zr‑97

Zirconium

Y‑88
Y‑90
Y‑90m
Y‑91
Y‑91m
Y‑92
Y‑93
Y‑94
Y‑95

Radionuclidea

0.238 h2.03 h1.10 h

16.5 h83.4 d3.27 d1.53 × 106 a
64.0 d
16.9 h107 d2.67 d
3.19 h
58.5 d0.828 h3.54 h10.1 h
0.318 h0.178 hPhysicalhalf-life

0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

f1
8.1 × 10–9
3.1 × 10–8
1.8 × 10–9
2.8 × 10–8
9.2 × 10–11
5.9 × 10–9
1.4 × 10–8
9.9 × 10–10
5.7 × 10–10

6.7 × 10–10
3.0 × 10–9
1.5 × 10–9

0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

e(g)6.9 × 10–9
2.8 × 10–9
6.5 × 10–9
1.2 × 10–9
8.5 × 10–9
2.2 × 10–8

f1 forg>1a

Age ≤ 1 a

3.8 × 10–10
2.0 × 10–9
8.7 × 10–10

4.8 × 10–9
2.0 × 10–9
4.5 × 10–9
7.6 × 10–10
5.6 × 10–9
1.4 × 10–8

6.0 × 10–9
2.0 × 10–8
1.2 × 10–9
1.8 × 10–8
6.0 × 10–11
3.6 × 10–9
8.5 × 10–9
5.5 × 10–10
3.1 × 10–10e(g)Age 1–2 a

1.9 × 10–10
1.0 × 10–9
4.4 × 10–10

2.7 × 10–9
1.2 × 10–9
2.5 × 10–9
5.1 × 10–10
3.0 × 10–9
7.3 × 10–9

3.5 × 10–9
1.0 × 10–8
6.1 × 10–10
8.8 × 10–9
3.3 × 10–11
1.8 × 10–9
4.3 × 10–9
2.7 × 10–10
1.5 × 10–10

e(g)

2–7 a

1.1 × 10–10
6.0 × 10–10
2.7 × 10–10

1.7 × 10–9
8.0 × 10–10
1.6 × 10–9
5.8 × 10–10
1.9 × 10–9
4.4 × 10–9

2.4 × 10–9
5.9 × 10–9
3.7 × 10–10
5.2 × 10–9
2.1 × 10–11
1.0 × 10–9
2.5 × 10–9
1.5 × 10–10
8.7 × 10–11

e(g)7–12 a7.9 × 10–11
3.4 × 10–10
1.8 × 10–10

1.1 × 10–9
5.4 × 10–10
9.9 × 10–10
8.6 × 10–10
1.2 × 10–9
2.6 × 10–9

1.6 × 10–9
3.3 × 10–9
2.2 × 10–10
2.9 × 10–9
1.4 × 10–11
6.2 × 10–10
1.4 × 10–9
1.0 × 10–10
5.9 × 10–11

e(g)12–17 a6.3 × 10–11
2.7 × 10–10
1.4 × 10–10

8.6 × 10–10
4.5 × 10–10
7.9 × 10–10
1.1 × 10–9
9.5 × 10–1
2.1 × 10–9

1.3 × 10–9
2.7 × 10–9
1.7 × 10–10
2.4 × 10–9
1.1 × 10–11
4.9 × 10–10
1.2 × 10–9
8.1 × 10–11
4.6 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

235

Tc‑93
Tc‑93m
Tc‑94
Tc‑94mTc‑95

Technetium

Mo‑90
Mo‑93
Mo‑93mMo‑99
Mo-101

Molybdenum

Nb‑90
Nb‑93m
Nb‑94
Nb‑95
Nb‑95m
Nb‑96
Nb‑97
Nb‑98

Radionuclidea

2.75 h
0.725 h4.88 h
0.867 h20.0 h

5.67 h
3.50 × 103 a6.85 h
2.75 d
0.244 h14.6 h13.6 a2.03 × 104 a
35.1 d3.61 d23.3 h1.20 h
0.858 hPhysicalhalf-life

1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1
1.1 × 10–8
1.5 × 10–9
1.5 × 10–8
4.6 × 10–9
6.4 × 10–9
9.2 × 10–9
7.7 × 10–10
1.2 × 10–9

2.7 × 10–10
2.0 × 10–10
1.2 × 10–9
1.3 × 10–9
9.9 × 10–10
0.500
0.500
0.500
0.500
0.500

1.000
1.000
1.000
1.000
1.000

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)

1.7 × 10–9
7.9 × 10–9
8.0 × 10–10
5.5 × 10–9
4.8 × 10–10

f1 forg>1a

Age ≤ 1 a

2.5 × 10–10
1.3 × 10–10
1.0 × 10–9
6.5 × 10–10
8.7 × 10–10

1.2 × 10–9
6.9 × 10–9
5.4 × 10–10
3.5 × 10–9
2.7 × 10–10

7.2 × 10–9
9.1 × 10–10
9.7 × 10–9
3.2 × 10–9
4.1 × 10–9
6.3 × 10–9
4.5 × 10–10
7.1 × 10–10e(g)Age 1–2 a

1.5 × 10–10
7.3 × 10–11
5.8 × 10–10
3.3 × 10–10
5.0 × 10–10

6.3 × 10–10
5.0 × 10–9
3.1 × 10–10
1.8 × 10–9
1.3 × 10–10

3.9 × 10–9
4.6 × 10–10
5.3 × 10–9
1.8 × 10–9
2.1 × 10–9
3.4 × 10–9
2.3 × 10–10
3.6 × 10–10

e(g)

2–7 a

9.8 × 10–11
4.6 × 10–11
3.7 × 10–10
1.9 × 10–10
3.3 × 10–10

4.0 × 10–10
4.0 × 10–9
2.0 × 10–10
1.1 × 10–9
7.6 × 10–11

2.5 × 10–9
2.7 × 10–10
3.4 × 10–9
1.1 × 10–9
1.2 × 10–9
2.2 × 10–9
1.3 × 10–10
2.2 × 10–10

e(g)7–12 a6.8 × 10–11
3.2 × 10–11
2.5 × 10–10
1.3 × 10–10
2.3 × 10–10

2.7 × 10–10
3.4 × 10–9
1.4 × 10–10
7.6 × 10–10
5.2 × 10–11

1.6 × 10–9
1.5 × 10–10
2.1 × 10–9
7.4 × 10–10
7.1 × 10–10
1.4 × 10–9
8.7 × 10–11
1.4 × 10–10

e(g)12–17 a5.5 × 10–11
2.5 × 10–11
2.0 × 10–10
1.0 × 10–10
1.8 × 10–10

2.2 × 10–10
3.1 × 10–9
1.1 × 10–10
6.0 × 10–10
4.1 × 10–11

1.2 × 10–9
1.2 × 10–10
1.7 × 10–9
5.8 × 10–10
5.6 × 10–10
1.1 × 10–9
6.8 × 10–11
1.1 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

236

Rh‑99
Rh‑99m
Rh-100Rhodium

Ru‑94
Ru‑97
Ru-103
Ru-105
Ru-106

Ruthenium

Tc‑95m
Tc‑96
Tc‑96m
Tc‑97
Tc‑97m
Tc‑98
Tc‑99
Tc‑99m
Tc-101
Tc-104

Radionuclidea

16.0 d
4.70 h20.8 h

0.863 h2.90 d39.3 d
4.44 h1.01 a61.0 d
4.28 d
0.858 h2.60 × 106 a
87.0 d
4.20 × 106 a
2.13 × 105 a
6.02 h
0.237 h0.303 hPhysicalhalf-life

0.100
0.100
0.100

0.100
0.100
0.100
0.100
0.100

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1
4.7 × 10–9
6.7 × 10–9
1.0 × 10–10
9.9 × 10–10
8.7 × 10–9
2.3 × 10–8
1.0 × 10–8
2.0 × 10–10
2.4 × 10–10
1.0 × 10–9

4.2 × 10–9
4.9 × 10–10
4.9 × 10–9

0.050
0.050
0.050

0.050
0.050
0.050
0.050
0.050

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

e(g)

9.3 × 10–10
1.2 × 10–9
7.1 × 10–9
2.7 × 10–9
8.4 × 10–8

f1 forg>1a

Age ≤ 1 a

2.9 × 10–9
3.5 × 10–10
3.6 × 10–9

5.9 × 10–10
8.5 × 10–10
4.6 × 10–9
1.8 × 10–9
4.9 × 10–8

2.8 × 10–9
5.1 × 10–9
6.5 × 10–11
4.9 × 10–10
4.1 × 10–9
1.2 × 10–8
4.8 × 10–9
1.3 × 10–10
1.3 × 10–10
5.3 × 10–10e(g)Age 1–2 a

1.6 × 10–9
2.0 × 10–10
2.0 × 10–9

3.1 × 10–10
4.7 × 10–10
2.4 × 10–9
9.1 × 10–10
2.5 × 10–8

1.6 × 10–9
3.0 × 10–9
3.6 × 10–11
2.4 × 10–10
2.0 × 10–9
6.1 × 10–9
2.3 × 10–9
7.2 × 10–11
6.1 × 10–11
2.6 × 10–10

e(g)

2–7 a

1.0 × 10–9
1.3 × 10–10
1.4 × 10–9

1.9 × 10–10
3.0 × 10–10
1.5 × 10–9
5.5 × 10–10
1.5 × 10–8

1.0 × 10–9
2.0 × 10–9
2.3 × 10–11
1.4 × 10–10
1.1 × 10–9
3.7 × 10–9
1.3 × 10–9
4.3 × 10–11
3.5 × 10–11
1.5 × 10–10

e(g)7–12 a6.5 × 10–10
8.3 × 10–11
8.8 × 10–10

1.2 × 10–10
1.9 × 10–10
9.2 × 10–10
3.3 × 10–10
8.6 × 10–9

7.0 × 10–10
1.4 × 10–9
1.6 × 10–11
8.8 × 10–11
7.0 × 10–10
2.5 × 10–9
8.2 × 10–10
2.8 × 10–11
2.4 × 10–11
1.0 × 10–10

e(g)12–17 a5.1 × 10–10
6.6 × 10–11
7.1 × 10–10

9.4 × 10–11
1.5 × 10–10
7.3 × 10–10
2.6 × 10–10
7.0 × 10–9

5.6 × 10–10
1.1 × 10–9
1.2 × 10–11
6.8 × 10–11
5.5 × 10–10
2.0 × 10–9
6.4 × 10–10
2.2 × 10–11
1.9 × 10–1
8.0 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

237

Ag-102
Ag-103Ag-104Ag-104m
Ag-105

Silver

Pd-100
Pd-101
Pd-103
Pd-107
Pd-109Palladium

Rh-101
Rh-101m
Rh-102
Rh-102m
Rh-103m
Rh-105
Rh-106m
Rh-107

Radionuclidea

0.215 h1.09 h1.15 h
0.558 h41.0 d

3.63 d8.27 h
17.0 d6.50 × 106 a
13.4 h3.20 a4.34 d
2.90 a207 d0.935 h1.47 d
2.20 h
0.362 hPhysicalhalf-life

0.100
0.100
0.100
0.100
0.100

0.050
0.050
0.050
0.050
0.050

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1
4.9 × 10–9
1.7 × 10–9
1.9 × 10–8
1.2 × 10–8
4.7 × 10–11
4.0 × 10–9
1.4 × 10–9
2.9 × 10–10

4.2 × 10–10
4.5 × 10–10
4.3 × 10–10
5.6 × 10–10
3.9 × 10–9
0.050
0.050
0.050
0.050
0.050

0.005
0.005
0.005
0.005
0.005

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

e(g)

7.4 × 10–9
8.2 × 10–10
2.2 × 10–9
4.4 × 10–10
6.3 × 10–9

f1 forg>1a

Age ≤ 1 a

2.4 × 10–10
2.7 × 10–10
2.9 × 10–10
3.3 × 10–10
2.5 × 10–9

5.2 × 10–9
5.7 × 10–10
1.4 × 10–9
2.8 × 10–10
4.1 × 10–9

2.8 × 10–9
1.2 × 10–9
1.0 × 10–8
7.4 × 10–9
2.7 × 10–11
2.7 × 10–9
9.7 × 10–10
1.6 × 10–10e(g)Age 1–2 a

1.2 × 10–10
1.4 × 10–10
1.7 × 10–10
1.7 × 10–10
1.4 × 10–9

2.9 × 10–9
3.1 × 10–10
7.2 × 10–10
1.4 × 10–10
2.0 × 10–9

1.6 × 10–9
6.8 × 10–10
6.4 × 10–9
3.9 × 10–9
1.3 × 10–11
1.3 × 10–9
5.3 × 10–10
7.9 × 10–11

e(g)

2–7 a

7.3 × 10–11
8.3 × 10–11
1.1 × 10–10
1.0 × 10–10
9.1 × 10–10

1.9 × 10–9
1.9 × 10–10
4.3 × 10–10
8.1 × 10–11
1.2 × 10–9

1.0 × 10–9
4.4 × 10–10
4.3 × 10–9
2.4 × 10–9
7.4 × 10–12
8.0 × 10–10
3.3 × 10–10
4.5 × 10–11

e(g)7–12 a5.0 × 10–11
5.5 × 10–11
7.5 × 10–11
6.8 × 10–11
5.9 × 10–10

1.2 × 10–9
1.2 × 10–10
2.4 × 10–10
4.6 × 10–11
6.8 × 10–10

6.7 × 10–10
2.8 × 10–10
3.0 × 10–9
1.4 × 10–9
4.8 × 10–12
4.6 × 10–10
2.0 × 10–10
3.1 × 10–11

e(g)12–17 a4.0 × 10–11
4.3 × 10–11
6.0 × 10–11
5.4 × 10–11
4.7 × 10–10

9.4 × 10–10
9.4 × 10–11
1.9 × 10–10
3.7 × 10–11
5.5 × 10–10

5.5 × 10–10
2.2 × 10–10
2.6 × 10–9
1.2 × 10–9
3.8 × 10–12
3.7 × 10–10
1.6 × 10–10
2.4 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

238

In-109In‑110Indium

Cd-104
Cd-107
Cd-109
Cd‑113
Cd‑113m
Cd‑115
Cd‑115m
Cd‑117
Cd‑117m

Cadmium

Ag-106
Ag-106m
Ag-108m
Ag‑110m
Ag‑111
Ag‑112
Ag‑115

Radionuclidea

4.20 h
4.90 h

0.961 h6.49 h1.27 a9.30 × 1015 a
13.6 a2.23 d44.6 d2.49 h
3.36 h

0.399 h8.41 d
1.27 × 102 a
250 d7.45 d
3.12 h
0.333 hPhysicalhalf-life

0.040
0.040

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1
3.7 × 10–10
9.7 × 10–9
2.1 × 10–8
2.4 × 10–8
1.4 × 10–8
4.9 × 10–9
7.2 × 10–10

5.2 × 10–10
1.5 × 10–9

0.020
0.020

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.050
0.050
0.050
0.050
0.050
0.050
0.050

e(g)

4.2 × 10–10
7.1 × 10–10
2.1 × 10–8
1.0 × 10–7
1.2 × 10–7
1.4 × 10–8
4.1 × 10–8
2.9 × 10–9
2.6 × 10–9

f1 forg>1a

Age ≤ 1 a

3.6 × 10–10
1.1 × 10–9

2.9 × 10–10
4.6 × 10–10
9.5 × 10–9
4.8 × 10–8
5.6 × 10–8
9.7 × 10–9
1.9 × 10–8
1.9 × 10–9
1.7 × 10–9

2.1 × 10–10
6.9 × 10–9
1.1 × 10–8
1.4 × 10–8
9.3 × 10–9
3.0 × 10–9
4.1 × 10–10e(g)Age 1–2 a

2.0 × 10–10
6.5 × 10–10

1.7 × 10–10
2.3 × 10–10
5.5 × 10–9
3.7 × 10–8
3.9 × 10–8
4.9 × 10–9
9.7 × 10–9
9.5 × 10–10
9.0 × 10–10

1.0 × 10–10
4.1 × 10–9
6.5 × 10–9
7.8 × 10–9
4.6 × 10–9
1.5 × 10–9
2.0 × 10–10

e(g)

2–7 a

1.3 × 10–10
4.4 × 10–10

1.1 × 10–10
1.3 × 10–10
3.5 × 10–9
3.0 × 10–8
2.9 × 10–8
2.9 × 10–9
6.9 × 10–9
5.7 × 10–10
5.6 × 10–10

6.0 × 10–11
2.8 × 10–9
4.3 × 10–9
5.2 × 10–9
2.7 × 10–9
8.9 × 10–10
1.2 × 10–10

e(g)7–12 a8.2 × 10–11
3.0 × 10–10

7.2 × 10–11
7.8 × 10–11
2.4 × 10–9
2.6 × 10–8
2.4 × 10–8
1.7 × 10–9
4.1 × 10–9
3.5 × 10–10
3.5 × 10–10

4.1 × 10–11
1.8 × 10–9
2.8 × 10–9
3.4 × 10–9
1.6 × 10–9
5.4 × 10–10
7.7 × 10–11

e(g)12–17 a6.6 × 10–11
2.4 × 10–10

5.4 × 10–11
6.2 × 10–11
2.0 × 10–9
2.5 × 10–8
2.3 × 10–8
1.4 × 10–9
3.3 × 10–9
2.8 × 10–10
2.8 × 10–10

3.2 × 10–11
1.5 × 10–9
2.3 × 10–9
2.8 × 10–9
1.3 × 10–9
4.3 × 10–10
6.0 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

239

1.15 h2.83 d0.240 h1.66 h49.5 d
5.10 × 1015 a
4.49 h
0.902 h0.730 h1.94 h
0.300 h4.00 h
0.588 h115 d13.6 d293 d1.13 d55.0 a129 d0.668 hTin
Sn‑110Sn‑111
Sn‑113
Sn‑117m
Sn‑119m
Sn‑121
Sn‑121m
Sn‑123
Sn‑123m

Physicalhalf-life

In‑110m
In‑111
In‑112
In‑113m
In‑114m
In‑115
In‑115m
In‑116m
In‑117
In‑117m
In‑119m

Radionuclidea

0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

f1
1.1 × 10–9
2.4 × 10–9
1.2 × 10–10
3.0 × 10–10
5.6 × 10–8
1.3 × 10–7
9.6 × 10–10
5.8 × 10–10
3.3 × 10–10
1.4 × 10–9
5.9 × 10–10

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

e(g)

3.5 × 10–9
2.5 × 10–10
7.8 × 10–9
7.7 × 10–9
4.1 × 10–9
2.6 × 10–9
4.6 × 10–9
2.5 × 10–8
4.7 × 10–10

f1 forg>1a

Age ≤ 1 a

2.3 × 10–9
1.5 × 10–10
5.0 × 10–9
5.0 × 10–9
2.5 × 10–9
1.7 × 10–9
2.7 × 10–9
1.6 × 10–8
2.6 × 10–10

6.4 × 10–10
1.7 × 10–9
6.7 × 10–11
1.8 × 10–10
3.1 × 10–8
6.4 × 10–8
6.0 × 10–10
3.6 × 10–10
1.9 × 10–10
8.6 × 10–10
3.2 × 10–10e(g)Age 1–2 a

1.2 × 10–9
7.4 × 10–11
2.6 × 10–9
2.5 × 10–9
1.3 × 10–9
8.4 × 10–10
1.4 × 10–9
7.8 × 10–9
1.3 × 10–10

3.2 × 10–10
9.1 × 10–10
3.3 × 10–11
9.3 × 10–11
1.5 × 10–8
4.8 × 10–8
3.0 × 10–10
1.9 × 10–10
9.7 × 10–11
4.3 × 10–10
1.6 × 10–10

e(g)

2–7 a

7.4 × 10–10
4.4 × 10–11
1.6 × 10–9
1.5 × 10–9
7.5 × 10–10
5.0 × 10–10
8.2 × 10–10
4.6 × 10–9
7.3 × 10–11

1.9 × 10–10
5.9 × 10–10
1.9 × 10–11
6.2 × 10–11
9.0 × 10–9
4.3 × 10–8
1.8 × 10–10
1.2 × 10–10
5.8 × 10–11
2.5 × 10–10
8.8 × 10–11

e(g)7–12 a4.4 × 10–10
3.0 × 10–11
9.2 × 10–10
8.8 × 10–10
4.3 × 10–10
2.8 × 10–10
4.7 × 10–10
2.6 × 10–9
4.9 × 10–11

1.3 × 10–10
3.7 × 10–10
1.3 × 10–11
3.6 × 10–11
5.2 × 10–9
3.6 × 10–8
1.1 × 10–10
8.0 × 10–11
3.9 × 10–11
1.6 × 10–10
6.0 × 10–11

e(g)12–17 a3.5 × 10–10
2.3 × 10–11
7.3 × 10–10
7.1 × 10–10
3.4 × 10–10
2.3 × 10–10
3.8 × 10–10
2.1 × 10–9
3.8 × 10–11

1.0 × 10–10
2.9 × 10–10
1.0 × 10–11
2.8 × 10–11
4.1 × 10–9
3.2 × 10–8
8.6 × 10–11
6.4 × 10–11
3.1 × 10–11
1.2 × 10–10
4.7 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

240

Sb‑115
Sb‑116
Sb‑116m
Sb‑117
Sb‑118m
Sb‑119Sb‑120Sb‑120m
Sb‑122
Sb‑124
Sb‑124m
Sb‑125
Sb‑126
Sb‑126m
Sb‑127
Sb‑128Antimony

Sn‑125
Sn‑126
Sn‑127
Sn‑128

Radionuclidea

0.530 h0.263 h1.00 h2.80 h5.00 h
1.59 d0.265 h5.76 d2.70 d60.2 d
0.337 h2.77 a12.4 d
0.317 h3.85 d
9.01 h

9.64 d
1.00 × 105 a2.10 h
0.985 hPhysicalhalf-life

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

0.040
0.040
0.040
0.040

f1
3.5 × 10–8
5.0 × 10–8
2.0 × 10–9
1.6 × 10–9

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.020
0.020
0.020
0.020

e(g)

2.5 × 10–10
2.7 × 10–10
5.0 × 10–10
1.6 × 10–10
1.3 × 10–9
8.4 × 10–10
1.7 × 10–10
8.1 × 10–9
1.8 × 10–8
2.5 × 10–8
8.5 × 10–11
1.1 × 10–8
2.0 × 10–8
3.9 × 10–10
1.7 × 10–8
6.3 × 10–9

f1 forg>1a

Age ≤ 1 a

1.5 × 10–10
1.6 × 10–10
3.3 × 10–10
1.0 × 10–10
1.0 × 10–9
5.8 × 10–10
9.4 × 10–11
6.0 × 10–9
1.2 × 10–8
1.6 × 10–8
4.9 × 10–11
6.1 × 10–9
1.4 × 10–8
2.2 × 10–10
1.2 × 10–8
4.5 × 10–9

2.2 × 10–8
3.0 × 10–8
1.3 × 10–9
9.7 × 10–10e(g)Age 1–2 a

7.5 × 10–11
8.0 × 10–11
1.9 × 10–10
5.6 × 10–11
5.8 × 10–10
3.0 × 10–10
4.6 × 10–11
3.5 × 10–9
6.1 × 10–9
8.4 × 10–9
2.5 × 10–11
3.4 × 10–9
7.6 × 10–9
1.1 × 10–10
5.9 × 10–9
2.4 × 10–9

1.1 × 10–8
1.6 × 10–8
6.6 × 10–10
4.9 × 10–10

e(g)

2–7 a

4.5 × 10–11
4.8 × 10–11
1.2 × 10–10
3.5 × 10–11
3.9 × 10–10
1.8 × 10–10
2.7 × 10–11
2.3 × 10–9
3.7 × 10–9
5.2 × 10–9
1.5 × 10–11
2.1 × 10–9
4.9 × 10–9
6.6 × 10–11
3.6 × 10–9
1.5 × 10–9

6.7 × 10–9
9.8 × 10–9
4.0 × 10–10
3.0 × 10–10

e(g)7–12 a3.1 × 10–11
3.3 × 10–11
8.3 × 10–11
2.2 × 10–11
2.6 × 10–10
1.0 × 10–10
1.8 × 10–11
1.6 × 10–9
2.1 × 10–9
3.2 × 10–9
1.0 × 10–11
1.4 × 10–9
3.1 × 10–9
4.5 × 10–11
2.1 × 10–9
9.5 × 10–10

3.8 × 10–9
5.9 × 10–9
2.5 × 10–10
1.9 × 10–10

e(g)12–17 a2.4 × 10–11
2.6 × 10–11
6.7 × 10–11
1.8 × 10–11
2.1 × 10–10
8.0 × 10–11
1.4 × 10–11
1.2 × 10–9
1.7 × 10–9
2.5 × 10–9
8.0 × 10–12
1.1 × 10–9
2.4 × 10–9
3.6 × 10–11
1.7 × 10–9
7.6 × 10–10

3.1 × 10–9
4.7 × 10–9
2.0 × 10–10
1.5 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

241

Te‑116
Te‑121
Te‑121m
Te‑123
Te‑123m
Te‑125m
Te‑127
Te‑127m
Te‑129
Te‑129m
Te‑131
Te‑131m
Te‑132
Te‑133
Te‑133m
Te‑134

Tellurium

Sb‑128
Sb‑129Sb‑130Sb‑131

Radionuclidea

2.49 h
17.0 d154 d1.00 × 1013 a
120 d
58.0 d9.35 h109 d1.16 h33.6 d
0.417 h1.25 d3.26 d
0.207 h0.923 h0.696 h0.173 h4.32 h
0.667 h0.383 hPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600

0.200
0.200
0.200
0.200

f1
3.7 × 10–10
4.3 × 10–9
9.1 × 10–10
1.1 × 10–9

0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300

0.100
0.100
0.100
0.100

e(g)

1.4 × 10–9
3.1 × 10–9
2.7 × 10–8
2.0 × 10–8
1.9 × 10–8
1.3 × 10–8
1.5 × 10–9
4.1 × 10–8
7.5 × 10–10
4.4 × 10–8
9.0 × 10–10
2.0 × 10–8
4.8 × 10–8
8.4 × 10–10
3.1 × 10–9
1.1 × 10–9

f1 forg>1a

Age ≤ 1 a

1.0 × 10–9
2.0 × 10–9
1.2 × 10–8
9.3 × 10–9
8.8 × 10–9
6.3 × 10–9
1.2 × 10–9
1.8 × 10–8
4.4 × 10–10
2.4 × 10–8
6.6 × 10–10
1.4 × 10–8
3.0 × 10–8
6.3 × 10–10
2.4 × 10–9
7.5 × 10–10

2.1 × 10–10
2.8 × 10–9
5.4 × 10–10
7.3 × 10–10e(g)Age 1–2 a

5.5 × 10–10
1.2 × 10–9
6.9 × 10–9
6.9 × 10–9
4.9 × 10–9
3.3 × 10–9
6.2 × 10–10
9.5 × 10–9
2.1 × 10–10
1.2 × 10–8
3.5 × 10–10
7.8 × 10–9
1.6 × 10–8
3.3 × 10–10
1.3 × 10–9
3.9 × 10–10

1.0 × 10–10
1.5 × 10–9
2.8 × 10–10
3.9 × 10–10

e(g)

2–7 a

3.4 × 10–10
8.0 × 10–10
4.2 × 10–9
5.4 × 10–9
2.8 × 10–9
1.9 × 10–9
3.6 × 10–10
5.2 × 10–9
1.2 × 10–10
6.6 × 10–9
1.9 × 10–10
4.3 × 10–9
8.3 × 10–9
1.6 × 10–10
6.3 × 10–10
2.2 × 10–10

6.0 × 10–11
8.8 × 10–10
1.7 × 10–10
2.1 × 10–10

e(g)7–12 a2.1 × 10–10
5.4 × 10–10
2.8 × 10–9
4.7 × 10–9
1.7 × 10–9
1.1 × 10–9
2.1 × 10–10
3.0 × 10–9
8.0 × 10–11
3.9 × 10–9
1.2 × 10–10
2.7 × 10–9
5.3 × 10–9
1.1 × 10–10
4.1 × 10–10
1.4 × 10–10

4.1 × 10–11
5.3 × 10–10
1.2 × 10–10
1.4 × 10–10

e(g)12–17 a1.7 × 10–1
4.3 × 10–1
2.3 × 10–9
4.4 × 10–9
1.4 × 10–9
8.7 × 10–10
1.7 × 10–10
2.3 × 10–9
6.3 × 10–11
3.0 × 10–9
8.7 × 10–11
1.9 × 10–9
3.8 × 10–9
7.2 × 10–11
2.8 × 10–10
1.1 × 10–10

3.3 × 10–11
4.2 × 10–10
9.1 × 10–11
1.0 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)242

Cs‑125
Cs‑127

Caesium

I‑120
I‑120m
I‑121
I‑123
I‑124
I‑125
I‑126
I‑128
I‑129
I‑130
I‑131
I‑132
I‑132m
I‑133
I‑134
I‑135

IodineRadionuclidea

0.750 h6.25 h

1.35 h
0.883 h2.12 h13.2 h
4.18 d60.1 d
13.0 d
0.416 h1.57 × 107 a
12.4 h8.04 d2.30 h
1.39 h20.8 h
0.876 h6.61 hPhysicalhalf-life

1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

e(g)

3.9 × 10–10
1.8 × 10–10

3.9 × 10–9
2.3 × 10–9
6.2 × 10–10
2.2 × 10–9
1.2 × 10–7
5.2 × 10–8
2.1 × 10–7
5.7 × 10–10
1.8 × 10–7
2.1 × 10–8
1.8 × 10–7
3.0 × 10–9
2.4 × 10–9
4.9 × 10–8
1.1 × 10–9
1.0 × 10–8

Age ≤ 1 a

1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1 forg>1a2.2 × 10–10
1.2 × 10–10

2.8 × 10–9
1.5 × 10–9
5.3 × 10–10
1.9 × 10–9
1.1 × 10–7
5.7 × 10–8
2.1 × 10–7
3.3 × 10–10
2.2 × 10–7
1.8 × 10–8
1.8 × 10–7
2.4 × 10–9
2.0 × 10–9
4.4 × 10–8
7.5 × 10–10
8.9 × 10–9e(g)Age 1–2 a

1.1 × 10–10
6.6 × 10–11

1.4 × 10–9
7.8 × 10–10
3.1 × 10–10
1.1 × 10–9
6.3 × 10–8
4.1 × 10–8
1.3 × 10–7
1.6 × 10–10
1.7 × 10–7
9.8 × 10–9
1.0 × 10–7
1.3 × 10–9
1.1 × 10–9
2.3 × 10–8
3.9 × 10–10
4.7 × 10–9

e(g)

2–7 a

6.5 × 10–11
4.2 × 10–11

7.2 × 10–10
4.2 × 10–10
1.7 × 10–10
4.9 × 10–10
3.1 × 10–8
3.1 × 10–8
6.8 × 10–8
8.9 × 10–11
1.9 × 10–7
4.6 × 10–9
5.2 × 10–8
6.2 × 10–10
5.0 × 10–10
1.0 × 10–8
2.1 × 10–10
2.2 × 10–9e(g)7–12 a4.4 × 10–11
2.9 × 10–11

4.8 × 10–10
2.9 × 10–10
1.2 × 10–10
3.3 × 10–10
2.0 × 10–8
2.2 × 10–8
4.5 × 10–8
6.0 × 10–11
1.4 × 10–7
3.0 × 10–9
3.4 × 10–8
4.1 × 10–10
3.3 × 10–10
6.8 × 10–9
1.4 × 10–10
1.4 × 10–9e(g)12–17 a3.5 × 10–11
2.4 × 10–11

3.4 × 10–10
2.1 × 10–10
8.2 × 10–11
2.1 × 10–10
1.3 × 10–8
1.5 × 10–8
2.9 × 10–8
4.6 × 10–11
1.1 × 10–7
2.0 × 10–9
2.2 × 10–8
2.9 × 10–10
2.2 × 10–10
4.3 × 10–9
1.1 × 10–10
9.3 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

243

Ba‑126
Ba‑128
Ba‑131
Ba‑131m
Ba‑133
Ba‑133m
Ba‑135m
Ba‑139Ba‑140Bariumf

Cs‑129Cs‑130Cs‑131
Cs‑132
Cs‑134
Cs‑134m
Cs‑135
Cs‑135m
Cs‑136
Cs‑137
Cs‑138

Radionuclidea

1.61 h
2.43 d11.8 d0.243 h10.7 a1.62 d
1.20 d1.38 h12.7 d1.34 d
0.498 h9.69 d6.48 d
2.06 a2.90 h2.30 × 106 a
0.883 h13.1 d30.0 a0.536 hPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600
0.600

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1
4.4 × 10–10
3.3 × 10–10
4.6 × 10–10
2.7 × 10–9
2.6 × 10–8
2.1 × 10–10
4.1 × 10–9
1.3 × 10–10
1.5 × 10–8
2.1 × 10–8
1.1 × 10–9

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

e(g)

2.7 × 10–9
2.0 × 10–8
4.2 × 10–9
5.8 × 10–11
2.2 × 10–8
4.2 × 10–9
3.3 × 10–9
1.4 × 10–9
3.2 × 10–8

f1 forg>1a

Age ≤ 1 a

1.7 × 10–9
1.7 × 10–8
2.6 × 10–9
3.2 × 10–11
6.2 × 10–9
3.6 × 10–9
2.9 × 10–9
8.4 × 10–10
1.8 × 10–8

3.0 × 10–10
1.8 × 10–10
2.9 × 10–10
1.8 × 10–9
1.6 × 10–8
1.2 × 10–10
2.3 × 10–9
8.6 × 10–11
9.5 × 10–9
1.2 × 10–8
5.9 × 10–10e(g)Age 1–2 a

8.5 × 10–10
9.0 × 10–9
1.4 × 10–9
1.6 × 10–11
3.9 × 10–9
1.8 × 10–9
1.5 × 10–9
4.1 × 10–10
9.2 × 10–9

1.7 × 10–10
9.0 × 10–11
1.6 × 10–10
1.1 × 10–9
1.3 × 10–8
5.9 × 10–11
1.7 × 10–9
4.9 × 10–11
6.1 × 10–9
9.6 × 10–9
2.9 × 10–10

e(g)

2–7 a

5.0 × 10–10
5.2 × 10–9
9.4 × 10–10
9.3 × 10–12
4.6 × 10–9
1.1 × 10–9
8.5 × 10–10
2.4 × 10–10
5.8 × 10–9

1.1 × 10–10
5.2 × 10–11
1.0 × 10–10
7.7 × 10–10
1.4 × 10–8
3.5 × 10–11
1.7 × 10–9
3.2 × 10–11
4.4 × 10–9
1.0 × 10–8
1.7 × 10–10

e(g)7–12 a3.1 × 10–10
3.0 × 10–9
6.2 × 10–10
6.3 × 10–12
7.3 × 10–9
5.9 × 10–10
4.7 × 10–10
1.5 × 10–10
3.7 × 10–9

7.2 × 10–11
3.6 × 10–11
6.9 × 10–11
5.7 × 10–10
1.9 × 10–8
2.5 × 10–11
2.0 × 10–9
2.3 × 10–11
3.4 × 10–9
1.3 × 10–8
1.2 × 10–10

e(g)12–17 a2.6 × 10–10
2.7 × 10–9
4.5 × 10–10
4.9 × 10–12
1.5 × 10–9
5.4 × 10–10
4.3 × 10–10
1.2 × 10–10
2.6 × 10–9

6.0 × 10–11
2.8 × 10–11
5.8 × 10–11
5.0 × 10–10
1.9 × 10–8
2.0 × 10–11
2.0 × 10–9
1.9 × 10–11
3.0 × 10–9
1.3 × 10–8
9.2 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

244

0.983 h4.80 h19.5 h6.00 × 104 a
1.35 × 1011 a
1.68 d
3.93 h
1.54 h
0.237 h3.00 d
17.6 h9.00 h
1.43 d138 d32.5 dCeriumCe‑134Ce‑135
Ce‑137
Ce‑137m
Ce‑139Ce‑1410.305 h0.177 hPhysicalhalf-life

La‑131
La‑132
La‑135
La‑137
La‑138
La‑140La‑141
La‑142
La‑143Lanthanum

Ba‑141
Ba‑142

Radionuclidea

0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.600
0.600

f1
7.6 × 10–10
3.6 × 10–10

2.8 × 10–8
7.0 × 10–9
2.6 × 10–10
6.1 × 10–9
2.6 × 10–9
8.1 × 10–9

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.200
0.200

e(g)

3.5 × 10–10
3.8 × 10–9
2.8 × 10–10
1.1 × 10–9
1.3 × 10–8
2.0 × 10–8
4.3 × 10–9
1.9 × 10–9
6.9 × 10–10

f1 forg>1a

Age ≤ 1 a

1.8 × 10–8
4.7 × 10–9
1.7 × 10–10
3.9 × 10–9
1.6 × 10–9
5.1 × 10–9

2.1 × 10–10
2.4 × 10–9
1.9 × 10–10
4.5 × 10–10
4.6 × 10–9
1.3 × 10–8
2.6 × 10–9
1.1 × 10–9
3.9 × 10–10

4.7 × 10–10
2.2 × 10–10e(g)Age 1–2 a

9.1 × 10–9
2.6 × 10–9
8.8 × 10–11
2.0 × 10–9
8.6 × 10–10
2.6 × 10–9

1.1 × 10–10
1.3 × 10–9
1.0 × 10–10
2.5 × 10–10
2.7 × 10–9
6.8 × 10–9
1.3 × 10–9
5.8 × 10–10
1.9 × 10–10

2.3 × 10–10
1.1 × 10–10

e(g)

2–7 a

5.5 × 10–9
1.6 × 10–9
5.4 × 10–11
1.2 × 10–9
5.4 × 10–10
1.5 × 10–9

6.6 × 10–11
7.8 × 10–10
6.4 × 10–11
1.6 × 10–10
1.9 × 10–9
4.2 × 10–9
7.6 × 10–10
3.5 × 10–10
1.1 × 10–10

1.3 × 10–10
6.6 × 10–11

e(g)7–12 a3.2 × 10–9
1.0 × 10–9
3.2 × 10–11
6.8 × 10–10
3.3 × 10–10
8.8 × 10–10

4.4 × 10–11
4.8 × 10–10
3.9 × 10–11
1.0 × 10–10
1.3 × 10–9
2.5 × 10–9
4.5 × 10–10
2.3 × 10–10
7.1 × 10–11

8.6 × 10–11
4.3 × 10–11

e(g)12–17 a2.5 × 10–9
7.9 × 10–10
2.5 × 10–11
5.4 × 10–10
2.6 × 10–10
7.1 × 10–10

3.5 × 10–11
3.9 × 10–10
3.0 × 10–11
8.1 × 10–11
1.1 × 10–9
2.0 × 10–9
3.6 × 10–10
1.8 × 10–10
5.6 × 10–11

7.0 × 10–11
3.5 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

245

1.38 d284 d0.218 h1.28 h2.10 h
4.51 h19.1 h0.243 h13.6 d
0.288 h5.98 h
0.227 h0.844 h5.04 h
0.495 h5.50 h
2.49 h
11.0 dPraseodymium
Pr‑136
Pr‑137
Pr‑138m
Pr‑139Pr‑142
Pr‑142m
Pr‑143
Pr‑144
Pr‑145
Pr‑147

NeodymiumNd‑136
Nd‑138
Nd‑139Nd‑139m
Nd‑141
Nd‑147

Physicalhalf-life

Ce‑143Ce‑144

Radionuclidea

0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005

f1
1.2 × 10–8
6.6 × 10–8

1.0 × 10–9
7.2 × 10–9
2.1 × 10–10
2.1 × 10–9
7.8 × 10–11
1.2 × 10–8

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4

e(g)3.7 × 10–10
4.1 × 10–10
1.0 × 10–9
3.2 × 10–10
1.5 × 10–8
2.0 × 10–10
1.4 × 10–8
6.4 × 10–10
4.7 × 10–9
3.9 × 10–10

f1 forg>1a

Age ≤ 1 a

6.1 × 10–10
4.5 × 10–9
1.2 × 10–10
1.4 × 10–9
5.0 × 10–11
7.8 × 10–9

2.1 × 10–10
2.5 × 10–10
7.4 × 10–10
2.0 × 10–10
9.8 × 10–9
1.2 × 10–10
8.7 × 10–9
3.5 × 10–10
2.9 × 10–9
2.2 × 10–10

8.0 × 10–9
3.9 × 10–8e(g)Age 1–2 a

3.1 × 10–10
2.3 × 10–9
6.3 × 10–11
7.8 × 10–10
2.7 × 10–11
3.9 × 10–9

1.0 × 10–10
1.3 × 10–10
4.1 × 10–10
1.1 × 10–10
4.9 × 10–9
6.2 × 10–11
4.3 × 10–9
1.7 × 10–10
1.4 × 10–9
1.1 × 10–10

4.1 × 10–9
1.9 × 10–8

e(g)

2–7 a

1.9 × 10–10
1.3 × 10–9
3.7 × 10–11
5.0 × 10–10
1.6 × 10–11
2.3 × 10–9

6.1 × 10–11
7.7 × 10–11
2.6 × 10–10
6.5 × 10–11
2.9 × 10–9
3.7 × 10–11
2.6 × 10–9
9.5 × 10–11
8.5 × 10–10
6.1 × 10–11

2.4 × 10–9
1.1 × 10–8

e(g)7–12 a

1.2 × 10–10
8.0 × 10–10
2.5 × 10–11
3.1 × 10–10
1.0 × 10–11
1.3 × 10–9

4.2 × 10–11
5.0 × 10–11
1.6 × 10–10
4.0 × 10–11
1.6 × 10–9
2.1 × 10–11
1.5 × 10–9
6.5 × 10–11
4.9 × 10–10
4.2 × 10–11

1.4 × 10–9
6.5 × 10–9e(g)12–17 a9.9 × 10–11
6.4 × 10–10
2.0 × 10–11
2.5 × 10–10
8.3 × 10–12
1.1 × 10–9

3.3 × 10–11
4.0 × 10–11
1.3 × 10–10
3.1 × 10–11
1.3 × 10–9
1.7 × 10–11
1.2 × 10–9
5.0 × 10–11
3.9 × 10–10
3.3 × 10–11

1.1 × 10–9
5.2 × 10–9

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

246

Sm‑141
Sm‑141m
Sm‑142
Sm‑145
Sm‑146

SamariumPm‑141
Pm‑143Pm‑144Pm‑145
Pm‑146
Pm‑147
Pm‑148Pm‑148m
Pm‑149Pm‑150Pm‑151

Promethium

Nd‑149Nd‑151

Radionuclidea

0.170 h0.377 h1.21 h340 d1.03 × 108 a

0.348 h265 d
363 d
17.7 a5.53 a2.62 a5.37 d41.3 d
2.21 d
2.68 h
1.18 d1.73 h
0.207 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005

f1
1.4 × 10–9
3.4 × 10–10

4.5 × 10–10
7.0 × 10–10
2.2 × 10–9
2.4 × 10–9
1.5 × 10–6

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4e(g)4.2 × 10–10
1.9 × 10–9
7.6 × 10–9
1.5 × 10–9
1.0 × 10–8
3.6 × 10–9
3.0 × 10–8
1.5 × 10–8
1.2 × 10–8
2.8 × 10–9
8.0 × 10–9

f1 forg>1a

Age ≤ 1 a

2.5 × 10–10
4.0 × 10–10
1.3 × 10–9
1.4 × 10–9
1.5 × 10–7

2.4 × 10–10
1.2 × 10–9
4.7 × 10–9
6.8 × 10–10
5.1 × 10–9
1.9 × 10–9
1.9 × 10–8
1.0 × 10–8
7.4 × 10–9
1.7 × 10–9
5.1 × 10–9

8.7 × 10–10
2.0 × 10–10e(g)Age 1–2 a

1.3 × 10–10
2.0 × 10–10
6.2 × 10–10
7.3 × 10–10
1.0 × 10–7

1.2 × 10–10
6.7 × 10–10
2.7 × 10–9
3.7 × 10–10
2.8 × 10–9
9.6 × 10–10
9.7 × 10–9
5.5 × 10–9
3.7 × 10–9
8.7 × 10–10
2.6 × 10–9

4.3 × 10–10
9.7 × 10–11

e(g)

2–7 a

7.3 × 10–11
1.2 × 10–10
3.6 × 10–10
4.5 × 10–10
7.0 × 10–8

6.8 × 10–11
4.4 × 10–10
1.8 × 10–9
2.3 × 10–10
1.8 × 10–9
5.7 × 10–10
5.8 × 10–9
3.5 × 10–9
2.2 × 10–9
5.2 × 10–10
1.6 × 10–9

2.6 × 10–10
5.7 × 10–11

e(g)7–12 a5.0 × 10–11
8.2 × 10–11
2.4 × 10–10
2.7 × 10–10
5.8 × 10–8

4.6 × 10–11
2.9 × 10–10
1.2 × 10–9
1.4 × 10–10
1.1 × 10–9
3.2 × 10–10
3.3 × 10–9
2.2 × 10–9
1.2 × 10–9
3.2 × 10–10
9.1 × 10–10

1.6 × 10–10
3.8 × 10–11

e(g)12–17 a3.9 × 10–11
6.5 × 10–11
1.9 × 10–10
2.1 × 10–10
5.4 × 10–8

3.6 × 10–11
2.3 × 10–10
9.7 × 10–10
1.1 × 10–10
9.0 × 10–10
2.6 × 10–10
2.7 × 10–9
1.7 × 10–9
9.9 × 10–10
2.6 × 10–10
7.3 × 10–10

1.2 × 10–10
3.0 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

247

Eu‑145
Eu‑146
Eu‑147
Eu‑148
Eu‑149Eu‑150Eu‑150m
Eu‑152
Eu‑152m
Eu‑154Eu‑155
Eu‑156
Eu‑157
Eu‑158Europium

Sm‑147
Sm‑151
Sm‑153
Sm‑155
Sm‑156

Radionuclidea

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

1.06 × 1011 a
90.0 a1.95 d
0.368 h9.40 h

5.94 d
4.61 d24.0 d54.5 d93.1 d34.2 a12.6 h13.3 a9.32 h8.80 a4.96 a15.2 d15.1 h
0.765 hf1

Physicalhalf-lifee(g)5.1 × 10–9
8.5 × 10–9
3.7 × 10–9
8.5 × 10–9
9.7 × 10–10
1.3 × 10–8
4.4 × 10–9
1.6 × 10–8
5.7 × 10–9
2.5 × 10–8
4.3 × 10–9
2.2 × 10–8
6.7 × 10–9
1.1 × 10–9

1.4 × 10–6
1.5 × 10–9
8.4 × 10–9
3.6 × 10–10
2.8 × 10–9

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

3.7 × 10–9
6.2 × 10–9
2.5 × 10–9
6.0 × 10–9
6.3 × 10–10
5.7 × 10–9
2.8 × 10–9
7.4 × 10–9
3.6 × 10–9
1.2 × 10–8
2.2 × 10–9
1.5 × 10–8
4.3 × 10–9
6.2 × 10–10

1.4 × 10–7
6.4 × 10–10
5.4 × 10–9
2.0 × 10–10
1.8 × 10–9e(g)Age 1–2 a

2.1 × 10–9
3.6 × 10–9
1.4 × 10–9
3.5 × 10–9
3.4 × 10–10
3.4 × 10–9
1.4 × 10–9
4.1 × 10–9
1.8 × 10–9
6.5 × 10–9
1.1 × 10–9
7.5 × 10–9
2.2 × 10–9
3.1 × 10–10

9.2 × 10–8
3.3 × 10–10
2.7 × 10–9
9.7 × 10–11
9.0 × 10–10

e(g)

2–7 a

1.4 × 10–9
2.4 × 10–9
8.9 × 10–10
2.4 × 10–9
2.1 × 10–10
2.3 × 10–9
8.2 × 10–10
2.6 × 10–9
1.1 × 10–9
4.1 × 10–9
6.8 × 10–10
4.6 × 10–9
1.3 × 10–9
1.8 × 10–10

6.4 × 10–8
2.0 × 10–10
1.6 × 10–9
5.5 × 10–11
5.4 × 10–10

e(g)7–12 a9.4 × 10–10
1.6 × 10–9
5.6 × 10–10
1.6 × 10–9
1.3 × 10–10
1.5 × 10–9
4.7 × 10–10
1.7 × 10–9
6.2 × 10–10
2.5 × 10–9
4.0 × 10–10
2.7 × 10–9
7.5 × 10–10
1.2 × 10–10

5.2 × 10–8
1.2 × 10–10
9.2 × 10–10
3.7 × 10–11
3.1 × 10–10

e(g)12–17 a7.5 × 10–10
1.3 × 10–9
4.4 × 10–10
1.3 × 10–9
1.0 × 10–10
1.3 × 10–9
3.8 × 10–10
1.4 × 10–9
5.0 × 10–10
2.0 × 10–9
3.2 × 10–10
2.2 × 10–9
6.0 × 10–10
9.4 × 10–11

4.9 × 10–8
9.8 × 10–11
7.4 × 10–10
2.9 × 10–11
2.5 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

248

Tb‑147
Tb‑149Tb‑150Tb‑151
Tb‑153
Tb‑154
Tb‑155
Tb‑156
Tb‑156m

Terbium

Gd‑145
Gd‑146
Gd‑147
Gd‑148
Gd‑149Gd‑151
Gd‑152
Gd‑153
Gd‑159GadoliniumRadionuclidea

1.65 h4.15 h3.27 h
17.6 h2.34 d
21.4 h5.32 d5.34 d
1.02 d

0.382 h48.3 d
1.59 d93.0 a9.40 d120 d1.08 × 1014 a
242 d
18.6 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

e(g)

1.5 × 10–9
2.4 × 10–9
2.5 × 10–9
2.7 × 10–9
2.3 × 10–9
4.7 × 10–9
1.9 × 10–9
9.0 × 10–9
1.5 × 10–9

4.5 × 10–10
9.4 × 10–9
4.5 × 10–9
1.7 × 10–6
4.0 × 10–9
2.1 × 10–9
1.2 × 10–6
2.9 × 10–9
5.7 × 10–9

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

1.0 × 10–9
1.5 × 10–9
1.6 × 10–9
1.9 × 10–9
1.5 × 10–9
3.4 × 10–9
1.3 × 10–9
6.3 × 10–9
1.0 × 10–9

2.6 × 10–10
6.0 × 10–9
3.2 × 10–9
1.6 × 10–7
2.7 × 10–9
1.3 × 10–9
1.2 × 10–7
1.8 × 10–9
3.6 × 10–9e(g)Age 1–2 a

5.4 × 10–10
8.0 × 10–10
8.3 × 10–10
1.0 × 10–9
8.2 × 10–10
1.9 × 10–9
6.8 × 10–10
3.5 × 10–9
5.6 × 10–10

1.3 × 10–10
3.2 × 10–9
1.8 × 10–9
1.1 × 10–7
1.5 × 10–9
6.8 × 10–10
7.7 × 10–8
9.4 × 10–10
1.8 × 10–9

e(g)

2–7 a

3.3 × 10–10
5.0 × 10–10
5.1 × 10–10
6.7 × 10–10
5.1 × 10–10
1.3 × 10–9
4.3 × 10–10
2.3 × 10–9
3.5 × 10–10

8.1 × 10–11
2.0 × 10–9
1.2 × 10–9
7.3 × 10–8
9.3 × 10–10
4.2 × 10–10
5.3 × 10–8
5.8 × 10–10
1.1 × 10–9e(g)7–12 a2.0 × 10–10
3.1 × 10–10
3.2 × 10–10
4.2 × 10–10
3.1 × 10–10
8.1 × 10–10
2.6 × 10–10
1.5 × 10–9
2.2 × 10–10

5.6 × 10–11
1.2 × 10–9
7.7 × 10–10
5.9 × 10–8
5.7 × 10–10
2.4 × 10–10
4.3 × 10–8
3.4 × 10–10
6.2 × 10–10

e(g)12–17 a1.6 × 10–10
2.5 × 10–10
2.5 × 10–10
3.4 × 10–10
2.5 × 10–10
6.5 × 10–10
2.1 × 10–10
1.2 × 10–9
1.7 × 10–10

4.4 × 10–11
9.6 × 10–10
6.1 × 10–10
5.6 × 10–8
4.5 × 10–10
2.0 × 10–10
4.1 × 10–8
2.7 × 10–10
4.9 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)249

Ho‑155
Ho‑157
Ho‑159Ho‑161
Ho‑162
Ho‑162m
Ho‑164
Ho‑164m

Holmium

Dy‑155
Dy‑157
Dy‑159Dy‑165
Dy‑166

Dysprosium

Tb‑156mʹ
Tb‑157
Tb‑158
Tb‑160Tb‑161

Radionuclidea

0.800 h0.210 h0.550 h2.50 h
0.250 h1.13 h
0.483 h0.625 h10.0 h8.10 h144 d2.33 h
3.40 d

5.00 h
1.50 × 102 a
1.50 × 102 a
72.3 d
6.91 dPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

f1
8.0 × 10–10
4.9 × 10–10
1.3 × 10–8
1.6 × 10–8
8.3 × 10–9

3.8 × 10–10
5.8 × 10–11
7.1 × 10–11
1.4 × 10–10
3.5 × 10–11
2.4 × 10–10
1.2 × 10–10
2.0 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)9.7 × 10–10
4.4 × 10–10
1.0 × 10–9
1.3 × 10–9
1.9 × 10–8

f1 forg>1a

Age ≤ 1 a

2.3 × 10–10
3.6 × 10–11
4.3 × 10–11
8.1 × 10–11
2.0 × 10–11
1.5 × 10–10
6.5 × 10–11
1.1 × 10–10

6.8 × 10–10
3.1 × 10–10
6.4 × 10–10
7.9 × 10–10
1.2 × 10–8

5.2 × 10–10
2.2 × 10–10
5.9 × 10–9
1.0 × 10–8
5.3 × 10–9e(g)Age 1–2 a

1.2 × 10–10
1.9 × 10–11
2.3 × 10–11
4.2 × 10–11
1.0 × 10–11
7.9 × 10–11
3.2 × 10–11
5.5 × 10–11

3.8 × 10–10
1.8 × 10–10
3.4 × 10–10
3.9 × 10–10
6.0 × 10–9

2.7 × 10–10
1.1 × 10–10
3.3 × 10–9
5.4 × 10–9
2.7 × 10–9

e(g)

2–7 a

7.1 × 10–11
1.2 × 10–11
1.4 × 10–11
2.5 × 10–11
6.0 × 10–12
4.9 × 10–11
1.8 × 10–11
3.2 × 10–11

2.5 × 10–10
1.2 × 10–10
2.1 × 10–10
2.3 × 10–10
3.6 × 10–9

1.7 × 10–10
6.8 × 10–11
2.1 × 10–9
3.3 × 10–9
1.6 × 10–9e(g)7–12 a4.7 × 10–11
8.1 × 10–12
9.9 × 10–12
1.6 × 10–11
4.2 × 10–12
3.3 × 10–11
1.2 × 10–11
2.1 × 10–11

1.6 × 10–10
7.7 × 10–11
1.3 × 10–10
1.4 × 10–10
2.0 × 10–9

1.0 × 10–10
4.1 × 10–11
1.4 × 10–9
2.0 × 10–9
9.0 × 10–10

e(g)12–17 a3.7 × 10–11
6.5 × 10–12
7.9 × 10–12
1.3 × 10–11
3.3 × 10–12
2.6 × 10–11
9.5 × 10–12
1.6 × 10–11

1.3 × 10–10
6.1 × 10–11
1.0 × 10–10
1.1 × 10–10
1.6 × 10–9

8.1 × 10–11
3.4 × 10–11
1.1 × 10–9
1.6 × 10–9
7.2 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

250

Tm‑162
Tm‑166
Tm‑167
Tm‑170Tm‑171
Tm‑172
Tm‑173
Tm‑175

Thulium

Er‑161Er‑165
Er‑169Er‑171
Er‑172

Erbium

Ho‑166
Ho‑166m
Ho‑167

Radionuclidea

0.362 h7.70 h
9.24 d129 d1.92 a2.65 d8.24 h
0.253 h3.24 h10.4 h
9.30 d7.52 h2.05 d

1.12 d
1.20 × 103 a
3.10 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005

f1
1.6 × 10–8
2.6 × 10–8
8.8 × 10–10

2.9 × 10–10
2.1 × 10–9
6.0 × 10–9
1.6 × 10–8
1.5 × 10–9
1.9 × 10–8
3.3 × 10–9
3.1 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)6.5 × 10–10
1.7 × 10–10
4.4 × 10–9
4.0 × 10–9
1.0 × 10–8

f1 forg>1a

Age ≤ 1 a

1.7 × 10–10
1.5 × 10–9
3.9 × 10–9
9.8 × 10–9
7.8 × 10–10
1.2 × 10–8
2.1 × 10–9
1.7 × 10–10

4.4 × 10–10
1.1 × 10–10
2.8 × 10–9
2.5 × 10–9
6.8 × 10–9

1.0 × 10–8
9.3 × 10–9
5.5 × 10–10e(g)Age 1–2 a

8.7 × 10–11
8.3 × 10–10
2.0 × 10–9
4.9 × 10–9
3.9 × 10–10
6.1 × 10–9
1.1 × 10–9
8.6 × 10–11

2.4 × 10–10
6.2 × 10–11
1.4 × 10–9
1.3 × 10–9
3.5 × 10–9

5.2 × 10–9
5.3 × 10–9
2.8 × 10–10

e(g)

2–7 a

5.2 × 10–11
5.5 × 10–10
1.2 × 10–9
2.9 × 10–9
2.3 × 10–10
3.7 × 10–9
6.5 × 10–10
5.0 × 10–11

1.6 × 10–10
3.9 × 10–11
8.2 × 10–10
7.6 × 10–10
2.1 × 10–9

3.1 × 10–9
3.5 × 10–9
1.7 × 10–10

e(g)7–12 a3.6 × 10–11
3.5 × 10–10
7.0 × 10–10
1.6 × 10–9
1.3 × 10–10
2.1 × 10–9
3.8 × 10–10
3.4 × 10–11

1.0 × 10–10
2.4 × 10–11
4.7 × 10–10
4.5 × 10–10
1.3 × 10–9

1.7 × 10–9
2.4 × 10–9
1.0 × 10–10

e(g)12–17 a2.9 × 10–11
2.8 × 10–10
5.6 × 10–10
1.3 × 10–9
1.1 × 10–10
1.7 × 10–9
3.1 × 10–10
2.7 × 10–11

8.0 × 10–11
1.9 × 10–11
3.7 × 10–10
3.6 × 10–10
1.0 × 10–9

1.4 × 10–9
2.0 × 10–9
8.3 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

251

Lu‑169Lu‑170Lu‑171
Lu‑172
Lu‑173
Lu‑174
Lu‑174m
Lu‑176
Lu‑176m
Lu‑177
Lu‑177m

LutetiumYb‑162
Yb‑166
Yb‑167
Yb‑169
Yb‑175
Yb‑177
Yb‑178

Ytterbium

Radionuclidea

1.42 d2.00 d8.22 d6.70 d1.37 a3.31 a142 d3.60 × 1010 a
3.68 h
6.71 d161 d0.315 h2.36 d
0.292 h32.0 d
4.19 d
1.90 h1.23 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

e(g)

3.5 × 10–9
7.4 × 10–9
5.9 × 10–9
1.0 × 10–8
2.7 × 10–9
3.2 × 10–9
6.2 × 10–9
2.4 × 10–8
2.0 × 10–9
6.1 × 10–9
1.7 × 10–8

2.2 × 10–10
7.7 × 10–9
7.0 × 10–11
7.1 × 10–9
5.0 × 10–9
1.0 × 10–9
1.4 × 10–9

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a2.4 × 10–9
5.2 × 10–9
4.0 × 10–9
7.0 × 10–9
1.6 × 10–9
1.7 × 10–9
3.8 × 10–9
1.1 × 10–8
1.2 × 10–9
3.9 × 10–9
1.1 × 10–8

1.3 × 10–10
5.4 × 10–9
4.1 × 10–11
4.6 × 10–9
3.2 × 10–9
6.8 × 10–10
8.4 × 10–10e(g)Age 1–2 a

1.4 × 10–9
2.9 × 10–9
2.2 × 10–9
3.9 × 10–9
8.6 × 10–10
9.1 × 10–10
1.9 × 10–9
5.7 × 10–9
6.0 × 10–10
2.0 × 10–9
5.8 × 10–9

6.9 × 10–11
2.9 × 10–9
2.1 × 10–11
2.4 × 10–9
1.6 × 10–9
3.4 × 10–10
4.2 × 10–10

e(g)

2–7 a

8.9 × 10–10
1.9 × 10–9
1.4 × 10–9
2.5 × 10–9
5.3 × 10–10
5.6 × 10–10
1.1 × 10–9
3.5 × 10–9
3.5 × 10–10
1.2 × 10–9
3.6 × 10–9

4.2 × 10–11
1.9 × 10–9
1.2 × 10–11
1.5 × 10–9
9.5 × 10–10
2.0 × 10–10
2.4 × 10–10

e(g)7–12 a5.7 × 10–10
1.2 × 10–9
8.5 × 10–10
1.6 × 10–9
3.2 × 10–10
3.3 × 10–10
6.6 × 10–10
2.2 × 10–9
2.1 × 10–10
6.6 × 10–10
2.1 × 10–9

2.9 × 10–11
1.2 × 10–9
8.4 × 10–12
8.8 × 10–10
5.4 × 10–10
1.1 × 10–10
1.5 × 10–10

e(g)12–17 a4.6 × 10–10
9.9 × 10–10
6.7 × 10–10
1.3 × 10–9
2.6 × 10–1
2.7 × 10–10
5.3 × 10–10
1.8 × 10–9
1.7 × 10–10
5.3 × 10–10
1.7 × 10–9

2.3 × 10–11
9.5 × 10–10
6.7 × 10–12
7.1 × 10–10
4.4 × 10–10
8.8 × 10–11
1.2 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

252

Ta‑172
Ta‑173

Tantalum

Hf‑170
Hf‑172
Hf‑173
Hf‑175
Hf‑177m
Hf‑178m
Hf‑179m
Hf‑180m
Hf‑181
Hf‑182
Hf‑182m
Hf‑183
Hf‑184

Hafnium

Lu‑178
Lu‑178m
Lu‑179Radionuclidea

0.613 h3.65 h

16.0 h
1.87 a24.0 h
70.0 d
0.856 h31.0 a25.1 d5.50 h42.4 d
9.00 × 106 a
1.02 h1.07 h4.12 h

0.473 h0.378 h4.59 hPhysicalhalf-life

0.010
0.010

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.005
0.005
0.005

f1
5.9 × 10–10
4.3 × 10–10
2.4 × 10–9

5.5 × 10–10
2.0 × 10–9

0.001
0.001

0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)3.9 × 10–9
1.9 × 10–8
1.9 × 10–9
3.8 × 10–9
7.8 × 10–10
7.0 × 10–8
1.2 × 10–8
1.4 × 10–9
1.2 × 10–8
5.6 × 10–8
4.1 × 10–10
8.1 × 10–10
5.5 × 10–9

f1 forg>1a

Age ≤ 1 a

3.2 × 10–10
1.3 × 10–9

2.7 × 10–9
6.1 × 10–9
1.3 × 10–9
2.4 × 10–9
4.7 × 10–10
1.9 × 10–8
7.8 × 10–9
9.7 × 10–10
7.4 × 10–9
7.9 × 10–9
2.5 × 10–10
4.8 × 10–10
3.6 × 10–9

3.3 × 10–10
2.4 × 10–10
1.5 × 10–9e(g)Age 1–2 a

1.6 × 10–10
6.5 × 10–10

1.5 × 10–9
3.3 × 10–9
7.2 × 10–10
1.3 × 10–9
2.5 × 10–10
1.1 × 10–8
4.1 × 10–9
5.3 × 10–10
3.8 × 10–9
5.4 × 10–9
1.3 × 10–10
2.4 × 10–10
1.8 × 10–9

1.6 × 10–10
1.2 × 10–10
7.5 × 10–10

e(g)

2–7 a

9.8 × 10–11
3.9 × 10–10

9.5 × 10–10
2.0 × 10–9
4.6 × 10–10
8.4 × 10–10
1.5 × 10–10
7.8 × 10–9
2.6 × 10–9
3.3 × 10–10
2.3 × 10–9
4.0 × 10–9
7.8 × 10–11
1.4 × 10–10
1.1 × 10–9

9.0 × 10–11
7.1 × 10–11
4.4 × 10–10

e(g)7–12 a6.6 × 10–11
2.4 × 10–10

6.0 × 10–10
1.3 × 10–9
2.8 × 10–10
5.2 × 10–10
1.0 × 10–10
5.5 × 10–9
1.6 × 10–9
2.1 × 10–10
1.4 × 10–9
3.3 × 10–9
5.2 × 10–11
9.3 × 10–11
6.6 × 10–10

6.1 × 10–11
4.9 × 10–11
2.6 × 10–10

e(g)12–17 a5.3 × 10–11
1.9 × 10–10

4.8 × 10–10
1.0 × 10–9
2.3 × 10–10
4.1 × 10–10
8.1 × 10–11
4.7 × 10–9
1.2 × 10–9
1.7 × 10–10
1.1 × 10–9
3.0 × 10–9
4.2 × 10–11
7.3 × 10–11
5.2 × 10–10

4.7 × 10–11
3.8 × 10–11
2.1 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

253

W‑176
W‑177
W‑178
W‑179
W‑181
W‑185

Tungsten

Ta‑174
Ta‑175
Ta‑176
Ta‑177
Ta‑178
Ta‑179Ta‑180Ta‑180m
Ta‑182
Ta‑182m
Ta‑183
Ta‑184
Ta‑185
Ta‑186

Radionuclidea

2.30 h2.25 h21.7 d
0.625 h121 d75.1 d

1.20 h10.5 h8.08 h2.36 d
2.20 h1.82 a1.00 × 1013 a
8.10 h115 d0.264 h5.10 d8.70 h
0.816 h0.175 hPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1
6.2 × 10–10
1.6 × 10–9
2.4 × 10–9
1.0 × 10–9
6.3 × 10–10
6.2 × 10–10
8.1 × 10–9
5.8 × 10–10
1.4 × 10–8
1.4 × 10–10
1.4 × 10–8
6.7 × 10–9
8.3 × 10–10
3.8 × 10–10

0.300
0.300
0.300
0.300
0.300
0.300

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

e(g)

6.8 × 10–10
4.4 × 10–10
1.8 × 10–9
3.4 × 10–11
6.3 × 10–10
4.4 × 10–9

f1 forg>1a

Age ≤ 1 a

5.5 × 10–10
3.2 × 10–10
1.4 × 10–9
2.0 × 10–11
4.7 × 10–10
3.3 × 10–9

3.7 × 10–10
1.1 × 10–9
1.7 × 10–9
6.9 × 10–10
4.5 × 10–10
4.1 × 10–10
5.3 × 10–9
3.7 × 10–10
9.4 × 10–9
7.5 × 10–11
9.3 × 10–9
4.4 × 10–9
4.6 × 10–10
2.1 × 10–10e(g)Age 1–2 a

3.0 × 10–10
1.7 × 10–10
7.3 × 10–10
1.0 × 10–11
2.5 × 10–10
1.6 × 10–9

1.9 × 10–10
6.2 × 10–10
9.2 × 10–10
3.6 × 10–10
2.4 × 10–10
2.2 × 10–10
2.8 × 10–9
1.9 × 10–10
5.0 × 10–9
3.7 × 10–11
4.7 × 10–9
2.3 × 10–9
2.3 × 10–10
1.1 × 10–10

e(g)

2–7 a

2.0 × 10–10
1.1 × 10–10
4.5 × 10–10
6.2 × 10–12
1.6 × 10–10
9.7 × 10–10

1.1 × 10–10
4.0 × 10–10
6.1 × 10–10
2.2 × 10–10
1.5 × 10–10
1.3 × 10–10
1.7 × 10–9
1.1 × 10–10
3.1 × 10–9
2.1 × 10–11
2.8 × 10–9
1.4 × 10–9
1.3 × 10–10
6.1 × 10–11

e(g)7–12 a1.3 × 10–10
7.2 × 10–11
2.7 × 10–10
4.2 × 10–12
9.5 × 10–11
5.5 × 10–10

7.2 × 10–11
2.6 × 10–10
3.9 × 10–10
1.3 × 10–10
9.1 × 10–11
8.1 × 10–11
1.1 × 10–9
6.7 × 10–11
1.9 × 10–9
1.5 × 10–11
1.6 × 10–9
8.5 × 10–10
8.6 × 10–11
4.2 × 10–11

e(g)12–17 a1.0 × 10–10
5.8 × 10–11
2.2 × 10–10
3.3 × 10–12
7.6 × 10–11
4.4 × 10–10

5.7 × 10–11
2.1 × 10–10
3.1 × 10–10
1.1 × 10–10
7.2 × 10–11
6.5 × 10–11
8.4 × 10–10
5.4 × 10–11
1.5 × 10–9
1.2 × 10–11
1.3 × 10–9
6.8 × 10–10
6.8 × 10–11
3.3 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

254

Os‑180Os‑181
Os‑182

OsmiumRe‑177
Re‑178
Re‑181
Re‑182
Re‑182
Re‑184
Re‑184m
Re‑186
Re‑186m
Re‑187
Re‑188
Re‑188m
Re‑189Rhenium

W‑187
W‑188

Radionuclidea

0.366 h1.75 h
22.0 h

0.233 h0.220 h20.0 h
2.67 d12.7 h
38.0 d165 d3.78 d2.00 × 105 a
5.00 × 1010 a
17.0 h
0.310 h1.01 d23.9 h69.4 dPhysicalhalf-life

0.020
0.020
0.020

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.600
0.600

f1
5.5 × 10–9
2.1 × 10–8

1.6 × 10–10
7.6 × 10–10
4.6 × 10–9

0.010
0.010
0.010

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

0.300
0.300

e(g)

2.5 × 10–10
2.9 × 10–10
4.2 × 10–9
1.4 × 10–8
2.4 × 10–9
8.9 × 10–9
1.7 × 10–8
1.9 × 10–8
3.0 × 10–8
6.8 × 10–11
1.7 × 10–8
3.8 × 10–10
9.8 × 10–9

f1 forg>1a

Age ≤ 1 a

9.8 × 10–11
5.0 × 10–10
3.2 × 10–9

1.4 × 10–10
1.6 × 10–10
2.8 × 10–9
8.9 × 10–9
1.7 × 10–9
5.6 × 10–9
9.8 × 10–9
1.1 × 10–8
1.6 × 10–8
3.8 × 10–11
1.1 × 10–8
2.3 × 10–10
6.2 × 10–9

4.3 × 10–9
1.5 × 10–8e(g)Age 1–2 a

5.1 × 10–11
2.7 × 10–10
1.7 × 10–9

7.2 × 10–11
7.9 × 10–11
1.4 × 10–9
4.7 × 10–9
8.9 × 10–10
3.0 × 10–9
4.9 × 10–9
5.5 × 10–9
7.6 × 10–9
1.8 × 10–11
5.4 × 10–9
1.1 × 10–10
3.0 × 10–9

2.2 × 10–9
7.7 × 10–9

e(g)

2–7 a

3.2 × 10–11
1.7 × 10–10
1.1 × 10–9

4.1 × 10–11
4.6 × 10–11
8.2 × 10–10
2.8 × 10–9
5.2 × 10–10
1.8 × 10–9
2.8 × 10–9
3.0 × 10–9
4.4 × 10–9
1.0 × 10–11
2.9 × 10–9
6.1 × 10–11
1.6 × 10–9

1.3 × 10–9
4.6 × 10–9e(g)7–12 a2.2 × 10–11
1.1 × 10–10
7.0 × 10–10

2.8 × 10–11
3.1 × 10–11
5.4 × 10–10
1.8 × 10–9
3.5 × 10–10
1.3 × 10–9
1.9 × 10–9
1.9 × 10–9
2.8 × 10–9
6.6 × 10–12
1.8 × 10–9
4.0 × 10–11
1.0 × 10–9

7.8 × 10–10
2.6 × 10–9e(g)12–17 a1.7 × 10–11
8.9 × 10–1
5.6 × 10–10

2.2 × 10–11
2.5 × 10–11
4.2 × 10–10
1.4 × 10–9
2.7 × 10–1
1.0 × 10–9
1.5 × 10–9
1.5 × 10–9
2.2 × 10–9
5.1 × 10–12
1.4 × 10–9
3.0 × 10–11
7.8 × 10–10

6.3 × 10–10
2.1 × 10–9

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

255

Ir‑182
Ir‑184
Ir‑185
Ir‑186
Ir‑186m
Ir‑187
Ir‑188
Ir‑189Ir‑190Ir‑190m
Ir‑190mʹ
Ir‑192
Ir‑192m
Ir‑193m

Iridium

Os‑185
Os‑189m
Os‑191
Os‑191m
Os‑193
Os‑194

Radionuclidea

0.250 h3.02 h
14.0 h15.8 h
1.75 h10.5 h1.73 d13.3 d12.1 d
3.10 h1.20 h
74.0 d
2.41 × 102 a
11.9 d94.0 d
6.00 h
15.4 d
13.0 h1.25 d
6.00 aPhysicalhalf-life

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020

f1
3.8 × 10–9
2.1 × 10–10
6.3 × 10–9
1.1 × 10–9
9.3 × 10–9
2.9 × 10–8

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010

e(g)

5.3 × 10–10
1.5 × 10–9
2.4 × 10–9
3.8 × 10–9
5.8 × 10–10
1.1 × 10–9
4.6 × 10–9
2.5 × 10–9
1.0 × 10–8
9.4 × 10–10
7.9 × 10–11
1.3 × 10–8
2.8 × 10–9
3.2 × 10–9

f1 forg>1a

Age ≤ 1 a

3.0 × 10–10
9.7 × 10–10
1.6 × 10–9
2.7 × 10–9
3.6 × 10–10
7.3 × 10–10
3.3 × 10–9
1.7 × 10–9
7.1 × 10–9
6.4 × 10–10
5.0 × 10–11
8.7 × 10–9
1.4 × 10–9
2.0 × 10–9

2.6 × 10–9
1.3 × 10–10
4.1 × 10–9
7.1 × 10–10
6.0 × 10–9
1.7 × 10–8e(g)Age 1–2 a

1.5 × 10–10
5.2 × 10–10
8.6 × 10–10
1.5 × 10–9
2.1 × 10–10
3.9 × 10–10
1.8 × 10–9
8.6 × 10–10
3.9 × 10–9
3.5 × 10–10
2.6 × 10–11
4.6 × 10–9
8.3 × 10–10
1.0 × 10–9

1.5 × 10–9
6.5 × 10–11
2.1 × 10–9
3.5 × 10–10
3.0 × 10–9
8.8 × 10–9

e(g)

2–7 a

8.9 × 10–11
3.3 × 10–10
5.3 × 10–10
9.6 × 10–10
1.3 × 10–10
2.5 × 10–10
1.2 × 10–9
5.2 × 10–10
2.5 × 10–9
2.3 × 10–10
1.6 × 10–11
2.8 × 10–9
5.5 × 10–10
6.0 × 10–10

9.8 × 10–10
3.8 × 10–11
1.2 × 10–9
2.1 × 10–10
1.8 × 10–9
5.2 × 10–9e(g)7–12 a6.0 × 10–11
2.1 × 10–10
3.3 × 10–10
6.1 × 10–10
7.7 × 10–11
1.5 × 10–10
7.9 × 10–10
3.0 × 10–10
1.6 × 10–9
1.5 × 10–10
1.0 × 10–11
1.7 × 10–9
3.7 × 10–10
3.4 × 10–10

6.5 × 10–10
2.2 × 10–11
7.0 × 10–10
1.2 × 10–10
1.0 × 10–9
3.0 × 10–9e(g)12–17 a4.8 × 10–11
1.7 × 10–10
2.6 × 10–10
4.9 × 10–10
6.1 × 10–11
1.2 × 10–10
6.3 × 10–10
2.4 × 10–10
1.2 × 10–9
1.2 × 10–10
8.0 × 10–12
1.4 × 10–9
3.1 × 10–10
2.7 × 10–1

5.1 × 10–10
1.8 × 10–11
5.7 × 10–10
9.6 × 10–11
8.1 × 10–10
2.4 × 10–9

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

256

Au‑193
Au‑194
Au‑195Gold

Pt‑186
Pt‑188Pt‑189Pt‑191
Pt‑193
Pt‑193m
Pt‑195m
Pt‑197
Pt‑197m
Pt‑199Pt‑200

PlatinumIr‑194
Ir‑194m
Ir‑195
Ir‑195m

Radionuclidea

17.6 h
1.65 d183 d2.00 h10.2 d10.9 h2.80 d50.0 a4.33 d
4.02 d18.3 h
1.57 h
0.513 h12.5 h19.1 h
171 d2.50 h3.80 hPhysicalhalf-life

0.200
0.200
0.200

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020

f1
1.5 × 10–8
1.7 × 10–8
1.2 × 10–9
2.3 × 10–9

1.2 × 10–9
2.9 × 10–9
2.4 × 10–9

0.100
0.100
0.100

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010
0.010

e(g)

7.8 × 10–10
6.7 × 10–9
1.1 × 10–9
3.1 × 10–9
3.7 × 10–10
5.2 × 10–9
7.1 × 10–9
4.7 × 10–9
1.0 × 10–9
4.7 × 10–10
1.4 × 10–8

f1 forg>1a

Age ≤ 1 a

8.8 × 10–10
2.2 × 10–9
1.7 × 10–9

5.3 × 10–10
4.5 × 10–9
7.4 × 10–10
2.1 × 10–9
2.4 × 10–10
3.4 × 10–9
4.6 × 10–9
3.0 × 10–9
6.1 × 10–10
2.7 × 10–10
8.8 × 10–9

9.8 × 10–9
1.1 × 10–8
7.3 × 10–10
1.5 × 10–9e(g)Age 1–2 a

4.6 × 10–10
1.2 × 10–9
8.9 × 10–10

2.9 × 10–10
2.4 × 10–9
3.9 × 10–10
1.1 × 10–9
1.2 × 10–10
1.7 × 10–9
2.3 × 10–9
1.5 × 10–9
3.0 × 10–10
1.3 × 10–10
4.4 × 10–9

4.9 × 10–9
6.4 × 10–9
3.6 × 10–10
7.3 × 10–10

e(g)

2–7 a

2.8 × 10–10
8.1 × 10–10
5.4 × 10–10

1.8 × 10–10
1.5 × 10–9
2.5 × 10–10
6.9 × 10–10
6.9 × 10–11
9.9 × 10–10
1.4 × 10–9
8.8 × 10–10
1.8 × 10–10
7.5 × 10–11
2.6 × 10–9

2.9 × 10–9
4.1 × 10–9
2.1 × 10–10
4.3 × 10–10

e(g)7–12 a1.7 × 10–10
5.3 × 10–10
3.2 × 10–10

1.2 × 10–10
9.5 × 10–10
1.5 × 10–10
4.2 × 10–10
3.9 × 10–11
5.6 × 10–10
7.9 × 10–10
5.1 × 10–10
1.1 × 10–10
5.0 × 10–11
1.5 × 10–9

1.7 × 10–9
2.6 × 10–9
1.3 × 10–10
2.6 × 10–10

e(g)12–17 a1.3 × 10–10
4.2 × 10–10
2.5 × 10–10

9.3 × 10–11
7.6 × 10–10
1.2 × 10–10
3.4 × 10–10
3.1 × 10–11
4.5 × 10–10
6.3 × 10–10
4.0 × 10–10
8.4 × 10–11
3.9 × 10–11
1.2 × 10–9

1.3 × 10–9
2.1 × 10–9
1.0 × 10–10
2.1 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

257

Hg‑193(organic)
Hg‑193(inorganic)
Hg‑193m(organic)
Hg‑193m(inorganic)
Hg‑194(organic)
Hg‑194(inorganic)
Hg‑195(organic)

MercuryAu‑198
Au‑198m
Au‑199Au‑200Au‑200m
Au‑201

Radionuclidea

1.000
0.800
0.040

11.1 h

1.000
0.800

9.90 h

2.60 × 102 a

1.000
0.800
0.040

2.60 × 102 a

11.1 h

3.50 h

1.000
0.800
0.040

0.200
0.200
0.200
0.200
0.200
0.200

f1

1.000
0.400
0.020
1.000
0.400

1.3 × 10–7
1.1 × 10–7
7.2 × 10–9
3.0 × 10–10
4.6 × 10–10

1.000
0.400
0.020

1.1 × 10–9
1.6 × 10–9
3.6 × 10–9

1.0 × 10–8
1.2 × 10–8
4.5 × 10–9
8.3 × 10–10
9.2 × 10–9
3.1 × 10–10

1.000
0.400
0.020

0.100
0.100
0.100
0.100
0.100
0.100

e(g)

3.3 × 10–10
4.7 × 10–10
8.5 × 10–10

f1 forg>1a

Age ≤ 1 a

3.50 h2.69 d2.30 d
3.14 d0.807 h18.7 h
0.440 hPhysicalhalf-life

2.0 × 10–10
4.8 × 10–10

1.2 × 10–7
4.8 × 10–8
3.6 × 10–9

6.8 × 10–10
1.8 × 10–9
2.4 × 10–9

1.9 × 10–10
4.4 × 10–10
5.5 × 10–10

7.2 × 10–9
8.5 × 10–9
3.1 × 10–9
4.7 × 10–10
6.6 × 10–9
1.7 × 10–10e(g)Age 1–2 a

1.0 × 10–10
2.5 × 10–10

8.4 × 10–8
3.5 × 10–8
2.6 × 10–9

3.7 × 10–10
9.5 × 10–10
1.3 × 10–9

9.8 × 10–11
2.2 × 10–10
2.8 × 10–10

3.7 × 10–9
4.4 × 10–9
1.6 × 10–9
2.3 × 10–10
3.5 × 10–9
8.2 × 10–11

e(g)

2–7 a

6.4 × 10–11
1.5 × 10–10

6.6 × 10–8
2.7 × 10–8
1.9 × 10–9

2.3 × 10–10
6.0 × 10–10
8.1 × 10–10

5.8 × 10–11
1.4 × 10–10
1.7 × 10–10

2.2 × 10–9
2.7 × 10–9
9.5 × 10–10
1.3 × 10–10
2.2 × 10–9
4.6 × 10–11

e(g)7–12 a4.2 × 10–11
9.3 × 10–11

5.5 × 10–8
2.3 × 10–8
1.5 × 10–9

1.5 × 10–10
3.7 × 10–10
5.0 × 10–10

3.9 × 10–11
8.3 × 10–11
1.0 × 10–10

1.3 × 10–9
1.6 × 10–9
5.5 × 10–10
8.7 × 10–11
1.3 × 10–9
3.1 × 10–11

e(g)12–17 a3.4 × 10–11
7.5 × 10–11

5.1 × 10–8
2.1 × 10–8
1.4 × 10–9

1.3 × 10–10
3.0 × 10–10
4.0 × 10–10

3.1 × 10–11
6.6 × 10–11
8.2 × 10–11

1.0 × 10–9
1.3 × 10–9
4.4 × 10–10
6.8 × 10–11
1.1 × 10–9
2.4 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

258

Hg‑195(inorganic)
Hg‑195m(organic)
Hg‑195m(inorganic)
Hg‑197(organic)
Hg‑197(inorganic)
Hg‑197m(organic)
Hg‑197m(inorganic)
Hg‑199m(organic)
Hg‑199m(inorganic)
Hg‑203(organic)
Hg‑203(inorganic)

Radionuclidea

1.000
0.800
0.040

1.000
0.800
0.040

1.000
0.800
0.040

1.000
0.800
0.040

1.000
0.800
0.040

1.73 d2.67 d23.8 h

0.710 h46.6 d46.6 d0.710 h23.8 h

2.67 d1.73 d0.040

f1

f1 for
g>1a
0.020
1.000
0.400
0.020
1.000
0.400
0.020
1.000
0.400
0.020
1.000
0.400
0.020
1.000
0.400
0.020

e(g)
9.5 × 10–10
2.1 × 10–9
2.6 × 10–9
5.8 × 10–9
9.7 × 10–10
1.3 × 10–9
2.5 × 10–9
1.5 × 10–9
2.2 × 10–9
5.2 × 10–9
3.4 × 10–10
3.6 × 10–10
3.7 × 10–10
1.5 × 10–8
1.3 × 10–8
5.5 × 10–9

Age ≤ 1 a9.90 hPhysicalhalf-life

1.1 × 10–8
6.4 × 10–9
3.6 × 10–9

1.9 × 10–10
2.1 × 10–10
2.1 × 10–10

9.5 × 10–10
2.5 × 10–9
3.4 × 10–9

6.2 × 10–10
1.2 × 10–9
1.6 × 10–9

1.3 × 10–9
2.8 × 10–9
3.8 × 10–9

6.3 × 10–10e(g)Age 1–2 a

5.7 × 10–9
3.4 × 10–9
1.8 × 10–9

9.3 × 10–11
1.0 × 10–10
1.0 × 10–10

4.8 × 10–10
1.2 × 10–9
1.7 × 10–9

3.1 × 10–10
6.1 × 10–10
8.3 × 10–10

6.8 × 10–10
1.4 × 10–9
2.0 × 10–9

3.3 × 10–10

e(g)

2–7 a

3.6 × 10–9
2.1 × 10–9
1.1 × 10–9

5.3 × 10–11
5.8 × 10–11
5.9 × 10–11

2.9 × 10–10
7.3 × 10–10
1.0 × 10–9

1.9 × 10–10
3.7 × 10–10
5.0 × 10–10

4.2 × 10–10
8.7 × 10–10
1.2 × 10–9

2.0 × 10–10

e(g)7–12 a2.3 × 10–9
1.3 × 10–9
6.7 × 10–10

3.6 × 10–11
3.9 × 10–11
3.9 × 10–11

1.8 × 10–10
4.2 × 10–10
5.9 × 10–10

1.2 × 10–10
2.2 × 10–10
2.9 × 10–10

2.7 × 10–10
5.1 × 10–10
7.0 × 10–10

1.2 × 10–10

e(g)12–17 a1.9 × 10–9
1.1 × 10–9
5.4 × 10–10

2.8 × 10–11
3.1 × 10–11
3.1 × 10–11

1.5 × 10–10
3.4 × 10–10
4.7 × 10–10

9.9 × 10–11
1.7 × 10–10
2.3 × 10–10

2.2 × 10–10
4.1 × 10–10
5.6 × 10–10

9.7 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

259

Pb‑195m
Pb‑198
Pb‑199Pb‑200Pb‑201
Pb‑202
Pb‑202m

Leadg

Tl‑194Tl‑194m
Tl‑195
Tl‑197
Tl‑198Tl‑198m
Tl‑199Tl‑200Tl‑201
Tl‑202
Tl‑204

ThalliumRadionuclidea

0.263 h2.40 h
1.50 h21.5 h
9.40 h3.00 × 105 a
3.62 h

0.550 h0.546 h1.16 h2.84 h5.30 h
1.87 h
7.42 h1.09 d
3.04 d12.2 d3.78 aPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600
0.600

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

e(g)

2.6 × 10–10
5.9 × 10–10
3.5 × 10–10
2.5 × 10–9
9.4 × 10–10
3.4 × 10–8
7.6 × 10–10

6.1 × 10–11
3.8 × 10–10
2.3 × 10–10
2.1 × 10–10
4.7 × 10–10
4.8 × 10–10
2.3 × 10–10
1.3 × 10–9
8.4 × 10–10
2.9 × 10–9
1.3 × 10–8

Age ≤ 1 a

0.200
0.200
0.200
0.200
0.200
0.200
0.200

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1 forg>1a

1.6 × 10–10
4.8 × 10–10
2.6 × 10–10
2.0 × 10–9
7.8 × 10–10
1.6 × 10–8
6.1 × 10–10

3.9 × 10–11
2.2 × 10–10
1.4 × 10–10
1.3 × 10–10
3.3 × 10–10
3.0 × 10–10
1.5 × 10–10
9.1 × 10–10
5.5 × 10–10
2.1 × 10–9
8.5 × 10–9e(g)Age 1–2 a

8.4 × 10–11
2.7 × 10–10
1.5 × 10–10
1.1 × 10–9
4.3 × 10–10
1.3 × 10–8
3.5 × 10–10

2.2 × 10–11
1.2 × 10–10
7.5 × 10–11
6.7 × 10–11
1.9 × 10–10
1.6 × 10–10
7.7 × 10–11
5.3 × 10–10
2.9 × 10–10
1.2 × 10–9
4.2 × 10–9

e(g)

2–7 a

5.2 × 10–11
1.7 × 10–10
9.4 × 10–11
7.0 × 10–10
2.7 × 10–10
1.9 × 10–8
2.3 × 10–10

1.4 × 10–11
7.0 × 10–11
4.7 × 10–11
4.2 × 10–11
1.2 × 10–10
9.7 × 10–11
4.8 × 10–11
3.5 × 10–10
1.8 × 10–10
7.9 × 10–10
2.5 × 10–9e(g)7–12 a3.5 × 10–11
1.1 × 10–10
6.3 × 10–11
4.4 × 10–10
1.8 × 10–10
2.7 × 10–8
1.5 × 10–10

1.0 × 10–11
4.9 × 10–11
3.3 × 10–11
2.8 × 10–11
8.7 × 10–11
6.7 × 10–11
3.2 × 10–11
2.4 × 10–10
1.2 × 10–10
5.4 × 10–10
1.5 × 10–9e(g)12–17 a2.9 × 10–11
1.0 × 10–10
5.4 × 10–11
4.0 × 10–10
1.6 × 10–10
8.8 × 10–9
1.3 × 10–10

8.1 × 10–12
4.0 × 10–11
2.7 × 10–11
2.3 × 10–11
7.3 × 10–11
5.4 × 10–11
2.6 × 10–11
2.0 × 10–10
9.5 × 10–11
4.5 × 10–10
1.2 × 10–9

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

260

Bi‑200Bi‑201
Bi‑202
Bi‑203
Bi‑205
Bi‑206
Bi‑207
Bi‑210Bi‑210m
Bi‑212
Bi‑213
Bi‑214

BismuthPb‑203
Pb‑205
Pb‑209Pb‑210Pb‑211
Pb‑212
Pb‑214

Radionuclidea

0.606 h1.80 h
1.67 h11.8 h15.3 d6.24 d38.0 a5.01 d3.00 × 106 a
1.01 h
0.761 h0.332 h2.17 d1.43 × 107 a
3.25 h22.3 a0.601 h10.6 h
0.447 hPhysicalhalf-life

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.600
0.600
0.600
0.600
0.600
0.600
0.600

f1
1.6 × 10–9
2.1 × 10–9
5.7 × 10–10
8.4 × 10–6
3.1 × 10–9
1.5 × 10–7
2.7 × 10–9

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.200
0.200
0.200
0.200
0.200
0.200
0.200

e(g)

4.2 × 10–10
1.0 × 10–9
6.4 × 10–10
3.5 × 10–9
6.1 × 10–9
1.4 × 10–8
1.0 × 10–8
1.5 × 10–8
2.1 × 10–7
3.2 × 10–9
2.5 × 10–9
1.4 × 10–9

f1 forg>1a

Age ≤ 1 a

2.7 × 10–10
6.7 × 10–10
4.4 × 10–10
2.5 × 10–9
4.5 × 10–9
1.0 × 10–8
7.1 × 10–9
9.7 × 10–9
9.1 × 10–8
1.8 × 10–9
1.4 × 10–9
7.4 × 10–10

1.3 × 10–9
9.9 × 10–10
3.8 × 10–10
3.6 × 10–6
1.4 × 10–9
6.3 × 10–8
1.0 × 10–9e(g)Age 1–2 a

1.5 × 10–10
3.6 × 10–10
2.5 × 10–10
1.4 × 10–9
2.6 × 10–9
5.7 × 10–9
3.9 × 10–9
4.8 × 10–9
4.7 × 10–8
8.7 × 10–10
6.7 × 10–10
3.6 × 10–10

6.8 × 10–10
6.2 × 10–10
1.9 × 10–10
2.2 × 10–6
7.1 × 10–10
3.3 × 10–8
5.2 × 10–10

e(g)

2–7 a

9.5 × 10–11
2.2 × 10–10
1.6 × 10–10
9.3 × 10–10
1.7 × 10–9
3.7 × 10–9
2.5 × 10–9
2.9 × 10–9
3.0 × 10–8
5.0 × 10–10
3.9 × 10–10
2.1 × 10–10

4.3 × 10–10
6.1 × 10–10
1.1 × 10–10
1.9 × 10–6
4.1 × 10–10
2.0 × 10–8
3.1 × 10–10

e(g)7–12 a6.4 × 10–11
1.4 × 10–10
1.1 × 10–10
6.0 × 10–10
1.1 × 10–9
2.4 × 10–9
1.6 × 10–9
1.6 × 10–9
1.9 × 10–8
3.3 × 10–10
2.5 × 10–10
1.4 × 10–10

2.7 × 10–10
6.5 × 10–10
6.6 × 10–11
1.9 × 10–6
2.7 × 10–10
1.3 × 10–8
2.0 × 10–10

e(g)12–17 a5.1 × 10–11
1.2 × 10–10
8.9 × 10–11
4.8 × 10–10
9.0 × 10–10
1.9 × 10–9
1.3 × 10–9
1.3 × 10–9
1.5 × 10–8
2.6 × 10–10
2.0 × 10–10
1.1 × 10–10

2.4 × 10–10
2.8 × 10–10
5.7 × 10–11
6.9 × 10–7
1.8 × 10–10
6.0 × 10–9
1.4 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

261

Ra‑223
Ra‑224
Ra‑225
Ra‑226
Ra‑227
Ra‑228Radiumh

Fr‑222
Fr‑223

Francium

At‑207
At‑211

Astatine

Po‑203
Po‑205
Po‑207
Po‑210

PoloniumRadionuclidea

11.4 d
3.66 d
14.8 d
1.60 × 103 a
0.703 h5.75 a0.240 h0.363 h1.80 h7.21 h

0.612 h1.80 h5.83 h138 dPhysicalhalf-life

0.600
0.600
0.600
0.600
0.600
0.600

1.000
1.000

1.000
1.000

1.000
1.000
1.000
1.000

f1

e(g)

5.3 × 10–6
2.7 × 10–6
7.1 × 10–6
4.7 × 10–6
1.1 × 10–9
3.0 × 10–5

6.2 × 10–9
2.6 × 10–8

2.5 × 10–9
1.2 × 10–7

2.9 × 10–10
3.5 × 10–10
4.4 × 10–10
2.6 × 10–5

Age ≤ 1 a

0.200
0.200
0.200
0.200
0.200
0.200

1.000
1.000

1.000
1.000

0.500
0.500
0.500
0.500

f1 forg>1a

1.1 × 10–6
6.6 × 10–7
1.2 × 10–6
9.6 × 10–7
4.3 × 10–10
5.7 × 10–6

3.9 × 10–9
1.7 × 10–8

1.6 × 10–9
7.8 × 10–8

2.4 × 10–10
2.8 × 10–10
5.7 × 10–10
8.8 × 10–6e(g)Age 1–2 a

5.7 × 10–7
3.5 × 10–7
6.1 × 10–7
6.2 × 10–7
2.5 × 10–10
3.4 × 10–6

2.0 × 10–9
8.3 × 10–9

8.0 × 10–10
3.8 × 10–8

1.3 × 10–10
1.6 × 10–10
3.2 × 10–10
4.4 × 10–6

e(g)

2–7 a

4.5 × 10–7
2.6 × 10–7
5.0 × 10–7
8.0 × 10–7
1.7 × 10–10
3.9 × 10–6

1.3 × 10–9
5.0 × 10–9

4.8 × 10–10
2.3 × 10–8

8.5 × 10–11
1.1 × 10–10
2.1 × 10–10
2.6 × 10–6

e(g)7–12 a3.7 × 10–7
2.0 × 10–7
4.4 × 10–7
1.5 × 10–6
1.3 × 10–10
5.3 × 10–6

8.5 × 10–10
2.9 × 10–9

2.9 × 10–10
1.3 × 10–8

5.8 × 10–11
7.2 × 10–11
1.4 × 10–10
1.6 × 10–6

e(g)12–17 a1.0 × 10–7
6.5 × 10–8
9.9 × 10–8
2.8 × 10–7
8.1 × 10–11
6.9 × 10–7

7.2 × 10–10
2.4 × 10–9

2.4 × 10–10
1.1 × 10–8

4.6 × 10–11
5.8 × 10–11
1.1 × 10–1
1.2 × 10–6

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

262

Pa‑227
Pa‑228
Pa‑230

Protactinium

Th‑226
Th‑227
Th‑228
Th‑229Th‑230Th‑231
Th‑232
Th‑234

Thorium

Ac‑224
Ac‑225
Ac‑226
Ac‑227
Ac‑228ActiniumRadionuclidea

0.638 h22.0 h
17.4 d

0.515 h18.7 d
1.91 a7.34 × 103 a
7.70 × 104 a
1.06 d
1.40 × 1010 a
24.1 d

2.90 h
10.0 d
1.21 d21.8 a6.13 hPhysicalhalf-life

0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

f1

e(g)

5.8 × 10–9
1.2 × 10–8
2.6 × 10–8

4.4 × 10–9
3.0 × 10–7
3.7 × 10–6
1.1 × 10–5
4.1 × 10–6
3.9 × 10–9
4.6 × 10–6
4.0 × 10–8

1.0 × 10–8
4.6 × 10–7
1.4 × 10–7
3.3 × 10–5
7.4 × 10–9

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

3.2 × 10–9
4.8 × 10–9
5.7 × 10–9

2.4 × 10–9
7.0 × 10–8
3.7 × 10–7
1.0 × 10–6
4.1 × 10–7
2.5 × 10–9
4.5 × 10–7
2.5 × 10–8

5.2 × 10–9
1.8 × 10–7
7.6 × 10–8
3.1 × 10–6
2.8 × 10–9e(g)Age 1–2 a

1.5 × 10–9
2.6 × 10–9
3.1 × 10–9

1.2 × 10–9
3.6 × 10–8
2.2 × 10–7
7.8 × 10–7
3.1 × 10–7
1.2 × 10–9
3.5 × 10–7
1.3 × 10–8

2.6 × 10–9
9.1 × 10–8
3.8 × 10–8
2.2 × 10–6
1.4 × 10–9

e(g)

2–7 a

8.7 × 10–10
1.6 × 10–9
1.9 × 10–9

6.7 × 10–10
2.3 × 10–8
1.5 × 10–7
6.2 × 10–7
2.4 × 10–7
7.4 × 10–10
2.9 × 10–7
7.4 × 10–9

1.5 × 10–9
5.4 × 10–8
2.3 × 10–8
1.5 × 10–6
8.7 × 10–10

e(g)7–12 a5.8 × 10–10
9.7 × 10–10
1.1 × 10–9

4.5 × 10–10
1.5 × 10–8
9.4 × 10–8
5.3 × 10–7
2.2 × 10–7
4.2 × 10–10
2.5 × 10–7
4.2 × 10–9

8.8 × 10–10
3.0 × 10–8
1.3 × 10–8
1.2 × 10–6
5.3 × 10–10

e(g)12–17 a4.5 × 10–10
7.8 × 10–10
9.2 × 10–10

3.5 × 10–10
8.8 × 10–9
7.2 × 10–8
4.9 × 10–7
2.1 × 10–7
3.4 × 10–10
2.3 × 10–7
3.4 × 10–9

7.0 × 10–10
2.4 × 10–8
1.0 × 10–8
1.1 × 10–6
4.3 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

263

Np‑232
Np‑233
Np‑234

Neptunium

U‑230
U‑231
U‑232
U‑233
U‑234
U‑235
U‑236
U‑237
U‑238
U‑239
U‑240

Uranium

Pa‑231
Pa‑232
Pa‑233
Pa‑234

Radionuclidea

0.245 h0.603 h4.40 d

0.005
0.005
0.005

0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

0.005
0.005
0.005
0.005

3.27 × 104 a
1.31 d
27.0 d6.70 h20.8 d
4.20 d72.0 a1.58 × 105 a
2.44 × 105 a
7.04 × 108 a
2.34 × 107 a
6.75 d
4.47 × 109 a
0.392 h14.1 hf1

Physicalhalf-lifee(g)8.7 × 10–11
2.1 × 10–11
6.2 × 10–9

7.9 × 10–7
3.1 × 10–9
2.5 × 10–6
3.8 × 10–7
3.7 × 10–7
3.5 × 10–7
3.5 × 10–7
8.3 × 10–9
3.4 × 10–7
3.4 × 10–10
1.3 × 10–8

1.3 × 10–5
6.3 × 10–9
9.7 × 10–9
5.0 × 10–9

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

5.1 × 10–11
1.3 × 10–11
4.4 × 10–9

3.0 × 10–7
2.0 × 10–9
8.2 × 10–7
1.4 × 10–7
1.3 × 10–7
1.3 × 10–7
1.3 × 10–7
5.4 × 10–9
1.2 × 10–7
1.9 × 10–10
8.1 × 10–9

1.3 × 10–6
4.2 × 10–9
6.2 × 10–9
3.2 × 10–9e(g)Age 1–2 a

2.7 × 10–11
6.6 × 10–12
2.4 × 10–9

1.5 × 10–7
1.0 × 10–9
5.8 × 10–7
9.2 × 10–8
8.8 × 10–8
8.5 × 10–8
8.4 × 10–8
2.8 × 10–9
8.0 × 10–8
9.3 × 10–11
4.1 × 10–9

1.1 × 10–6
2.2 × 10–9
3.2 × 10–9
1.7 × 10–9

e(g)

2–7 a

1.7 × 10–11
4.0 × 10–12
1.6 × 10–9

1.0 × 10–7
6.1 × 10–10
5.7 × 10–7
7.8 × 10–8
7.4 × 10–8
7.1 × 10–8
7.0 × 10–8
1.6 × 10–9
6.8 × 10–8
5.4 × 10–11
2.4 × 10–9

9.2 × 10–7
1.4 × 10–9
1.9 × 10–9
1.0 × 10–9e(g)7–12 a

1.2 × 10–11
2.8 × 10–12
1.0 × 10–9

6.6 × 10–8
3.5 × 10–10
6.4 × 10–7
7.8 × 10–8
7.4 × 10–8
7.0 × 10–8
7.0 × 10–8
9.5 × 10–10
6.7 × 10–8
3.5 × 10–11
1.4 × 10–9

8.0 × 10–7
8.9 × 10–10
1.1 × 10–9
6.4 × 10–10

e(g)12–17 a9.7 × 10–12
2.2 × 10–12
8.1 × 10–10

5.6 × 10–8
2.8 × 10–10
3.3 × 10–7
5.1 × 10–8
4.9 × 10–8
4.7 × 10–8
4.7 × 10–8
7.6 × 10–10
4.5 × 10–8
2.7 × 10–11
1.1 × 10–9

7.1 × 10–7
7.2 × 10–10
8.7 × 10–10
5.1 × 10–10

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

264

Pu‑234
Pu‑235
Pu‑236
Pu‑237
Pu‑238
Pu‑239Pu‑240Pu‑241
Pu‑242
Pu‑243
Pu‑244Pu‑245
Pu‑246

Plutonium

Np‑235
Np‑236
Np‑236m
Np‑237
Np‑238
Np‑239Np‑240Radionuclidea

8.80 h
0.422 h2.85 a45.3 d87.7 a2.41 × 104 a
6.54 × 103 a
14.4 a3.76 × 105 a4.95 h8.26 × 107 a
10.5 h10.9 d1.08 a1.15 × 105 a
22.5 h2.14 × 106 a
2.12 d2.36 d1.08 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1
7.1 × 10–10
1.9 × 10–7
2.5 × 10–9
2.0 × 10–6
9.5 × 10–9
8.9 × 10–9
8.7 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)2.1 × 10–9
2.2 × 10–11
2.1 × 10–6
1.1 × 10–9
4.0 × 10–6
4.2 × 10–6
4.2 × 10–6
5.6 × 10–8
4.0 × 10–6
1.0 × 10–9
4.0 × 10–6
8.0 × 10–9
3.6 × 10–8

f1 forg>1a

Age ≤ 1 a

1.1 × 10–9
1.3 × 10–11
2.2 × 10–7
6.9 × 10–10
4.0 × 10–7
4.2 × 10–7
4.2 × 10–7
5.7 × 10–9
4.0 × 10–7
6.2 × 10–10
4.1 × 10–7
5.1 × 10–9
2.3 × 10–8

4.1 × 10–10
2.4 × 10–8
1.3 × 10–9
2.1 × 10–7
6.2 × 10–9
5.7 × 10–9
5.2 × 10–10e(g)Age 1–2 a

5.5 × 10–10
6.5 × 10–12
1.4 × 10–7
3.6 × 10–10
3.1 × 10–7
3.3 × 10–7
3.3 × 10–7
5.5 × 10–9
3.2 × 10–7
3.1 × 10–10
3.2 × 10–7
2.6 × 10–9
1.2 × 10–8

2.0 × 10–10
1.8 × 10–8
6.6 × 10–10
1.4 × 10–7
3.2 × 10–9
2.9 × 10–9
2.6 × 10–10

e(g)

2–7 a

3.3 × 10–10
3.9 × 10–12
1.0 × 10–7
2.2 × 10–10
2.4 × 10–7
2.7 × 10–7
2.7 × 10–7
5.1 × 10–9
2.6 × 10–7
1.8 × 10–10
2.6 × 10–7
1.5 × 10–9
7.1 × 10–9

1.2 × 10–10
1.8 × 10–8
4.0 × 10–10
1.1 × 10–7
1.9 × 10–9
1.7 × 10–9
1.6 × 10–10

e(g)7–12 a2.0 × 10–10
2.7 × 10–12
8.5 × 10–8
1.3 × 10–10
2.2 × 10–7
2.4 × 10–7
2.4 × 10–7
4.8 × 10–9
2.3 × 10–7
1.1 × 10–10
2.3 × 10–7
8.9 × 10–10
4.1 × 10–9

6.8 × 10–11
1.8 × 10–8
2.4 × 10–10
1.1 × 10–7
1.1 × 10–9
1.0 × 10–9
1.0 × 10–10

e(g)12–17 a1.6 × 10–10
2.1 × 10–12
8.7 × 10–8
1.0 × 10–10
2.3 × 10–7
2.5 × 10–7
2.5 × 10–7
4.8 × 10–9
2.4 × 10–7
8.5 × 10–11
2.4 × 10–7
7.2 × 10–10
3.3 × 10–9

5.3 × 10–11
1.7 × 10–8
1.9 × 10–10
1.1 × 10–7
9.1 × 10–10
8.0 × 10–10
8.2 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)265

Cm‑238
Cm‑240Cm‑241
Cm‑242
Cm‑243CuriumAm‑237
Am‑238
Am‑239Am‑240Am‑241
Am‑242
Am‑242m
Am‑243
Am‑244
Am‑244m
Am‑245
Am‑246
Am‑246m

AmericiumRadionuclidea

2.40 h
27.0 d32.8 d163 d28.5 a1.22 h
1.63 h11.9 h2.12 d
4.32 × 102 a
16.0 h1.52 × 102 a
7.38 × 103 a
10.1 h
0.433 h2.05 h
0.650 h0.417 hPhysicalhalf-life

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

e(g)

7.8 × 10–10
2.2 × 10–7
1.1 × 10–8
5.9 × 10–7
3.2 × 10–6

1.7 × 10–10
2.5 × 10–10
2.6 × 10–9
4.7 × 10–9
3.7 × 10–6
5.0 × 10–9
3.1 × 10–6
3.6 × 10–6
4.9 × 10–9
3.7 × 10–10
6.8 × 10–10
6.7 × 10–10
3.9 × 10–10

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

4.9 × 10–10
4.8 × 10–8
5.7 × 10–9
7.6 × 10–8
3.3 × 10–7

1.0 × 10–10
1.6 × 10–10
1.7 × 10–9
3.3 × 10–9
3.7 × 10–7
2.2 × 10–9
3.0 × 10–7
3.7 × 10–7
3.1 × 10–9
2.0 × 10–10
4.5 × 10–10
3.8 × 10–10
2.2 × 10–10e(g)Age 1–2 a

2.6 × 10–10
2.5 × 10–8
3.0 × 10–9
3.9 × 10–8
2.2 × 10–7

5.5 × 10–11
9.1 × 10–11
8.4 × 10–10
1.8 × 10–9
2.7 × 10–7
1.1 × 10–9
2.3 × 10–7
2.7 × 10–7
1.6 × 10–9
9.6 × 10–11
2.2 × 10–10
1.9 × 10–10
1.1 × 10–10

e(g)

2–7 a

1.6 × 10–10
1.5 × 10–8
1.9 × 10–9
2.4 × 10–8
1.6 × 10–7

3.3 × 10–11
5.9 × 10–11
5.1 × 10–10
1.2 × 10–9
2.2 × 10–7
6.4 × 10–10
2.0 × 10–7
2.2 × 10–7
9.6 × 10–10
5.5 × 10–11
1.3 × 10–10
1.1 × 10–10
6.4 × 10–11

e(g)7–12 a1.0 × 10–10
9.2 × 10–9
1.1 × 10–9
1.5 × 10–8
1.4 × 10–7

2.2 × 10–11
4.0 × 10–11
3.0 × 10–10
7.3 × 10–10
2.0 × 10–7
3.7 × 10–10
1.9 × 10–7
2.0 × 10–7
5.8 × 10–10
3.7 × 10–11
7.9 × 10–11
7.3 × 10–11
4.4 × 10–11

e(g)12–17 a8.0 × 10–11
7.6 × 10–9
9.1 × 10–10
1.2 × 10–8
1.5 × 10–7

1.8 × 10–11
3.2 × 10–11
2.4 × 10–10
5.8 × 10–10
2.0 × 10–7
3.0 × 10–10
1.9 × 10–7
2.0 × 10–7
4.6 × 10–10
2.9 × 10–11
6.2 × 10–11
5.8 × 10–11
3.4 × 10–11

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

266

Cf‑244
Cf‑246
Cf‑248

Californium

Bk‑245
Bk‑246
Bk‑247
Bk‑249
Bk‑250Berkelium

Cm‑244
Cm‑245
Cm‑246
Cm‑247
Cm‑248
Cm‑249Cm‑250Radionuclidea

0.323 h1.49 d334 d4.94 d1.83 d1.38 × 103 a
320 d3.22 h18.1 a8.50 × 103 a4.73 × 103 a
1.56 × 107 a
3.39 × 105 a
1.07 h
6.90 × 103 a

Physicalhalf-life

0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1
2.9 × 10–6
3.7 × 10–6
3.7 × 10–6
3.4 × 10–6
1.4 × 10–5
3.9 × 10–10
7.8 × 10–5

9.8 × 10–10
5.0 × 10–8
1.5 × 10–6

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)6.1 × 10–9
3.7 × 10–9
8.9 × 10–6
2.2 × 10–8
1.5 × 10–9

f1 forg>1a

Age ≤ 1 a

4.8 × 10–10
2.4 × 10–8
1.6 × 10–7

3.9 × 10–9
2.6 × 10–9
8.6 × 10–7
2.9 × 10–9
8.5 × 10–10

2.9 × 10–7
3.7 × 10–7
3.7 × 10–7
3.5 × 10–7
1.4 × 10–6
2.2 × 10–10
8.2 × 10–6e(g)Age 1–2 a

2.4 × 10–10
1.2 × 10–8
9.9 × 10–8

2.0 × 10–9
1.4 × 10–9
6.3 × 10–7
1.9 × 10–9
4.4 × 10–10

1.9 × 10–7
2.8 × 10–7
2.8 × 10–7
2.6 × 10–7
1.0 × 10–6
1.1 × 10–10
6.0 × 10–6

e(g)

2–7 a

1.3 × 10–10
7.3 × 10–9
6.0 × 10–8

1.2 × 10–9
9.4 × 10–10
4.6 × 10–7
1.4 × 10–9
2.7 × 10–10

1.4 × 10–7
2.3 × 10–7
2.2 × 10–7
2.1 × 10–7
8.4 × 10–7
6.1 × 10–11
4.9 × 10–6

e(g)7–12 a8.9 × 10–11
4.1 × 10–9
3.3 × 10–8

7.2 × 10–10
6.0 × 10–10
3.8 × 10–7
1.1 × 10–9
1.7 × 10–10

1.2 × 10–7
2.1 × 10–7
2.1 × 10–7
1.9 × 10–7
7.7 × 10–7
4.0 × 10–11
4.4 × 10–6

e(g)12–17 a7.0 × 10–11
3.3 × 10–9
2.8 × 10–

5.7 × 10–10
4.8 × 10–10
3.5 × 10–7
9.7 × 10–10
1.4 × 10–10

1.2 × 10–7
2.1 × 10–7
2.1 × 10–7
1.9 × 10–7
7.7 × 10–7
3.1 × 10–11
4.4 × 10–6

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

267

Fm‑252
Fm‑253
Fm‑254
Fm‑255
Fm‑257

Fermium

Es‑250Es‑251
Es‑253
Es‑254
Es‑254m

Einsteinium

Cf‑249Cf‑250
Cf‑251
Cf‑252
Cf‑253
Cf‑254

Radionuclidea

22.7 h3.00 d3.24 h20.1 h
101 d

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005

3.50 × 102 a
13.1 a8.98 × 102 a2.64 a17.8 d60.5 d

2.10 h1.38 d20.5 d276 d1.64 df1

Physicalhalf-lifee(g)3.8 × 10–8
2.5 × 10–8
5.6 × 10–9
3.3 × 10–8
9.8 × 10–7

2.3 × 10–10
1.9 × 10–9
1.7 × 10–7
1.4 × 10–6
5.7 × 10–8

9.0 × 10–6
5.7 × 10–6
9.1 × 10–6
5.0 × 10–6
1.0 × 10–7
1.1 × 10–5

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a2.0 × 10–8
6.7 × 10–9
3.2 × 10–9
1.9 × 10–8
1.1 × 10–7

9.9 × 10–11
1.2 × 10–9
4.5 × 10–8
1.6 × 10–7
3.0 × 10–8

8.7 × 10–7
5.5 × 10–7
8.8 × 10–7
5.1 × 10–7
1.1 × 10–8
2.6 × 10–6e(g)Age 1–2 a

9.9 × 10–9
3.4 × 10–9
1.6 × 10–9
9.5 × 10–9
6.5 × 10–8

5.7 × 10–11
6.1 × 10–10
2.3 × 10–8
9.8 × 10–8
1.5 × 10–8

6.4 × 10–7
3.7 × 10–7
6.5 × 10–7
3.2 × 10–7
6.0 × 10–9
1.4 × 10–6

e(g)

2–7 a

5.9 × 10–9
2.1 × 10–9
9.3 × 10–10
5.6 × 10–9
4.0 × 10–8

3.7 × 10–11
3.7 × 10–10
1.4 × 10–8
6.0 × 10–8
9.1 × 10–9

4.7 × 10–7
2.3 × 10–7
4.7 × 10–7
1.9 × 10–7
3.7 × 10–9
8.4 × 10–7

e(g)7–12 a3.3 × 10–9
1.1 × 10–9
5.6 × 10–10
3.2 × 10–9
1.9 × 10–8

2.6 × 10–11
2.2 × 10–10
7.6 × 10–9
3.3 × 10–8
5.2 × 10–9

3.8 × 10–7
1.7 × 10–7
3.9 × 10–7
1.0 × 10–7
1.8 × 10–9
5.0 × 10–7

e(g)12–17 a2.7 × 10–9
9.1 × 10–10
4.4 × 10–10
2.5 × 10–9
1.5 × 10–8

2.1 × 10–11
1.7 × 10–10
6.1 × 10–9
2.8 × 10–8
4.2 × 10–9

3.5 × 10–7
1.6 × 10–7
3.6 × 10–7
9.0 × 10–8
1.4 × 10–9
4.0 × 10–7

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

268

5.20 h
55.0 dPhysicalhalf-life

0.005
0.005

f1

e(g)

3.1 × 10–9
6.3 × 10–7

Age ≤ 1 a

5.0 × 10–4
5.0 × 10–4

f1 forg>1a

8.8 × 10–10
8.9 × 10–8e(g)Age 1–2 a

4.5 × 10–10
5.0 × 10–8

e(g)

2–7 a

2.7 × 10–10
3.0 × 10–8

e(g)7–12 a

1.5 × 10–10
1.6 × 10–8

e(g)12–17 abm and mʹ denote metastable states of the radionuclide. The metastable state mʹ is of higher energy than the metastable state m.
The f1 value for calcium for 1–15 year olds is 0.4.
c
The f1 value for iron for 1–15 year olds is 0.2.
d
The f1 value for cobalt for 1–15 year olds is 0.3.
e
The f1 value for strontium for 1–15 year olds is 0.4.
f
The f1 value for barium for 1–15 year olds is 0.3.
g
The f1 value for lead for 1–15 year olds is 0.4.
h
The f1 value for radium for 1–15 year olds is 0.3.
Note: f1: gut transfer factor; e(g): effective dose per unit intake by age group.

a

Md‑257
Md‑258Mendelevium

Radionuclidea

1.2 × 10–10
1.3 × 10–8

e(g)

>17 a

TABLE III.2D. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INGESTION (Sv/Bq) (cont.)

269

1.60 × 106 a

Be-10

0.340 h5.73 × 103 a

C-11

C-14

Carbon53.3 d12.3 aPhysicalhalf-life

Be-7

Beryllium

H-3

HydrogenRadionuclidea

F
M
S
F
M
S

M
S
M
S

F
M
S

Type

1.000
0.200
0.020
1.000
0.200
0.020

0.020
0.020
0.020
0.020

1.000
0.200
0.020

f1

Age ≤ 1 a

1.0 × 10–10
1.5 × 10–10
1.6 × 10–10
6.1 × 10–10
8.3 × 10–9
1.9 × 10–8

2.5 × 10–10
2.8 × 10–10
4.1 × 10–8
9.9 × 10–8

2.6 × 10–11
3.4 × 10–10
1.2 × 10–9

e(g)

1.000
0.100
0.010
1.000
0.100
0.010

0.005
0.005
0.005
0.005

1.000
0.100
0.010

f1 forg>1a

7.0 × 10–11
1.1 × 10–10
1.1 × 10–10
6.7 × 10–10
6.6 × 10–9
1.7 × 10–8

2.1 × 10–10
2.4 × 10–10
3.4 × 10–8
9.1 × 10–8

2.0 × 10–11
2.7 × 10–10
1.0 × 10–9e(g)Age 1–2 a

3.2 × 10–11
4.9 × 10–11
5.1 × 10–11
3.6 × 10–10
4.0 × 10–9
1.1 × 10–8

1.2 × 10–10
1.4 × 10–10
2.0 × 10–8
6.1 × 10–8

1.1 × 10–11
1.4 × 10–10
6.3 × 10–10

e(g)

2–7 a

2.1 × 10–11
3.2 × 10–11
3.3 × 10–11
2.9 × 10–10
2.8 × 10–9
7.4 × 10–9

8.3 × 10–11
9.6 × 10–11
1.3 × 10–8
4.2 × 10–8

8.2 × 10–12
8.2 × 10–11
3.8 × 10–10

e(g)7–12 a1.3 × 10–11
2.1 × 10–11
2.2 × 10–11
1.9 × 10–10
2.5 × 10–9
6.4 × 10–9

6.2 × 10–11
6.8 × 10–11
1.1 × 10–8
3.7 × 10–8

5.9 × 10–12
5.3 × 10–11
2.8 × 10–10

e(g)12–17 a1.1 × 10–11
1.8 × 10–11
1.8 × 10–11
2.0 × 10–10
2.0 × 10–9
5.8 × 10–9

5.0 × 10–11
5.5 × 10–11
9.6 × 10–9
3.5 × 10–8

6.2 × 10–12
4.5 × 10–11
2.6 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

270

Si‑31

SiliconAl-26

Aluminium

Mg-28

Magnesium

Na-22
Na-24

Sodium

F-18

Fluorine

Radionuclidea

2.62 h

7.16 × 105 a

20.9 h

2.60 a15.0 h1.83 hPhysicalhalf-life

F
M
S

F
M

F
M

F
F

F
M
S

Type

0.020
0.020
0.020

0.020
0.020

1.000
1.000

1.000
1.000

1.000
1.000
1.000

f1

Age ≤ 1 a

3.6 × 10–10
6.9 × 10–10
7.2 × 10–10

8.1 × 10–8
8.8 × 10–8

5.3 × 10–9
7.3 × 10–9

9.7 × 10–9
2.3 × 10–9

2.6 × 10–10
4.1 × 10–10
4.2 × 10–10

e(g)

0.010
0.010
0.010

0.010
0.010

0.500
0.500

1.000
1.000

1.000
1.000
1.000

f1 forg>1a2.3 × 10–10
4.4 × 10–10
4.7 × 10–10

6.2 × 10–8
7.4 × 10–8

4.7 × 10–9
7.2 × 10–9

7.3 × 10–9
1.8 × 10–9

1.9 × 10–10
2.9 × 10–10
3.1 × 10–10e(g)Age 1–2 a

9.5 × 10–11
2.0 × 10–10
2.2 × 10–10

3.2 × 10–8
4.4 × 10–8

2.2 × 10–9
3.5 × 10–9

3.8 × 10–9
9.3 × 10–10

9.1 × 10–11
1.5 × 10–10
1.5 × 10–10

e(g)

2–7 a

5.9 × 10–11
1.3 × 10–10
1.4 × 10–10

2.0 × 10–8
2.9 × 10–8

1.3 × 10–9
2.3 × 10–9

2.4 × 10–9
5.7 × 10–10

5.6 × 10–11
9.7 × 10–11
1.0 × 10–10

e(g)7–12 a3.2 × 10–11
8.9 × 10–11
9.5 × 10–11

1.3 × 10–8
2.2 × 10–8

7.3 × 10–10
1.5 × 10–9

1.5 × 10–9
3.4 × 10–10

3.4 × 10–11
6.9 × 10–11
7.3 × 10–11

e(g)12–17 a2.7 × 10–11
7.4 × 10–11
7.9 × 10–11

1.1 × 10–8
2.0 × 10–8

6.0 × 10–10
1.2 × 10–9

1.3 × 10–9
2.7 × 10–10

2.8 × 10–11
5.6 × 10–11
5.9 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

271

3.01 × 105 a

0.620 h0.927 h

Cl‑36

Cl‑38

Cl‑39

Chlorine

S‑35(inorganic)

87.4 d25.4 dP‑33

Sulphur

14.3 d

4.50 × 102 a

Physicalhalf-life

P‑32

Phosphorus

Si‑32Radionuclidea

F
M
F
M
F
M

F
M
S

F
M
F
M

F
M
S

Type

1.000
1.000
1.000
1.000
1.000
1.000

1.000
0.200
0.020

1.000
1.000
1.000
1.000

0.020
0.020
0.020

f1

Age ≤ 1 a

3.9 × 10–9
3.1 × 10–8
2.9 × 10–10
4.7 × 10–10
2.7 × 10–10
4.3 × 10–10

5.5 × 10–10
5.9 × 10–9
7.7 × 10–9

1.2 × 10–8
2.2 × 10–8
1.2 × 10–9
6.1 × 10–9

3.0 × 10–8
7.1 × 10–8
2.8 × 10–7

e(g)

1.000
1.000
1.000
1.000
1.000
1.000

0.800
0.100
0.010

0.800
0.800
0.800
0.800

0.010
0.010
0.010

f1 forg>1a2.6 × 10–9
2.6 × 10–8
1.9 × 10–10
3.0 × 10–10
1.8 × 10–10
2.8 × 10–10

3.9 × 10–10
4.5 × 10–9
6.0 × 10–9

7.5 × 10–9
1.5 × 10–8
7.8 × 10–10
4.6 × 10–9

2.3 × 10–8
6.0 × 10–8
2.7 × 10–7e(g)Age 1–2 a

1.1 × 10–9
1.5 × 10–8
8.4 × 10–11
1.4 × 10–10
8.4 × 10–11
1.3 × 10–10

1.8 × 10–10
2.8 × 10–9
3.6 × 10–9

3.2 × 10–9
8.0 × 10–9
3.0 × 10–10
2.8 × 10–9

1.1 × 10–8
3.6 × 10–8
1.9 × 10–7

e(g)

2–7 a

7.1 × 10–10
1.0 × 10–8
5.1 × 10–11
8.5 × 10–11
5.1 × 10–11
8.5 × 10–11

1.1 × 10–10
2.0 × 10–9
2.6 × 10–9

1.8 × 10–9
5.3 × 10–9
2.0 × 10–10
2.1 × 10–9

6.4 × 10–9
2.4 × 10–8
1.3 × 10–7

e(g)7–12 a3.9 × 10–10
8.8 × 10–9
3.0 × 10–11
5.4 × 10–11
3.1 × 10–11
5.6 × 10–11

6.0 × 10–11
1.8 × 10–9
2.3 × 10–9

9.8 × 10–10
4.0 × 10–9
1.1 × 10–10
1.9 × 10–9

3.8 × 10–9
1.9 × 10–8
1.1 × 10–7

e(g)12–17 a3.3 × 10–10
7.3 × 10–9
2.5 × 10–11
4.5 × 10–11
2.5 × 10–11
4.6 × 10–11

5.1 × 10–11
1.4 × 10–9
1.9 × 10–9

7.7 × 10–10
3.4 × 10–9
9.2 × 10–11
1.5 × 10–9

3.2 × 10–9
1.7 × 10–8
1.1 × 10–7

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

272

4.53 d

Ca‑47

Sc‑43
Sc‑44
Sc‑44m

3.89 h
3.93 h
2.44 d

163 d

Ca‑45

Scandium1.40 × 105 a

1.28 × 109 a
12.4 h22.6 h
0.369 h0.333 hPhysicalhalf-life

Ca‑41

Calciumb

K‑40
K‑42
K‑43
K‑44
K‑45

Potassium

Radionuclidea

S
S
S

F
M
S
F
M
S
F
M
S

F
F
F
F
F

Type

0.001
0.001
0.001

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

1.000
1.000
1.000
1.000
1.000

f1

Age ≤ 1 a

9.3 × 10–10
1.6 × 10–9
1.1 × 10–8

6.7 × 10–10
4.2 × 10–10
6.7 × 10–10
5.7 × 10–9
1.2 × 10–8
1.5 × 10–8
4.9 × 10–9
1.0 × 10–8
1.2 × 10–8

2.4 × 10–8
1.6 × 10–9
1.3 × 10–9
2.2 × 10–10
1.5 × 10–10e(g)1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010

1.000
1.000
1.000
1.000
1.000

f1 forg>1a6.7 × 10–10
1.2 × 10–9
8.4 × 10–9

3.8 × 10–10
2.6 × 10–10
6.0 × 10–10
3.0 × 10–9
8.8 × 10–9
1.2 × 10–8
3.6 × 10–9
7.7 × 10–9
8.5 × 10–9

1.7 × 10–8
1.0 × 10–9
9.7 × 10–10
1.4 × 10–10
1.0 × 10–10e(g)Age 1–2 a

3.3 × 10–10
5.6 × 10–10
4.2 × 10–9

2.6 × 10–10
1.7 × 10–10
3.8 × 10–10
1.4 × 10–9
5.3 × 10–9
7.2 × 10–9
1.7 × 10–9
4.2 × 10–9
4.6 × 10–9

7.5 × 10–9
4.4 × 10–10
4.7 × 10–10
6.5 × 10–11
4.8 × 10–11

e(g)

2–7 a

2.2 × 10–10
3.6 × 10–10
2.8 × 10–9

3.3 × 10–10
1.7 × 10–10
2.4 × 10–10
1.0 × 10–9
3.9 × 10–9
5.1 × 10–9
1.1 × 10–9
2.9 × 10–9
3.3 × 10–9

4.5 × 10–9
2.6 × 10–10
2.9 × 10–10
4.0 × 10–11
3.0 × 10–11

e(g)7–12 a

1.4 × 10–10
2.3 × 10–10
1.7 × 10–9

3.3 × 10–10
1.6 × 10–10
1.9 × 10–10
7.6 × 10–10
3.5 × 10–9
4.6 × 10–9
6.1 × 10–10
2.4 × 10–9
2.6 × 10–9

2.5 × 10–9
1.5 × 10–10
1.7 × 10–10
2.4 × 10–11
1.8 × 10–11

e(g)12–17 a1.1 × 10–10
1.8 × 10–10
1.4 × 10–9

1.7 × 10–10
9.5 × 10–11
1.8 × 10–10
4.6 × 10–10
2.7 × 10–9
3.7 × 10–9
5.5 × 10–10
1.9 × 10–9
2.1 × 10–9

2.1 × 10–9
1.2 × 10–10
1.4 × 10–10
2.0 × 10–11
1.5 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

273

3.08 hTi–45

0.543 h16.2 d

330 d

V‑47

V‑48

V‑49

Vanadium47.3 a83.8 d3.35 d1.82 d
0.956 hPhysicalhalf-life

Ti‑44

Titanium

Sc‑46
Sc‑47
Sc‑48
Sc‑49

Radionuclidea

F
M
F
M
F
M

F
M
S
F
M
S

S
S
S
S

Type

0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020

0.001
0.001
0.001
0.001

f1

Age ≤ 1 a

2.8 × 10–8
4.0 × 10–9
7.8 × 10–9
3.9 × 10–10

1.8 × 10–10
2.8 × 10–10
8.4 × 10–9
1.4 × 10–8
2.0 × 10–10
2.8 × 10–10
0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4e(g)3.1 × 10–7
1.7 × 10–7
3.2 × 10–7
4.4 × 10–10
7.4 × 10–10
7.7 × 10–10

f1 forg>1a

1.2 × 10–10
1.9 × 10–10
6.4 × 10–9
1.1 × 10–8
1.6 × 10–10
2.1 × 10–10

2.6 × 10–7
1.5 × 10–7
3.1 × 10–7
3.2 × 10–10
5.2 × 10–10
5.5 × 10–10

2.3 × 10–8
2.8 × 10–9
5.9 × 10–9
2.4 × 10–10e(g)Age 1–2 a

5.6 × 10–11
8.6 × 10–11
3.3 × 10–9
6.3 × 10–9
7.7 × 10–11
1.1 × 10–10

1.5 × 10–7
9.2 × 10–8
2.1 × 10–7
1.5 × 10–10
2.5 × 10–10
2.7 × 10–10

1.4 × 10–8
1.5 × 10–9
3.1 × 10–9
1.1 × 10–10

e(g)

2–7 a

3.5 × 10–11
5.5 × 10–11
2.1 × 10–9
4.3 × 10–9
4.3 × 10–11
6.3 × 10–11

9.6 × 10–8
5.9 × 10–8
1.5 × 10–7
9.1 × 10–11
1.6 × 10–10
1.7 × 10–10

9.8 × 10–9
1.1 × 10–9
2.0 × 10–9
7.1 × 10–11

e(g)7–12 a2.1 × 10–11
3.5 × 10–11
1.3 × 10–9
2.9 × 10–9
2.5 × 10–11
4.0 × 10–11

6.6 × 10–8
4.6 × 10–8
1.3 × 10–7
5.1 × 10–11
1.1 × 10–10
1.1 × 10–10

8.4 × 10–9
9.2 × 10–10
1.4 × 10–9
4.7 × 10–11

e(g)12–17 a1.7 × 10–11
2.9 × 10–11
1.1 × 10–9
2.4 × 10–9
2.1 × 10–11
3.4 × 10–11

6.1 × 10–8
4.2 × 10–8
1.2 × 10–7
4.2 × 10–11
8.8 × 10–11
9.3 × 10–11

6.8 × 10–9
7.3 × 10–10
1.1 × 10–9
4.0 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

274

0.702 h27.7 d

Cr‑49

Cr‑51

0.770 h5.59 d

0.352 h3.70 × 106 a

312 d

Mn‑51

Mn‑52

Mn‑52m

Mn‑53

Mn‑54

Manganese

23.0 hPhysicalhalf-life

Cr‑48

ChromiumRadionuclidea

F
M
F
M
F
M
F
M
F
M

F
M
S
F
M
S
F
M
S

Type

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

f1

Age ≤ 1 a

2.5 × 10–10
4.0 × 10–10
7.0 × 10–9
8.6 × 10–9
1.9 × 10–10
2.8 × 10–10
3.2 × 10–10
4.6 × 10–10
5.2 × 10–9
7.5 × 10–9

7.6 × 10–10
1.1 × 10–9
1.2 × 10–9
1.9 × 10–10
3.0 × 10–10
3.1 × 10–10
1.7 × 10–10
2.6 × 10–10
2.6 × 10–10

e(g)

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1 forg>1a

1.7 × 10–10
2.7 × 10–10
5.5 × 10–9
6.8 × 10–9
1.3 × 10–10
1.9 × 10–10
2.2 × 10–10
3.4 × 10–10
4.1 × 10–9
6.2 × 10–9

6.0 × 10–10
9.1 × 10–10
9.8 × 10–10
1.3 × 10–10
2.0 × 10–10
2.1 × 10–10
1.3 × 10–10
1.9 × 10–10
2.1 × 10–10e(g)Age 1–2 a

7.5 × 10–11
1.2 × 10–10
2.9 × 10–9
3.7 × 10–9
6.1 × 10–11
8.7 × 10–11
1.1 × 10–10
1.7 × 10–10
2.2 × 10–9
3.8 × 10–9

3.1 × 10–10
5.1 × 10–10
5.5 × 10–10
6.0 × 10–11
9.5 × 10–11
9.9 × 10–11
6.3 × 10–11
1.0 × 10–10
1.0 × 10–10

e(g)

2–7 a

4.6 × 10–11
7.8 × 10–11
1.8 × 10–9
2.4 × 10–9
3.8 × 10–11
5.5 × 10–11
6.0 × 10–11
1.0 × 10–10
1.5 × 10–9
2.4 × 10–9

2.0 × 10–10
3.4 × 10–10
3.7 × 10–10
3.7 × 10–11
6.1 × 10–11
6.4 × 10–11
4.0 × 10–11
6.4 × 10–11
6.6 × 10–11

e(g)7–12 a2.7 × 10–11
5.0 × 10–11
1.1 × 10–9
1.7 × 10–9
2.2 × 10–11
3.4 × 10–11
3.4 × 10–11
6.4 × 10–11
9.9 × 10–10
1.9 × 10–9

1.2 × 10–10
2.5 × 10–10
2.8 × 10–10
2.2 × 10–11
4.0 × 10–11
4.2 × 10–11
2.4 × 10–11
3.9 × 10–11
4.5 × 10–11

e(g)12–17 a2.3 × 10–11
4.1 × 10–11
9.4 × 10–10
1.4 × 10–9
1.9 × 10–11
2.9 × 10–11
2.9 × 10–11
5.4 × 10–11
8.5 × 10–10
1.5 × 10–9

9.9 × 10–11
2.0 × 10–10
2.2 × 10–10
1.9 × 10–11
3.3 × 10–11
3.5 × 10–11
2.0 × 10–11
3.2 × 10–11
3.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

275

44.5 d

1.00 × 105 a

Fe‑59

Fe‑60

Co‑55

17.5 h2.70 aFe‑55

Cobaltd8.28 h

2.58 hPhysicalhalf-life

Fe‑52

Ironc

Mn‑56

Radionuclidea

F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

F
M

Type

0.600
0.200
0.020

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

0.200
0.200

f1

Age ≤ 1 a

6.9 × 10–10
1.1 × 10–9

2.2 × 10–9
4.1 × 10–9
4.6 × 10–9

0.100
0.100
0.010

0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010

0.100
0.100

e(g)

5.2 × 10–9
5.8 × 10–9
6.0 × 10–9
4.2 × 10–9
1.9 × 10–9
1.0 × 10–9
2.1 × 10–8
1.8 × 10–8
1.7 × 10–8
4.4 × 10–7
2.0 × 10–7
9.3 × 10–8

f1 forg>1a

1.8 × 10–9
3.1 × 10–9
3.3 × 10–9

3.6 × 10–9
4.1 × 10–9
4.2 × 10–9
3.2 × 10–9
1.4 × 10–9
8.5 × 10–10
1.3 × 10–8
1.3 × 10–8
1.3 × 10–8
3.9 × 10–7
1.7 × 10–7
8.8 × 10–8

4.9 × 10–10
7.8 × 10–10e(g)Age 1–2 a

9.0 × 10–10
1.5 × 10–9
1.6 × 10–9

1.5 × 10–9
1.9 × 10–9
2.0 × 10–9
2.2 × 10–9
9.9 × 10–10
5.0 × 10–10
7.1 × 10–9
7.9 × 10–9
8.1 × 10–9
3.5 × 10–7
1.6 × 10–7
6.7 × 10–8

2.3 × 10–10
3.7 × 10–10

e(g)

2–7 a

5.5 × 10–10
9.8 × 10–10
1.1 × 10–9

8.9 × 10–10
1.2 × 10–9
1.3 × 10–9
1.4 × 10–9
6.2 × 10–10
2.9 × 10–10
4.2 × 10–9
5.5 × 10–9
5.8 × 10–9
3.2 × 10–7
1.4 × 10–7
5.2 × 10–8

1.4 × 10–10
2.4 × 10–10

e(g)7–12 a3.1 × 10–10
6.1 × 10–10
6.6 × 10–10

4.9 × 10–10
7.4 × 10–10
7.7 × 10–10
9.4 × 10–10
4.4 × 10–10
2.0 × 10–10
2.6 × 10–9
4.6 × 10–9
5.1 × 10–9
2.9 × 10–7
1.4 × 10–7
4.9 × 10–8

7.8 × 10–11
1.5 × 10–10

e(g)12–17 a2.7 × 10–10
5.0 × 10–10
5.3 × 10–10

3.9 × 10–10
6.0 × 10–10
6.3 × 10–10
7.7 × 10–10
3.8 × 10–10
1.8 × 10–10
2.2 × 10–9
3.7 × 10–9
4.0 × 10–9
2.8 × 10–7
1.4 × 10–7
4.9 × 10–8

6.4 × 10–11
1.2 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

276

78.7 d271 d70.8 d

9.15 h5.27 a0.174 h1.65 h

Co‑57

Co‑58

Co‑58m

Co‑60

Co‑60mCo‑61

Physicalhalf-life

Co‑56

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010

e(g)
1.4 × 10–8
2.5 × 10–8
2.9 × 10–8
1.5 × 10–9
2.8 × 10–9
4.4 × 10–9
4.0 × 10–9
7.3 × 10–9
9.0 × 10–9
4.8 × 10–11
1.1 × 10–10
1.3 × 10–10
3.0 × 10–8
4.2 × 10–8
9.2 × 10–8
4.4 × 10–12
7.1 × 10–12
7.6 × 10–12
2.1 × 10–10
4.0 × 10–10
4.3 × 10–10

1.0 × 10–8
2.1 × 10–8
2.5 × 10–8
1.1 × 10–9
2.2 × 10–9
3.7 × 10–9
3.0 × 10–9
6.5 × 10–9
7.5 × 10–9
3.6 × 10–11
7.6 × 10–11
9.0 × 10–11
2.3 × 10–8
3.4 × 10–8
8.6 × 10–8
2.8 × 10–12
4.7 × 10–12
5.1 × 10–12
1.4 × 10–10
2.7 × 10–10
2.8 × 10–10e(g)Age 1–2 a

5.5 × 10–9
1.1 × 10–8
1.5 × 10–8
5.6 × 10–10
1.3 × 10–9
2.3 × 10–9
1.6 × 10–9
3.5 × 10–9
4.5 × 10–9
1.7 × 10–11
3.8 × 10–11
4.5 × 10–11
1.4 × 10–8
2.1 × 10–8
5.9 × 10–8
1.5 × 10–12
2.7 × 10–12
2.9 × 10–12
6.0 × 10–11
1.2 × 10–10
1.3 × 10–10

e(g)

2–7 a

3.5 × 10–9
7.4 × 10–9
1.0 × 10–8
3.7 × 10–10
8.5 × 10–10
1.5 × 10–9
1.0 × 10–9
2.4 × 10–9
3.1 × 10–9
1.1 × 10–11
2.4 × 10–11
3.0 × 10–11
8.9 × 10–9
1.5 × 10–8
4.0 × 10–8
1.0 × 10–12
1.8 × 10–12
2.0 × 10–12
3.8 × 10–11
8.2 × 10–11
8.8 × 10–11

e(g)7–12 a2.2 × 10–9
5.8 × 10–9
8.0 × 10–9
2.3 × 10–10
6.7 × 10–10
1.2 × 10–9
6.4 × 10–10
2.0 × 10–9
2.6 × 10–9
5.9 × 10–12
1.6 × 10–11
2.0 × 10–11
6.1 × 10–9
1.2 × 10–8
3.4 × 10–8
8.3 × 10–13
1.5 × 10–12
1.7 × 10–12
2.2 × 10–11
5.7 × 10–11
6.1 × 10–11

e(g)12–17 a1.8 × 10–9
4.8 × 10–9
6.7 × 10–9
1.9 × 10–10
5.5 × 10–10
1.0 × 10–9
5.3 × 10–10
1.6 × 10–9
2.1 × 10–9
5.2 × 10–12
1.3 × 10–11
1.7 × 10–11
5.2 × 10–9
1.0 × 10–8
3.1 × 10–8
6.9 × 10–13
1.2 × 10–12
1.4 × 10–12
1.9 × 10–11
4.7 × 10–11
5.1 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

277

6.10 d1.50 d7.50 × 104 a

96.0 a2.52 h

Ni‑57

Ni‑59

Ni‑63

Ni‑65

0.232 hPhysicalhalf-life

Ni‑56

Nickel

Co‑62mRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020

0.600
0.200
0.020

f1

Age ≤ 1 a

1.4 × 10–10
1.9 × 10–10
2.0 × 10–10

0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010

0.100
0.100
0.010

e(g)

3.3 × 10–9
4.9 × 10–9
5.5 × 10–9
2.2 × 10–9
3.6 × 10–9
3.9 × 10–9
9.6 × 10–10
7.9 × 10–10
1.7 × 10–9
2.3 × 10–9
2.5 × 10–9
4.8 × 10–9
4.4 × 10–10
7.7 × 10–10
8.1 × 10–10

f1 forg>1a2.8 × 10–9
4.1 × 10–9
4.6 × 10–9
1.8 × 10–9
2.8 × 10–9
3.0 × 10–9
8.1 × 10–10
6.2 × 10–10
1.5 × 10–9
2.0 × 10–9
1.9 × 10–9
4.3 × 10–9
3.0 × 10–10
5.2 × 10–10
5.5 × 10–10

9.5 × 10–11
1.3 × 10–10
1.3 × 10–10e(g)Age 1–2 a

1.5 × 10–9
2.3 × 10–9
2.7 × 10–9
8.9 × 10–10
1.5 × 10–9
1.5 × 10–9
4.5 × 10–10
3.4 × 10–10
9.5 × 10–10
1.1 × 10–9
1.1 × 10–9
2.7 × 10–9
1.4 × 10–10
2.4 × 10–10
2.6 × 10–10

4.5 × 10–11
6.1 × 10–11
6.3 × 10–11

e(g)

2–7 a

9.3 × 10–10
1.5 × 10–9
1.8 × 10–9
5.5 × 10–10
9.5 × 10–10
1.0 × 10–9
2.8 × 10–10
2.1 × 10–10
5.9 × 10–10
6.7 × 10–10
7.0 × 10–10
1.7 × 10–9
8.5 × 10–11
1.6 × 10–10
1.7 × 10–10

2.8 × 10–11
3.8 × 10–11
4.0 × 10–11

e(g)7–12 a5.8 × 10–10
1.1 × 10–9
1.3 × 10–9
3.1 × 10–10
6.2 × 10–10
6.6 × 10–10
1.9 × 10–10
1.4 × 10–10
4.6 × 10–10
4.6 × 10–10
5.3 × 10–10
1.3 × 10–9
4.9 × 10–11
1.0 × 10–10
1.1 × 10–10

1.7 × 10–11
2.4 × 10–11
2.5 × 10–11

e(g)12–17 a4.9 × 10–10
8.7 × 10–10
1.0 × 10–9
2.5 × 10–10
5.0 × 10–10
5.3 × 10–10
1.8 × 10–10
1.3 × 10–10
4.4 × 10–10
4.4 × 10–10
4.8 × 10–10
1.3 × 10–9
4.1 × 10–11
8.5 × 10–11
9.0 × 10–11

1.4 × 10–11
2.0 × 10–11
2.1 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

278

12.7 h

2.58 d

Cu‑64

Cu‑67

Zn‑62

9.26 h

3.41 h

Cu‑61

Zinc

0.387 h2.27 dPhysicalhalf-life

Cu‑60

CopperNi‑66

Radionuclidea

F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

1.000
0.200
0.020

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.100
0.100
0.020

f1

Age ≤ 1 a

5.7 × 10–9
1.3 × 10–8
1.5 × 10–8

1.7 × 10–9
4.5 × 10–9
5.1 × 10–9

0.500
0.100
0.010

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

0.050
0.050
0.010

e(g)

2.1 × 10–10
3.0 × 10–10
3.1 × 10–10
3.1 × 10–10
4.9 × 10–10
5.1 × 10–10
2.8 × 10–10
5.5 × 10–10
5.8 × 10–10
9.5 × 10–10
2.3 × 10–9
2.5 × 10–9

f1 forg>1a

1.7 × 10–9
3.5 × 10–9
3.4 × 10–9

1.6 × 10–10
2.2 × 10–10
2.2 × 10–10
2.7 × 10–10
4.4 × 10–10
4.5 × 10–10
2.7 × 10–10
5.4 × 10–10
5.7 × 10–10
8.0 × 10–10
2.0 × 10–9
2.1 × 10–9

3.8 × 10–9
9.4 × 10–9
1.0 × 10–8e(g)Age 1–2 a

7.7 × 10–10
1.6 × 10–9
1.8 × 10–9

7.5 × 10–11
1.0 × 10–10
1.1 × 10–10
1.3 × 10–10
2.1 × 10–10
2.2 × 10–10
1.2 × 10–10
2.7 × 10–10
2.9 × 10–10
3.5 × 10–10
1.1 × 10–9
1.2 × 10–9

1.6 × 10–9
4.5 × 10–9
5.0 × 10–9

e(g)

2–7 a

4.6 × 10–10
1.0 × 10–9
1.1 × 10–9

4.6 × 10–11
6.5 × 10–11
6.7 × 10–11
7.9 × 10–11
1.4 × 10–10
1.4 × 10–10
7.6 × 10–11
1.9 × 10–10
2.0 × 10–10
2.2 × 10–10
8.1 × 10–10
8.9 × 10–10

1.0 × 10–9
2.9 × 10–9
3.2 × 10–9e(g)7–12 a2.5 × 10–10
6.0 × 10–10
6.6 × 10–10

2.8 × 10–11
4.0 × 10–11
4.2 × 10–11
4.5 × 10–11
9.1 × 10–11
9.6 × 10–11
4.2 × 10–11
1.4 × 10–10
1.3 × 10–10
1.2 × 10–10
6.9 × 10–10
7.7 × 10–10

5.1 × 10–10
2.0 × 10–9
2.2 × 10–9e(g)12–17 a2.0 × 10–10
5.0 × 10–10
5.5 × 10–10

2.3 × 10–11
3.3 × 10–11
3.4 × 10–11
3.7 × 10–11
7.4 × 10–11
7.8 × 10–11
3.5 × 10–11
1.1 × 10–10
1.2 × 10–10
1.0 × 10–10
5.5 × 10–10
6.1 × 10–10

4.2 × 10–10
1.6 × 10–9
1.8 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

279

0.950 h13.8 h3.92 h

1.94 dZn‑69

Zn‑69mZn‑71m

Zn‑72

Ga‑65

0.253 h

244 d

Zn‑65

Gallium

0.635 hPhysicalhalf-life

Zn‑63

Radionuclidea

F
M

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type

0.010
0.010

1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

2.1 × 10–10
3.4 × 10–10
3.6 × 10–10
1.5 × 10–8
8.5 × 10–9
7.6 × 10–9
1.1 × 10–10
2.2 × 10–10
2.3 × 10–10
6.6 × 10–10
2.1 × 10–9
2.2 × 10–9
6.2 × 10–10
1.3 × 10–9
1.4 × 10–9
4.3 × 10–9
8.8 × 10–9
9.7 × 10–9

0.001
0.001

0.500
0.100
0.010
0.500
0.100
0.010
0.500
0.100
0.010
0.500
0.100
0.010
0.500
0.100
0.010
0.500
0.100
0.010

e(g)

1.1 × 10–10
1.6 × 10–10

f1 forg>1a

7.3 × 10–11
1.1 × 10–10

1.4 × 10–10
2.3 × 10–10
2.4 × 10–10
1.0 × 10–8
6.5 × 10–9
6.7 × 10–9
7.4 × 10–11
1.4 × 10–10
1.5 × 10–10
6.7 × 10–10
1.5 × 10–9
1.7 × 10–9
5.5 × 10–10
9.4 × 10–10
1.0 × 10–9
3.5 × 10–9
6.5 × 10–9
7.0 × 10–9e(g)Age 1–2 a

3.4 × 10–11
4.8 × 10–11

6.5 × 10–11
1.0 × 10–10
1.1 × 10–10
5.7 × 10–9
3.7 × 10–9
4.4 × 10–9
3.2 × 10–11
6.5 × 10–11
6.9 × 10–11
3.0 × 10–10
7.5 × 10–10
8.2 × 10–10
2.6 × 10–10
4.6 × 10–10
4.9 × 10–10
1.7 × 10–9
3.4 × 10–9
3.6 × 10–9

e(g)

2–7 a

2.1 × 10–11
3.1 × 10–11

4.0 × 10–11
6.6 × 10–11
6.9 × 10–11
3.8 × 10–9
2.4 × 10–9
2.9 × 10–9
2.1 × 10–11
4.4 × 10–11
4.7 × 10–11
1.8 × 10–10
5.0 × 10–10
5.4 × 10–10
1.6 × 10–10
2.9 × 10–10
3.1 × 10–10
1.0 × 10–9
2.3 × 10–9
2.4 × 10–9e(g)7–12 a1.3 × 10–11
2.0 × 10–11

2.4 × 10–11
4.2 × 10–11
4.4 × 10–11
2.5 × 10–9
1.9 × 10–9
2.4 × 10–9
1.2 × 10–11
3.1 × 10–11
3.4 × 10–11
9.9 × 10–11
3.0 × 10–10
3.3 × 10–10
9.1 × 10–11
1.9 × 10–10
2.0 × 10–10
5.9 × 10–10
1.5 × 10–9
1.6 × 10–9e(g)12–17 a1.1 × 10–11
1.7 × 10–11

2.0 × 10–11
3.5 × 10–11
3.7 × 10–11
2.2 × 10–9
1.6 × 10–9
2.0 × 10–9
1.1 × 10–11
2.6 × 10–11
2.8 × 10–11
8.2 × 10–11
2.4 × 10–10
2.7 × 10–10
7.4 × 10–11
1.5 × 10–10
1.6 × 10–10
4.9 × 10–10
1.2 × 10–9
1.3 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

280

3.26 d

1.13 h

0.353 h14.1 h

4.91 h

Ga‑67

Ga‑68

Ga‑70

Ga‑72

Ga‑73

2.27 h0.312 h288 d1.63 d

Ge‑66

Ge‑67

Ge‑68

Ge‑69

Germanium

9.40 hPhysicalhalf-life

Ga‑66

Radionuclidea

F
M
F
M
F
M
F
M

F
M
F
M
F
M
F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1

Age ≤ 1 a

2.8 × 10–9
4.5 × 10–9
6.4 × 10–10
1.4 × 10–9
2.9 × 10–10
4.6 × 10–10
9.5 × 10–11
1.5 × 10–10
2.9 × 10–9
4.5 × 10–9
6.7 × 10–10
1.2 × 10–9

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

e(g)

4.5 × 10–10
6.4 × 10–10
1.7 × 10–10
2.5 × 10–10
5.4 × 10–9
6.0 × 10–8
1.2 × 10–9
1.8 × 10–9

f1 forg>1a

3.5 × 10–10
4.8 × 10–10
1.1 × 10–10
1.6 × 10–10
3.8 × 10–9
5.0 × 10–8
9.0 × 10–10
1.4 × 10–9

2.0 × 10–9
3.1 × 10–9
4.6 × 10–10
1.0 × 10–9
1.9 × 10–10
3.1 × 10–10
6.0 × 10–11
9.6 × 10–11
2.2 × 10–9
3.3 × 10–9
4.5 × 10–10
8.4 × 10–10e(g)Age 1–2 a

1.8 × 10–10
2.5 × 10–10
4.9 × 10–11
7.3 × 10–11
1.8 × 10–9
3.0 × 10–8
4.6 × 10–10
7.4 × 10–10

9.2 × 10–10
1.5 × 10–9
2.2 × 10–10
5.0 × 10–10
8.8 × 10–11
1.4 × 10–10
2.6 × 10–11
4.3 × 10–11
1.0 × 10–9
1.6 × 10–9
2.0 × 10–10
4.0 × 10–10

e(g)

2–7 a

1.1 × 10–10
1.6 × 10–10
3.1 × 10–11
4.6 × 10–11
1.1 × 10–9
2.0 × 10–8
2.8 × 10–10
4.9 × 10–10

5.7 × 10–10
9.2 × 10–10
1.4 × 10–10
3.6 × 10–10
5.4 × 10–11
9.2 × 10–11
1.6 × 10–11
2.8 × 10–11
6.4 × 10–10
1.0 × 10–9
1.2 × 10–10
2.6 × 10–10

e(g)7–12 a6.7 × 10–11
1.1 × 10–10
1.8 × 10–11
2.9 × 10–11
6.3 × 10–10
1.6 × 10–8
1.7 × 10–10
3.6 × 10–10

3.0 × 10–10
5.3 × 10–10
7.7 × 10–11
3.0 × 10–10
3.1 × 10–11
5.9 × 10–11
1.0 × 10–11
1.8 × 10–11
3.6 × 10–10
6.5 × 10–10
6.4 × 10–11
1.7 × 10–10

e(g)12–17 a5.4 × 10–11
9.1 × 10–11
1.5 × 10–11
2.5 × 10–11
5.2 × 10–10
1.4 × 10–8
1.3 × 10–10
2.9 × 10–10

2.5 × 10–10
4.4 × 10–10
6.4 × 10–11
2.4 × 10–10
2.6 × 10–11
4.9 × 10–11
8.8 × 10–12
1.6 × 10–11
2.9 × 10–10
5.3 × 10–10
5.4 × 10–11
1.4 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

281

11.3 h1.45 h

Ge‑77

Ge‑78

As‑69
As‑70
As‑71
As‑72
As‑73
As‑74
As‑76
As‑77
As‑78

0.253 h0.876 h2.70 d1.08 d80.3 d17.8 d
1.10 d
1.62 d1.51 h1.38 h

Ge‑75

Arsenic

11.8 dPhysicalhalf-life

Ge‑71

Radionuclidea

M
M
M
M
M
M
M
M
M

F
M
F
M
F
M
F
M

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

Age ≤ 1 a

6.0 × 10–11
1.2 × 10–10
1.6 × 10–10
2.9 × 10–10
1.3 × 10–9
2.3 × 10–9
4.3 × 10–10
7.3 × 10–10

0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500
0.500

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

e(g)

2.1 × 10–10
5.7 × 10–10
2.2 × 10–9
5.9 × 10–9
5.4 × 10–9
1.1 × 10–8
5.1 × 10–9
2.2 × 10–9
8.0 × 10–10

f1 forg>1a

1.4 × 10–10
4.3 × 10–10
1.9 × 10–9
5.7 × 10–9
4.0 × 10–9
8.4 × 10–9
4.6 × 10–9
1.7 × 10–9
5.8 × 10–10

4.3 × 10–11
8.6 × 10–11
1.0 × 10–10
1.9 × 10–10
9.5 × 10–10
1.7 × 10–9
2.9 × 10–10
5.0 × 10–10e(g)Age 1–2 a

6.3 × 10–11
2.1 × 10–10
1.0 × 10–9
2.7 × 10–9
2.3 × 10–9
4.7 × 10–9
2.2 × 10–9
8.9 × 10–10
2.7 × 10–10

2.0 × 10–11
4.1 × 10–11
4.3 × 10–11
8.9 × 10–11
4.7 × 10–10
8.8 × 10–10
1.4 × 10–10
2.5 × 10–10

e(g)

2–7 a

4.0 × 10–11
1.3 × 10–10
6.8 × 10–10
1.7 × 10–9
1.5 × 10–9
3.3 × 10–9
1.4 × 10–9
6.2 × 10–10
1.7 × 10–10

1.1 × 10–11
2.4 × 10–11
2.8 × 10–11
6.1 × 10–11
2.9 × 10–10
6.0 × 10–10
8.9 × 10–11
1.6 × 10–10

e(g)7–12 a2.5 × 10–11
8.3 × 10–11
5.0 × 10–10
1.1 × 10–9
1.2 × 10–9
2.6 × 10–9
8.8 × 10–10
5.0 × 10–10
1.1 × 10–10

6.1 × 10–12
1.3 × 10–11
1.7 × 10–11
4.4 × 10–11
1.7 × 10–10
4.5 × 10–10
5.5 × 10–11
1.2 × 10–10

e(g)12–17 a2.1 × 10–11
6.7 × 10–11
4.0 × 10–10
9.0 × 10–10
1.0 × 10–9
2.1 × 10–9
7.4 × 10–10
3.9 × 10–10
8.9 × 10–11

4.8 × 10–12
1.1 × 10–11
1.5 × 10–11
3.6 × 10–11
1.4 × 10–10
3.7 × 10–10
4.5 × 10–11
9.5 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

282

0.683 h7.15 h

0.650 h120 d6.50 × 104 a

0.308 h0.954 hSe‑73

Se‑73m

Se‑75

Se‑79

Se‑81

Se‑81mPhysicalhalf-life

Se‑70

SeleniumRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

3.9 × 10–10
6.5 × 10–10
6.8 × 10–10
7.7 × 10–10
1.6 × 10–9
1.8 × 10–9
9.3 × 10–11
1.8 × 10–10
1.9 × 10–10
7.8 × 10–9
5.4 × 10–9
5.6 × 10–9
1.6 × 10–8
1.4 × 10–8
2.3 × 10–8
8.6 × 10–11
1.3 × 10–10
1.4 × 10–10
1.8 × 10–10
3.8 × 10–10
4.1 × 10–10

e(g)
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010

f1 forg>1a

3.0 × 10–10
4.7 × 10–10
4.8 × 10–10
6.5 × 10–10
1.2 × 10–9
1.3 × 10–9
7.2 × 10–11
1.3 × 10–10
1.3 × 10–10
6.0 × 10–9
4.5 × 10–9
4.7 × 10–9
1.3 × 10–8
1.1 × 10–8
2.0 × 10–8
5.4 × 10–11
8.5 × 10–11
8.9 × 10–11
1.2 × 10–10
2.5 × 10–10
2.7 × 10–10e(g)Age 1–2 a

1.5 × 10–10
2.3 × 10–10
2.3 × 10–10
3.3 × 10–10
5.9 × 10–10
6.3 × 10–10
3.5 × 10–11
6.1 × 10–11
6.5 × 10–11
3.4 × 10–9
2.5 × 10–9
2.9 × 10–9
7.7 × 10–9
6.9 × 10–9
1.3 × 10–8
2.3 × 10–11
3.8 × 10–11
3.9 × 10–11
5.4 × 10–11
1.2 × 10–10
1.3 × 10–10

e(g)

2–7 a

9.0 × 10–11
1.4 × 10–10
1.5 × 10–10
2.1 × 10–10
3.8 × 10–10
4.0 × 10–10
2.3 × 10–11
3.9 × 10–11
4.1 × 10–11
2.5 × 10–9
1.7 × 10–9
2.0 × 10–9
5.6 × 10–9
4.9 × 10–9
8.7 × 10–9
1.5 × 10–11
2.5 × 10–11
2.6 × 10–11
3.4 × 10–11
8.0 × 10–11
8.5 × 10–11

e(g)7–12 a5.1 × 10–11
8.9 × 10–11
9.4 × 10–11
1.0 × 10–10
2.4 × 10–10
2.6 × 10–10
1.1 × 10–11
2.5 × 10–11
2.6 × 10–11
1.2 × 10–9
1.3 × 10–9
1.6 × 10–9
1.5 × 10–9
3.3 × 10–9
7.6 × 10–9
9.2 × 10–12
1.6 × 10–11
1.7 × 10–11
1.9 × 10–11
5.8 × 10–11
6.2 × 10–11

e(g)12–17 a4.2 × 10–11
7.3 × 10–11
7.6 × 10–11
8.0 × 10–11
1.9 × 10–10
2.1 × 10–10
9.2 × 10–12
2.0 × 10–11
2.2 × 10–11
1.0 × 10–9
1.1 × 10–9
1.3 × 10–9
1.1 × 10–9
2.6 × 10–9
6.8 × 10–9
8.0 × 10–12
1.4 × 10–11
1.5 × 10–11
1.6 × 10–11
4.7 × 10–11
5.1 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

283

0.422 h0.691 h1.63 h

16.2 h2.33 d0.290 h4.42 h1.47 dBr‑74m

Br‑75

Br‑76

Br‑77

Br‑80

Br‑80m

Br‑820.375 hPhysicalhalf-life

Br‑74

Bromine

Se‑83

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

F
M
S

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
0.200
0.020

f1

Age ≤ 1 a

1.7 × 10–10
2.7 × 10–10
2.8 × 10–10

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.800
0.100
0.010

e(g)

2.5 × 10–10
3.6 × 10–10
4.0 × 10–10
5.9 × 10–10
2.9 × 10–10
4.5 × 10–10
2.2 × 10–9
3.0 × 10–9
5.3 × 10–10
6.3 × 10–10
7.1 × 10–11
1.1 × 10–10
4.3 × 10–10
6.8 × 10–10
2.7 × 10–9
3.8 × 10–9

f1 forg>1a

1.8 × 10–10
2.5 × 10–10
2.8 × 10–10
4.1 × 10–10
2.1 × 10–10
3.1 × 10–10
1.7 × 10–9
2.3 × 10–9
4.4 × 10–10
5.1 × 10–10
4.4 × 10–11
6.5 × 10–11
2.8 × 10–10
4.5 × 10–10
2.2 × 10–9
3.0 × 10–9

1.2 × 10–10
1.9 × 10–10
2.0 × 10–10e(g)Age 1–2 a

8.6 × 10–11
1.2 × 10–10
1.3 × 10–10
1.9 × 10–10
9.7 × 10–11
1.5 × 10–10
8.4 × 10–10
1.2 × 10–9
2.2 × 10–10
2.7 × 10–10
1.8 × 10–11
2.8 × 10–11
1.2 × 10–10
2.1 × 10–10
1.2 × 10–9
1.7 × 10–9

5.8 × 10–11
9.2 × 10–11
9.6 × 10–11

e(g)

2–7 a

5.3 × 10–11
7.5 × 10–11
8.1 × 10–11
1.2 × 10–10
5.9 × 10–11
9.7 × 10–11
5.1 × 10–10
7.5 × 10–10
1.3 × 10–10
1.6 × 10–10
1.2 × 10–11
1.8 × 10–11
7.2 × 10–11
1.4 × 10–10
7.0 × 10–10
1.1 × 10–9

3.6 × 10–11
5.9 × 10–11
6.2 × 10–11

e(g)7–12 a3.2 × 10–11
4.6 × 10–11
4.8 × 10–11
7.5 × 10–11
3.5 × 10–11
6.5 × 10–11
3.0 × 10–10
5.0 × 10–10
7.7 × 10–11
1.1 × 10–10
6.9 × 10–12
1.1 × 10–11
4.0 × 10–11
9.3 × 10–11
4.2 × 10–10
7.9 × 10–10

2.1 × 10–11
3.9 × 10–11
4.1 × 10–11

e(g)12–17 a2.6 × 10–11
3.8 × 10–11
3.9 × 10–11
6.2 × 10–11
2.9 × 10–11
5.3 × 10–11
2.4 × 10–10
4.1 × 10–10
6.2 × 10–11
8.4 × 10–11
5.9 × 10–12
9.4 × 10–12
3.3 × 10–11
7.6 × 10–11
3.5 × 10–10
6.3 × 10–10

1.8 × 10–11
3.2 × 10–11
3.4 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

284

Sr‑80

Strontiume

Rb‑79
Rb-81
Rb‑81m
Rb‑82m
Rb‑83
Rb‑84
Rb‑86
Rb‑87
Rb‑88
Rb‑89

1.67 h

0.382 h4.58 h
0.533 h6.20 h86.2 d32.8 d18.7 d
4.70 × 1010 a
0.297 h0.253 h0.530 hBr‑84

Rubidium2.39 hPhysicalhalf-life

Br‑83

Radionuclidea

F
M
S

F
F
F
F
F
F
F
F
F
F

F
M
F
M

Type

0.600
0.200
0.020

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000

f1

Age ≤ 1 a

1.7 × 10–10
3.5 × 10–10
2.4 × 10–10
3.7 × 10–10

7.8 × 10–10
1.4 × 10–9
1.5 × 10–9

0.300
0.100
0.010

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

1.000
1.000
1.000
1.000

e(g)

1.6 × 10–10
3.2 × 10–10
6.2 × 10–11
8.6 × 10–10
4.9 × 10–9
8.6 × 10–9
1.2 × 10–8
6.0 × 10–9
1.9 × 10–10
1.4 × 10–10

f1 forg>1a5.4 × 10–10
9.0 × 10–10
9.4 × 10–10

1.1 × 10–10
2.5 × 10–10
4.6 × 10–11
7.3 × 10–10
3.8 × 10–9
6.4 × 10–9
7.7 × 10–9
4.1 × 10–9
1.2 × 10–10
9.3 × 10–11

1.1 × 10–10
2.3 × 10–10
1.6 × 10–10
2.4 × 10–10e(g)Age 1–2 a

2.4 × 10–10
4.1 × 10–10
4.3 × 10–10

5.0 × 10–11
1.2 × 10–10
2.2 × 10–11
3.9 × 10–10
2.0 × 10–9
3.1 × 10–9
3.4 × 10–9
1.8 × 10–9
5.2 × 10–11
4.3 × 10–11

4.7 × 10–11
1.1 × 10–10
7.1 × 10–11
1.1 × 10–10

e(g)

2–7 a

1.4 × 10–10
2.5 × 10–10
2.7 × 10–10

3.2 × 10–11
7.1 × 10–11
1.4 × 10–11
2.3 × 10–10
1.3 × 10–9
2.0 × 10–9
2.0 × 10–9
1.1 × 10–9
3.2 × 10–11
2.7 × 10–11

3.0 × 10–11
7.7 × 10–11
4.4 × 10–11
6.9 × 10–11

e(g)7–12 a7.9 × 10–11
1.5 × 10–10
1.6 × 10–10

1.9 × 10–11
4.2 × 10–11
8.5 × 10–12
1.4 × 10–10
7.9 × 10–10
1.2 × 10–9
1.1 × 10–9
6.0 × 10–10
1.9 × 10–11
1.6 × 10–11

1.8 × 10–11
5.9 × 10–11
2.6 × 10–11
4.4 × 10–11

e(g)12–17 a7.1 × 10–11
1.3 × 10–10
1.4 × 10–10

1.6 × 10–11
3.4 × 10–11
7.0 × 10–12
1.1 × 10–10
6.9 × 10–10
1.0 × 10–9
9.3 × 10–10
5.0 × 10–10
1.6 × 10–11
1.4 × 10–11

1.6 × 10–11
4.8 × 10–11
2.2 × 10–11
3.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

285

0.425 h25.0 d1.35 d64.8 d

1.16 h2.80 h50.5 d

Sr‑82

Sr‑83

Sr‑85

Sr‑85m

Sr-87mSr‑89

Physicalhalf-life

Sr‑81

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010

e(g)
2.1 × 10–10
3.3 × 10–10
3.4 × 10–10
2.8 × 10–8
5.5 × 10–8
6.1 × 10–8
1.4 × 10–9
2.5 × 10–9
2.8 × 10–9
4.4 × 10–9
4.3 × 10–9
4.4 × 10–9
2.4 × 10–11
3.1 × 10–11
3.2 × 10–11
9.7 × 10–11
1.6 × 10–10
1.7 × 10–10
1.5 × 10–8
3.3 × 10–8
3.9 × 10–8

1.5 × 10–10
2.2 × 10–10
2.3 × 10–10
1.5 × 10–8
4.0 × 10–8
4.6 × 10–8
1.1 × 10–9
1.9 × 10–9
2.0 × 10–9
2.3 × 10–9
3.1 × 10–9
3.7 × 10–9
1.9 × 10–11
2.5 × 10–11
2.6 × 10–11
7.8 × 10–11
1.2 × 10–10
1.2 × 10–10
7.3 × 10–9
2.4 × 10–8
3.0 × 10–8e(g)Age 1–2 a

6.7 × 10–11
1.0 × 10–10
1.1 × 10–10
6.6 × 10–9
2.1 × 10–8
2.5 × 10–8
5.5 × 10–10
9.5 × 10–10
1.0 × 10–9
1.1 × 10–9
1.8 × 10–9
2.2 × 10–9
9.6 × 10–12
1.3 × 10–11
1.3 × 10–11
3.8 × 10–11
5.9 × 10–11
6.2 × 10–11
3.2 × 10–9
1.3 × 10–8
1.7 × 10–8

e(g)

2–7 a

4.1 × 10–11
6.6 × 10–11
6.9 × 10–11
4.6 × 10–9
1.4 × 10–8
1.7 × 10–8
3.4 × 10–10
6.0 × 10–10
6.5 × 10–10
9.6 × 10–10
1.2 × 10–9
1.3 × 10–9
6.0 × 10–12
8.0 × 10–12
8.3 × 10–12
2.3 × 10–11
3.8 × 10–11
4.0 × 10–11
2.3 × 10–9
9.1 × 10–9
1.2 × 10–8

e(g)7–12 a2.4 × 10–11
4.2 × 10–11
4.4 × 10–11
3.2 × 10–9
1.0 × 10–8
1.2 × 10–8
2.0 × 10–10
3.9 × 10–10
4.2 × 10–10
8.3 × 10–10
8.8 × 10–10
1.0 × 10–9
3.7 × 10–12
5.1 × 10–12
5.4 × 10–12
1.3 × 10–11
2.5 × 10–11
2.6 × 10–11
1.7 × 10–9
7.3 × 10–9
9.3 × 10–9e(g)12–17 a2.1 × 10–11
3.5 × 10–11
3.7 × 10–11
2.1 × 10–9
8.9 × 10–9
1.1 × 10–8
1.6 × 10–10
3.1 × 10–10
3.4 × 10–10
3.8 × 10–10
6.4 × 10–10
8.1 × 10–10
2.9 × 10–12
4.1 × 10–12
4.3 × 10–12
1.1 × 10–11
2.0 × 10–11
2.1 × 10–11
1.0 × 10–9
6.1 × 10–9
7.9 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

286

9.50 h2.71 h

Sr‑91

Sr‑92

14.7 h0.800 h3.35 d107 d2.67 d

Y‑86

Y‑86m

Y‑87

Y‑88

Y‑90

Yttrium

29.1 aPhysicalhalf-life

Sr‑90

Radionuclidea

M
S
M
S
M
S
M
S
M
S

F
M
S
F
M
S
F
M
S

Type

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 a

1.3 × 10–7
1.5 × 10–7
4.2 × 10–7
1.4 × 10–9
3.1 × 10–9
3.5 × 10–9
9.0 × 10–10
1.9 × 10–9
2.2 × 10–9

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4

0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010

e(g)

3.7 × 10–9
3.8 × 10–9
2.2 × 10–10
2.3 × 10–10
2.7 × 10–9
2.8 × 10–9
1.9 × 10–8
2.0 × 10–8
1.3 × 10–8
1.3 × 10–8

f1 forg>1a2.9 × 10–9
3.0 × 10–9
1.7 × 10–10
1.8 × 10–10
2.1 × 10–9
2.2 × 10–9
1.6 × 10–8
1.7 × 10–8
8.4 × 10–9
8.8 × 10–9

5.2 × 10–8
1.1 × 10–7
4.0 × 10–7
1.1 × 10–9
2.2 × 10–9
2.5 × 10–9
7.1 × 10–10
1.4 × 10–9
1.5 × 10–9e(g)Age 1–2 a

1.5 × 10–9
1.5 × 10–9
8.7 × 10–11
9.0 × 10–11
1.1 × 10–9
1.1 × 10–9
1.0 × 10–8
9.8 × 10–9
4.0 × 10–9
4.2 × 10–9

3.1 × 10–8
6.5 × 10–8
2.7 × 10–7
5.2 × 10–10
1.1 × 10–9
1.2 × 10–9
3.3 × 10–10
6.5 × 10–10
7.0 × 10–10

e(g)

2–7 a

9.3 × 10–10
9.6 × 10–10
5.6 × 10–11
5.7 × 10–11
7.0 × 10–10
7.3 × 10–10
6.7 × 10–9
6.6 × 10–9
2.6 × 10–9
2.7 × 10–9

4.1 × 10–8
5.1 × 10–8
1.8 × 10–7
3.1 × 10–10
6.9 × 10–10
7.7 × 10–10
2.0 × 10–10
4.1 × 10–10
4.5 × 10–10

e(g)7–12 a5.6 × 10–10
5.8 × 10–10
3.4 × 10–11
3.5 × 10–11
4.7 × 10–10
5.0 × 10–10
4.9 × 10–9
5.4 × 10–9
1.7 × 10–9
1.8 × 10–9

5.3 × 10–8
5.0 × 10–8
1.6 × 10–7
1.7 × 10–10
4.4 × 10–10
4.9 × 10–10
1.0 × 10–10
2.5 × 10–10
2.7 × 10–10

e(g)12–17 a4.5 × 10–10
4.7 × 10–10
2.7 × 10–11
2.8 × 10–11
3.7 × 10–10
3.9 × 10–10
4.1 × 10–9
4.4 × 10–9
1.4 × 10–9
1.5 × 10–9

2.4 × 10–8
3.6 × 10–8
1.6 × 10–7
1.6 × 10–10
3.7 × 10–10
4.1 × 10–10
9.8 × 10–11
2.1 × 10–10
2.3 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

287

58.5 d0.828 h3.54 h10.1 h

0.318 h0.178 h

Y‑91

Y‑91m

Y‑92

Y‑93

Y‑94

Y‑95

16.5 h83.4 d

Zr‑86

Zr‑88

Zirconium

3.19 hPhysicalhalf-life

Y‑90m

Radionuclidea

F
M
S
F
M
S

M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type

0.020
0.020
0.020
0.020
0.020
0.020

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

f1

Age ≤ 1 a

7.2 × 10–10
7.5 × 10–10
3.9 × 10–8
4.3 × 10–8
7.0 × 10–11
7.4 × 10–11
1.8 × 10–9
1.9 × 10–9
4.4 × 10–9
4.6 × 10–9
2.8 × 10–10
2.9 × 10–10
1.5 × 10–10
1.6 × 10–10

0.002
0.002
0.002
0.002
0.002
0.002

1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4
1.0 × 10–4e(g)2.4 × 10–9
3.4 × 10–9
3.5 × 10–9
6.9 × 10–9
8.5 × 10–9
1.3 × 10–8

f1 forg>1a

1.9 × 10–9
2.6 × 10–9
2.7 × 10–9
8.3 × 10–9
7.8 × 10–9
1.2 × 10–8

5.7 × 10–10
6.0 × 10–10
3.0 × 10–8
3.4 × 10–8
5.5 × 10–11
5.9 × 10–11
1.2 × 10–9
1.2 × 10–9
2.9 × 10–9
3.0 × 10–9
1.8 × 10–10
1.9 × 10–10
9.8 × 10–11
1.0 × 10–10e(g)Age 1–2 a

9.5 × 10–10
1.3 × 10–9
1.4 × 10–9
5.6 × 10–9
5.1 × 10–9
7.7 × 10–9

2.8 × 10–10
2.9 × 10–10
1.6 × 10–8
1.9 × 10–8
2.9 × 10–11
3.1 × 10–11
5.3 × 10–10
5.5 × 10–10
1.3 × 10–9
1.4 × 10–9
8.1 × 10–11
8.4 × 10–11
4.4 × 10–11
4.5 × 10–11

e(g)

2–7 a

5.9 × 10–10
8.4 × 10–10
8.7 × 10–10
4.7 × 10–9
3.6 × 10–9
5.2 × 10–9

1.8 × 10–10
1.9 × 10–10
1.1 × 10–8
1.3 × 10–8
1.8 × 10–11
2.0 × 10–11
3.3 × 10–10
3.5 × 10–10
8.1 × 10–10
8.5 × 10–10
5.0 × 10–11
5.2 × 10–11
2.8 × 10–11
2.9 × 10–11

e(g)7–12 a3.4 × 10–10
5.2 × 10–10
5.4 × 10–10
3.6 × 10–9
3.0 × 10–9
4.3 × 10–9

1.1 × 10–10
1.2 × 10–10
8.4 × 10–9
1.0 × 10–8
1.2 × 10–11
1.4 × 10–11
2.0 × 10–10
2.1 × 10–10
4.7 × 10–10
5.0 × 10–10
3.1 × 10–11
3.3 × 10–11
1.8 × 10–11
1.8 × 10–11

e(g)12–17 a2.7 × 10–10
4.2 × 10–10
4.3 × 10–10
3.5 × 10–9
2.6 × 10–9
3.6 × 10–9

9.5 × 10–11
1.0 × 10–10
7.1 × 10–9
8.9 × 10–9
1.0 × 10–11
1.1 × 10–11
1.7 × 10–10
1.8 × 10–10
4.0 × 10–10
4.2 × 10–10
2.7 × 10–11
2.8 × 10–11
1.5 × 10–11
1.6 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

288

1.53 × 106 a

64.0 d

16.9 h

Zr‑93

Zr‑95

Zr‑97

0.238 h2.03 h

Nb‑88

Nb‑89

Niobium

3.27 dPhysicalhalf-life

Zr‑89

Radionuclidea

F
M
S
F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 a

2.6 × 10–9
3.7 × 10–9
3.9 × 10–9
3.5 × 10–9
3.3 × 10–9
7.0 × 10–9
1.2 × 10–8
2.0 × 10–8
2.4 × 10–8
5.0 × 10–9
7.8 × 10–9
8.2 × 10–9

0.010
0.010
0.010
0.010
0.010
0.010

0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002

e(g)

1.8 × 10–10
2.5 × 10–10
2.6 × 10–10
7.0 × 10–10
1.1 × 10–9
1.2 × 10–9

f1 forg>1a

1.3 × 10–10
1.8 × 10–10
1.8 × 10–10
4.8 × 10–10
7.6 × 10–10
7.9 × 10–10

2.0 × 10–9
2.8 × 10–9
2.9 × 10–9
4.8 × 10–9
3.1 × 10–9
6.4 × 10–9
1.1 × 10–8
1.6 × 10–8
1.9 × 10–8
3.4 × 10–9
5.3 × 10–9
5.6 × 10–9e(g)Age 1–2 a

6.3 × 10–11
8.5 × 10–11
8.7 × 10–11
2.2 × 10–10
3.6 × 10–10
3.7 × 10–10

9.9 × 10–10
1.5 × 10–9
1.5 × 10–9
5.3 × 10–9
2.8 × 10–9
4.5 × 10–9
6.4 × 10–9
9.7 × 10–9
1.2 × 10–8
1.5 × 10–9
2.8 × 10–9
2.9 × 10–9

e(g)

2–7 a

3.9 × 10–11
5.3 × 10–11
5.5 × 10–11
1.3 × 10–10
2.2 × 10–10
2.3 × 10–10

6.1 × 10–10
9.6 × 10–10
1.0 × 10–9
9.7 × 10–9
4.1 × 10–9
3.3 × 10–9
4.2 × 10–9
6.8 × 10–9
8.3 × 10–9
9.1 × 10–10
1.8 × 10–9
1.9 × 10–9e(g)7–12 a2.4 × 10–11
3.3 × 10–11
3.5 × 10–11
7.4 × 10–11
1.4 × 10–10
1.5 × 10–10

3.6 × 10–10
6.5 × 10–10
6.8 × 10–10
1.8 × 10–8
7.5 × 10–9
3.3 × 10–9
2.8 × 10–9
5.9 × 10–9
7.3 × 10–9
4.8 × 10–10
1.1 × 10–9
1.2 × 10–9e(g)12–17 a1.9 × 10–11
2.7 × 10–11
2.8 × 10–11
6.1 × 10–11
1.1 × 10–10
1.2 × 10–10

2.9 × 10–10
5.2 × 10–10
5.5 × 10–10
2.5 × 10–8
1.0 × 10–8
3.3 × 10–9
2.5 × 10–9
4.8 × 10–9
5.9 × 10–9
3.9 × 10–10
9.2 × 10–10
8.9 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

289

1.10 h

14.6 h13.6 a2.03 × 104 a

35.1 d3.61 d23.3 hNb‑90

Nb‑93m

Nb‑94

Nb‑95

Nb‑95mNb‑96

Physicalhalf-life

Nb‑89mRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 af1 for
g>1a
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)
4.0 × 10–10
6.2 × 10–10
6.4 × 10–10
3.5 × 10–9
5.1 × 10–9
5.3 × 10–9
1.8 × 10–9
3.1 × 10–9
7.4 × 10–9
3.1 × 10–8
4.3 × 10–8
1.2 × 10–7
4.1 × 10–9
6.8 × 10–9
7.7 × 10–9
2.3 × 10–9
4.3 × 10–9
4.6 × 10–9
3.1 × 10–9
4.7 × 10–9
4.9 × 10–9

2.9 × 10–10
4.3 × 10–10
4.4 × 10–10
2.7 × 10–9
3.9 × 10–9
4.0 × 10–9
1.4 × 10–9
2.4 × 10–9
6.5 × 10–9
2.7 × 10–8
3.7 × 10–8
1.2 × 10–7
3.1 × 10–9
5.2 × 10–9
5.9 × 10–9
1.6 × 10–9
3.1 × 10–9
3.4 × 10–9
2.4 × 10–9
3.6 × 10–9
3.7 × 10–9e(g)Age 1–2 a

1.4 × 10–10
2.1 × 10–10
2.1 × 10–10
1.3 × 10–9
1.9 × 10–9
2.0 × 10–9
7.0 × 10–10
1.3 × 10–9
4.0 × 10–9
1.5 × 10–8
2.3 × 10–8
8.3 × 10–8
1.6 × 10–9
3.1 × 10–9
3.6 × 10–9
7.0 × 10–10
1.7 × 10–9
1.9 × 10–9
1.2 × 10–9
1.8 × 10–9
1.9 × 10–9

e(g)

2–7 a

8.3 × 10–11
1.3 × 10–10
1.4 × 10–10
8.2 × 10–10
1.3 × 10–9
1.3 × 10–9
4.4 × 10–10
8.2 × 10–10
2.5 × 10–9
1.0 × 10–8
1.6 × 10–8
5.8 × 10–8
1.2 × 10–9
2.2 × 10–9
2.5 × 10–9
4.2 × 10–10
1.2 × 10–9
1.3 × 10–9
7.3 × 10–10
1.2 × 10–9
1.2 × 10–9e(g)7–12 a4.8 × 10–11
8.2 × 10–11
8.6 × 10–11
4.7 × 10–10
7.8 × 10–10
8.1 × 10–10
2.7 × 10–10
5.9 × 10–10
1.9 × 10–9
6.7 × 10–9
1.3 × 10–8
5.2 × 10–8
7.5 × 10–10
1.9 × 10–9
2.2 × 10–9
2.4 × 10–10
1.0 × 10–9
1.1 × 10–9
4.2 × 10–10
7.8 × 10–10
8.3 × 10–10

e(g)12–17 a3.9 × 10–11
6.8 × 10–11
7.1 × 10–11
3.8 × 10–10
6.3 × 10–10
6.6 × 10–10
2.2 × 10–10
5.1 × 10–10
1.8 × 10–9
5.8 × 10–9
1.1 × 10–8
4.9 × 10–8
5.7 × 10–10
1.5 × 10–9
1.8 × 10–9
2.0 × 10–10
7.9 × 10–10
8.8 × 10–10
3.4 × 10–10
6.3 × 10–10
6.6 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

290

0.858 hNb‑98

5.67 h

3.50 × 103 a6.85 h

2.75 d

Mo‑90

Mo‑93

Mo‑93mMo‑99

Molybdenum

1.20 hPhysicalhalf-life

Nb‑97

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S

F
M
S
F
M
S

Type

1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 a

2.2 × 10–10
3.7 × 10–10
3.8 × 10–10
3.4 × 10–10
5.2 × 10–10
5.3 × 10–10

0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010

0.010
0.010
0.010
0.010
0.010
0.010

e(g)

1.2 × 10–9
2.6 × 10–9
2.8 × 10–9
3.1 × 10–9
2.2 × 10–9
6.0 × 10–9
7.3 × 10–10
1.2 × 10–9
1.3 × 10–9
2.3 × 10–9
6.0 × 10–9
6.9 × 10–9

f1 forg>1a

1.1 × 10–9
2.0 × 10–9
2.1 × 10–9
2.6 × 10–9
1.8 × 10–9
5.8 × 10–9
6.4 × 10–10
9.7 × 10–10
1.0 × 10–9
1.7 × 10–9
4.4 × 10–9
4.8 × 10–9

1.5 × 10–10
2.5 × 10–10
2.6 × 10–10
2.4 × 10–10
3.6 × 10–10
3.7 × 10–10e(g)Age 1–2 a

5.3 × 10–10
9.9 × 10–10
1.1 × 10–9
1.7 × 10–9
1.1 × 10–9
4.0 × 10–9
3.3 × 10–10
5.0 × 10–10
5.2 × 10–10
7.7 × 10–10
2.2 × 10–9
2.4 × 10–9

6.8 × 10–11
1.2 × 10–10
1.2 × 10–10
1.1 × 10–10
1.7 × 10–10
1.8 × 10–10

e(g)

2–7 a

3.2 × 10–10
6.5 × 10–10
6.9 × 10–10
1.3 × 10–9
7.9 × 10–10
2.8 × 10–9
2.0 × 10–10
3.2 × 10–10
3.4 × 10–10
4.7 × 10–10
1.5 × 10–9
1.7 × 10–9

4.2 × 10–11
7.7 × 10–11
8.1 × 10–11
6.9 × 10–11
1.1 × 10–10
1.1 × 10–10

e(g)7–12 a1.9 × 10–10
4.2 × 10–10
4.5 × 10–10
1.1 × 10–9
6.6 × 10–10
2.4 × 10–9
1.2 × 10–10
2.0 × 10–10
2.1 × 10–10
2.6 × 10–10
1.1 × 10–9
1.2 × 10–9

2.5 × 10–11
5.2 × 10–11
5.5 × 10–11
4.1 × 10–11
6.8 × 10–11
7.1 × 10–11

e(g)12–17 a1.5 × 10–10
3.4 × 10–10
3.6 × 10–10
1.0 × 10–9
5.9 × 10–10
2.3 × 10–9
9.6 × 10–11
1.6 × 10–10
1.7 × 10–10
2.2 × 10–10
8.9 × 10–10
9.9 × 10–10

2.1 × 10–11
4.3 × 10–11
4.5 × 10–11
3.3 × 10–11
5.6 × 10–11
5.8 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

291

2.75 h

0.725 h4.88 h

0.867 h20.0 hTc‑93m

Tc‑94

Tc‑94m

Tc‑95

0.244 hPhysicalhalf-life

Tc‑93

Technetium

Mo-101

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

1.000
0.200
0.020

f1

Age ≤ 1 a

1.4 × 10–10
2.2 × 10–10
2.3 × 10–10

0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010

0.800
0.100
0.010

e(g)

2.4 × 10–10
2.7 × 10–10
2.8 × 10–10
1.2 × 10–10
1.4 × 10–10
1.4 × 10–10
8.9 × 10–10
9.8 × 10–10
9.9 × 10–10
4.8 × 10–10
4.4 × 10–10
4.3 × 10–10
7.5 × 10–10
8.3 × 10–10
8.5 × 10–10

f1 forg>1a

2.1 × 10–10
2.3 × 10–10
2.3 × 10–10
9.8 × 10–11
1.1 × 10–10
1.1 × 10–10
7.5 × 10–10
8.1 × 10–10
8.2 × 10–10
3.4 × 10–10
3.0 × 10–10
3.0 × 10–10
6.3 × 10–10
6.9 × 10–10
7.0 × 10–10

9.7 × 10–11
1.5 × 10–10
1.6 × 10–10e(g)Age 1–2 a

1.1 × 10–10
1.2 × 10–10
1.2 × 10–10
4.9 × 10–11
5.4 × 10–11
5.4 × 10–11
3.9 × 10–10
4.2 × 10–10
4.3 × 10–10
1.6 × 10–10
1.4 × 10–10
1.4 × 10–10
3.3 × 10–10
3.6 × 10–10
3.6 × 10–10

4.4 × 10–11
7.0 × 10–11
7.2 × 10–11

e(g)

2–7 a

6.7 × 10–11
7.5 × 10–11
7.6 × 10–11
2.9 × 10–11
3.4 × 10–11
3.4 × 10–11
2.3 × 10–10
2.6 × 10–10
2.7 × 10–10
8.6 × 10–11
8.8 × 10–11
8.8 × 10–11
2.0 × 10–10
2.2 × 10–10
2.3 × 10–10

2.8 × 10–11
4.5 × 10–11
4.7 × 10–11

e(g)7–12 a4.0 × 10–11
4.4 × 10–11
4.5 × 10–11
1.8 × 10–11
2.1 × 10–11
2.1 × 10–11
1.4 × 10–10
1.6 × 10–10
1.6 × 10–10
5.2 × 10–11
5.5 × 10–11
5.6 × 10–11
1.2 × 10–10
1.3 × 10–10
1.4 × 10–10

1.7 × 10–11
3.0 × 10–11
3.1 × 10–11

e(g)12–17 a3.2 × 10–11
3.5 × 10–11
3.5 × 10–11
1.4 × 10–11
1.7 × 10–11
1.7 × 10–11
1.1 × 10–10
1.2 × 10–10
1.3 × 10–10
4.1 × 10–11
4.5 × 10–11
4.6 × 10–11
9.6 × 10–11
1.0 × 10–10
1.1 × 10–10

1.4 × 10–11
2.5 × 10–11
2.6 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

292

61.0 d

4.28 d

0.858 h2.60 × 106 a

87.0 d

4.20 × 106 a

2.13 × 105 a

Tc‑96

Tc‑96m

Tc‑97

Tc‑97m

Tc‑98

Tc‑99

Physicalhalf-life

Tc‑95mRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010

e(g)
2.4 × 10–9
4.9 × 10–9
6.0 × 10–9
4.2 × 10–9
4.7 × 10–9
4.8 × 10–9
5.3 × 10–11
5.6 × 10–11
5.7 × 10–11
5.2 × 10–10
1.2 × 10–9
5.0 × 10–9
3.4 × 10–9
1.3 × 10–8
1.6 × 10–8
1.0 × 10–8
3.5 × 10–8
1.1 × 10–7
4.0 × 10–9
1.7 × 10–8
4.1 × 10–8

1.8 × 10–9
4.0 × 10–9
5.0 × 10–9
3.4 × 10–9
3.9 × 10–9
3.9 × 10–9
4.1 × 10–11
4.4 × 10–11
4.4 × 10–11
3.7 × 10–10
1.0 × 10–9
4.8 × 10–9
2.3 × 10–9
1.0 × 10–8
1.3 × 10–8
6.8 × 10–9
2.9 × 10–8
1.1 × 10–7
2.5 × 10–9
1.3 × 10–8
3.7 × 10–8e(g)Age 1–2 a

9.3 × 10–10
2.3 × 10–9
2.7 × 10–9
1.8 × 10–9
2.1 × 10–9
2.1 × 10–9
2.1 × 10–11
2.3 × 10–11
2.3 × 10–11
1.7 × 10–10
5.7 × 10–10
3.3 × 10–9
9.8 × 10–10
6.1 × 10–9
7.8 × 10–9
3.2 × 10–9
1.7 × 10–8
7.6 × 10–8
1.0 × 10–9
8.0 × 10–9
2.4 × 10–8

e(g)

2–7 a

5.7 × 10–10
1.5 × 10–9
1.8 × 10–9
1.1 × 10–9
1.3 × 10–9
1.4 × 10–9
1.3 × 10–11
1.4 × 10–11
1.5 × 10–11
9.4 × 10–11
3.6 × 10–10
2.2 × 10–9
5.6 × 10–10
4.4 × 10–9
5.7 × 10–9
1.9 × 10–9
1.2 × 10–8
5.4 × 10–8
5.9 × 10–10
5.7 × 10–9
1.7 × 10–8

e(g)7–12 a3.6 × 10–10
1.1 × 10–9
1.5 × 10–9
7.0 × 10–10
8.6 × 10–10
8.9 × 10–10
7.7 × 10–12
9.3 × 10–12
9.5 × 10–12
5.6 × 10–11
2.8 × 10–10
1.9 × 10–9
3.0 × 10–10
4.1 × 10–9
5.2 × 10–9
1.2 × 10–9
1.0 × 10–8
4.8 × 10–8
3.6 × 10–10
5.0 × 10–9
1.5 × 10–8

e(g)12–17 a2.9 × 10–10
8.8 × 10–10
1.2 × 10–9
5.7 × 10–10
6.8 × 10–10
7.0 × 10–10
6.2 × 10–12
7.4 × 10–12
7.5 × 10–12
4.3 × 10–11
2.2 × 10–10
1.8 × 10–9
2.7 × 10–10
3.2 × 10–9
4.1 × 10–9
9.7 × 10–10
8.3 × 10–9
4.5 × 10–8
2.9 × 10–10
4.0 × 10–9
1.3 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

293

0.237 h0.303 hTc-101

Tc-1040.863 h2.90 d39.3 d

Ru‑94

Ru‑97

Ru-103

Ruthenium

6.02 hPhysicalhalf-life

Tc‑99mRadionuclidea

F
M
S
F
M
S
F
M
S

F
M
S
F
M
S
F
M
S

Type

0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020

1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

1.2 × 10–10
1.3 × 10–10
1.3 × 10–10
8.5 × 10–11
1.1 × 10–10
1.1 × 10–10
2.7 × 10–10
2.9 × 10–10
2.9 × 10–10

0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010

0.800
0.100
0.010
0.800
0.100
0.010
0.800
0.100
0.010

e(g)

2.5 × 10–10
3.8 × 10–10
4.0 × 10–10
5.5 × 10–10
7.7 × 10–10
8.1 × 10–10
4.2 × 10–9
1.1 × 10–8
1.3 × 10–8

f1 forg>1a

1.9 × 10–10
2.8 × 10–10
2.9 × 10–10
4.4 × 10–10
6.1 × 10–10
6.3 × 10–10
3.0 × 10–9
8.4 × 10–9
1.0 × 10–8

8.7 × 10–11
9.9 × 10–11
1.0 × 10–10
5.6 × 10–11
7.1 × 10–11
7.3 × 10–11
1.8 × 10–10
1.9 × 10–10
1.9 × 10–10e(g)Age 1–2 a

9.0 × 10–11
1.3 × 10–10
1.4 × 10–10
2.2 × 10–10
3.1 × 10–10
3.3 × 10–10
1.5 × 10–9
5.0 × 10–9
6.0 × 10–9

4.1 × 10–11
5.1 × 10–11
5.2 × 10–11
2.5 × 10–11
3.2 × 10–11
3.3 × 10–11
8.0 × 10–11
8.6 × 10–11
8.7 × 10–11

e(g)

2–7 a

5.4 × 10–11
8.4 × 10–11
8.7 × 10–11
1.3 × 10–10
2.0 × 10–10
2.1 × 10–10
9.3 × 10–10
3.5 × 10–9
4.2 × 10–9

2.4 × 10–11
3.4 × 10–11
3.5 × 10–11
1.6 × 10–11
2.1 × 10–11
2.2 × 10–11
4.6 × 10–11
5.4 × 10–11
5.4 × 10–11

e(g)7–12 a3.1 × 10–11
5.2 × 10–11
5.4 × 10–11
7.7 × 10–11
1.3 × 10–10
1.4 × 10–10
5.6 × 10–10
3.0 × 10–9
3.7 × 10–9

1.5 × 10–11
2.4 × 10–11
2.5 × 10–11
9.7 × 10–12
1.4 × 10–11
1.4 × 10–11
2.8 × 10–11
3.3 × 10–11
3.4 × 10–11

e(g)12–17 a2.5 × 10–11
4.2 × 10–11
4.4 × 10–11
6.2 × 10–11
1.0 × 10–10
1.1 × 10–10
4.8 × 10–10
2.4 × 10–9
3.0 × 10–9

1.2 × 10–11
1.9 × 10–11
2.0 × 10–11
8.2 × 10–12
1.2 × 10–11
1.2 × 10–11
2.3 × 10–11
2.8 × 10–11
2.9 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

294

1.01 aRu-10616.0 d

4.70 h20.8 h3.20 aRh‑99

Rh‑99m

Rh-100Rh-101

Rhodium

4.44 hPhysicalhalf-life

Ru-105

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S

F
M
S
F
M
S

Type

0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.020
0.100
0.100
0.020

f1

Age ≤ 1 a

7.1 × 10–10
1.3 × 10–9
1.4 × 10–9
7.2 × 10–8
1.4 × 10–7
2.6 × 10–7

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

0.050
0.050
0.010
0.050
0.050
0.010

e(g)

2.6 × 10–9
4.5 × 10–9
4.9 × 10–9
2.4 × 10–10
3.1 × 10–10
3.2 × 10–10
2.1 × 10–9
2.7 × 10–9
2.8 × 10–9
7.4 × 10–9
9.8 × 10–9
1.9 × 10–8

f1 forg>1a2.0 × 10–9
3.5 × 10–9
3.8 × 10–9
2.0 × 10–10
2.5 × 10–10
2.6 × 10–10
1.8 × 10–9
2.2 × 10–9
2.2 × 10–9
6.1 × 10–9
8.0 × 10–9
1.7 × 10–8

5.1 × 10–10
9.2 × 10–10
9.8 × 10–10
5.4 × 10–8
1.1 × 10–7
2.3 × 10–7e(g)Age 1–2 a

9.9 × 10–10
2.0 × 10–9
2.2 × 10–9
1.0 × 10–10
1.3 × 10–10
1.3 × 10–10
9.1 × 10–10
1.1 × 10–9
1.2 × 10–9
3.5 × 10–9
4.9 × 10–9
1.1 × 10–8

2.3 × 10–10
4.5 × 10–10
4.8 × 10–10
2.6 × 10–8
6.4 × 10–8
1.4 × 10–7

e(g)

2–7 a

6.2 × 10–10
1.3 × 10–9
1.3 × 10–9
6.1 × 10–11
8.0 × 10–11
8.2 × 10–11
5.6 × 10–10
7.1 × 10–10
7.3 × 10–10
2.3 × 10–9
3.4 × 10–9
7.4 × 10–9

1.4 × 10–10
3.0 × 10–10
3.2 × 10–10
1.6 × 10–8
4.1 × 10–8
9.1 × 10–8

e(g)7–12 a3.8 × 10–10
9.6 × 10–10
1.1 × 10–9
3.5 × 10–11
4.9 × 10–11
5.1 × 10–11
3.3 × 10–10
4.3 × 10–10
4.4 × 10–10
1.5 × 10–9
2.8 × 10–9
6.2 × 10–9

7.9 × 10–11
2.0 × 10–10
2.2 × 10–10
9.2 × 10–9
3.1 × 10–8
7.1 × 10–8

e(g)12–17 a3.2 × 10–10
7.7 × 10–10
8.7 × 10–10
2.8 × 10–11
3.9 × 10–11
4.0 × 10–11
2.6 × 10–10
3.4 × 10–10
3.5 × 10–10
1.4 × 10–9
2.3 × 10–9
5.4 × 10–9

6.5 × 10–11
1.7 × 10–10
1.8 × 10–10
7.9 × 10–9
2.8 × 10–8
6.6 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

295

4.34 d

2.90 a207 d0.935 h1.47 d

2.20 h

0.362 hRh-102

Rh-102m

Rh-103m

Rh-105

Rh-106m

Rh-107

Physicalhalf-life

Rh-101m

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

Age ≤ 1 af1 for
g>1a
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

e(g)
8.4 × 10–10
1.3 × 10–9
1.3 × 10–9
3.3 × 10–8
3.0 × 10–8
5.4 × 10–8
1.2 × 10–8
2.0 × 10–8
3.0 × 10–8
8.6 × 10–12
1.9 × 10–11
2.0 × 10–11
1.0 × 10–9
2.2 × 10–9
2.4 × 10–9
5.7 × 10–10
8.2 × 10–10
8.5 × 10–10
8.9 × 10–11
1.4 × 10–10
1.5 × 10–10

6.6 × 10–10
9.8 × 10–10
1.0 × 10–9
2.8 × 10–8
2.5 × 10–8
5.0 × 10–8
8.7 × 10–9
1.6 × 10–8
2.5 × 10–8
5.9 × 10–12
1.2 × 10–11
1.3 × 10–11
6.9 × 10–10
1.6 × 10–9
1.7 × 10–9
4.5 × 10–10
6.3 × 10–10
6.5 × 10–10
5.9 × 10–11
9.3 × 10–11
9.7 × 10–11e(g)Age 1–2 a

3.3 × 10–10
5.2 × 10–10
5.5 × 10–10
1.7 × 10–8
1.5 × 10–8
3.5 × 10–8
4.4 × 10–9
9.0 × 10–9
1.5 × 10–8
2.7 × 10–12
6.3 × 10–12
6.7 × 10–12
3.0 × 10–10
7.4 × 10–10
8.0 × 10–10
2.2 × 10–10
3.2 × 10–10
3.3 × 10–10
2.6 × 10–11
4.2 × 10–11
4.4 × 10–11

e(g)

2–7 a

2.0 × 10–10
3.5 × 10–10
3.7 × 10–10
1.1 × 10–8
1.0 × 10–8
2.4 × 10–8
2.7 × 10–9
6.0 × 10–9
1.0 × 10–8
1.6 × 10–12
4.0 × 10–12
4.3 × 10–12
1.8 × 10–10
5.2 × 10–10
5.6 × 10–10
1.4 × 10–10
2.0 × 10–10
2.1 × 10–10
1.7 × 10–11
2.8 × 10–11
2.9 × 10–11

e(g)7–12 a

1.2 × 10–10
2.5 × 10–10
2.7 × 10–10
7.9 × 10–9
7.9 × 10–9
2.0 × 10–8
1.7 × 10–9
4.7 × 10–9
8.2 × 10–9
1.0 × 10–12
3.0 × 10–12
3.2 × 10–12
9.6 × 10–11
4.1 × 10–10
4.5 × 10–10
8.0 × 10–11
1.3 × 10–10
1.4 × 10–10
1.0 × 10–11
1.9 × 10–11
1.9 × 10–11

e(g)12–17 a9.7 × 10–11
1.9 × 10–10
2.1 × 10–10
7.3 × 10–9
6.9 × 10–9
1.7 × 10–8
1.5 × 10–9
4.0 × 10–9
7.1 × 10–9
8.6 × 10–13
2.5 × 10–12
2.7 × 10–12
8.2 × 10–11
3.2 × 10–10
3.5 × 10–10
6.5 × 10–11
1.1 × 10–10
1.1 × 10–10
9.0 × 10–12
1.6 × 10–11
1.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

296

17.0 d6.50 × 106 a

13.4 h

Pd-103

Pd-107

Pd-109Ag-1020.215 h8.27 h

Pd-101Silver

3.63 dPhysicalhalf-life

Pd-100Palladium

Radionuclidea

F
M
S

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type

0.100
0.100
0.020

0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

f1

Age ≤ 1 a

1.2 × 10–10
1.6 × 10–10
1.6 × 10–10

3.9 × 10–9
5.2 × 10–9
5.3 × 10–9
3.6 × 10–10
4.8 × 10–10
5.0 × 10–10
9.7 × 10–10
2.3 × 10–9
2.5 × 10–9
2.6 × 10–10
6.5 × 10–10
2.2 × 10–9
1.5 × 10–9
2.6 × 10–9
2.7 × 10–9

e(g)

0.050
0.050
0.010

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1 forg>1a

8.6 × 10–11
1.1 × 10–10
1.2 × 10–10

3.0 × 10–9
4.0 × 10–9
4.1 × 10–9
2.9 × 10–10
3.8 × 10–10
3.9 × 10–10
6.5 × 10–10
1.6 × 10–9
1.8 × 10–9
1.8 × 10–10
5.0 × 10–10
2.0 × 10–9
9.9 × 10–10
1.8 × 10–9
1.9 × 10–9e(g)Age 1–2 a

4.2 × 10–11
5.5 × 10–11
5.6 × 10–11

1.5 × 10–9
2.2 × 10–9
2.2 × 10–9
1.4 × 10–10
1.9 × 10–10
2.0 × 10–10
3.0 × 10–10
9.0 × 10–10
1.0 × 10–9
8.2 × 10–11
2.6 × 10–10
1.3 × 10–9
4.2 × 10–10
8.8 × 10–10
9.3 × 10–10

e(g)

2–7 a

2.6 × 10–11
3.4 × 10–11
3.5 × 10–11

9.7 × 10–10
1.4 × 10–9
1.5 × 10–9
8.6 × 10–11
1.2 × 10–10
1.2 × 10–10
1.9 × 10–10
5.9 × 10–10
6.8 × 10–10
5.2 × 10–11
1.5 × 10–10
7.8 × 10–10
2.6 × 10–10
5.9 × 10–10
6.3 × 10–10

e(g)7–12 a

1.5 × 10–11
2.1 × 10–11
2.2 × 10–11

5.8 × 10–10
9.9 × 10–10
1.0 × 10–9
4.9 × 10–11
7.5 × 10–11
7.8 × 10–11
1.1 × 10–10
4.5 × 10–10
5.3 × 10–10
3.1 × 10–11
1.0 × 10–10
6.2 × 10–10
1.4 × 10–10
4.3 × 10–10
4.6 × 10–10

e(g)12–17 a1.3 × 10–11
1.7 × 10–11
1.8 × 10–11

4.7 × 10–10
8.0 × 10–10
8.5 × 10–10
3.9 × 10–11
5.9 × 10–11
6.2 × 10–11
8.9 × 10–11
3.8 × 10–10
4.5 × 10–10
2.5 × 10–11
8.5 × 10–11
5.9 × 10–10
1.2 × 10–10
3.4 × 10–10
3.7 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

297

1.09 h1.15 h

0.558 h41.0 d

0.399 h8.41 d

1.27 × 102 a

Ag-104Ag-104m

Ag-105

Ag-106

Ag-106m

Ag-108m

Physicalhalf-life

Ag-103

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020

f1

Age ≤ 1 af1 for
g>1a
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010

e(g)
1.4 × 10–10
2.2 × 10–10
2.3 × 10–10
2.3 × 10–10
2.9 × 10–10
2.9 × 10–10
1.6 × 10–10
2.3 × 10–10
2.4 × 10–10
3.9 × 10–9
4.5 × 10–9
4.5 × 10–9
9.4 × 10–11
1.4 × 10–10
1.5 × 10–10
7.7 × 10–9
7.2 × 10–9
7.0 × 10–9
3.5 × 10–8
3.3 × 10–8
8.9 × 10–8

1.0 × 10–10
1.6 × 10–10
1.6 × 10–10
1.9 × 10–10
2.3 × 10–10
2.4 × 10–10
1.1 × 10–10
1.6 × 10–10
1.7 × 10–10
3.4 × 10–9
3.5 × 10–9
3.6 × 10–9
6.4 × 10–11
9.5 × 10–11
9.9 × 10–11
6.1 × 10–9
5.8 × 10–9
5.7 × 10–9
2.8 × 10–8
2.7 × 10–8
8.7 × 10–8e(g)Age 1–2 a

4.9 × 10–11
7.6 × 10–11
7.9 × 10–11
9.8 × 10–11
1.2 × 10–10
1.2 × 10–10
5.5 × 10–11
7.7 × 10–11
8.0 × 10–11
1.7 × 10–9
2.0 × 10–9
2.1 × 10–9
2.9 × 10–11
4.4 × 10–11
4.5 × 10–11
3.2 × 10–9
3.2 × 10–9
3.2 × 10–9
1.6 × 10–8
1.7 × 10–8
6.2 × 10–8

e(g)

2–7 a

3.0 × 10–11
4.8 × 10–11
5.1 × 10–11
5.9 × 10–11
7.4 × 10–11
7.6 × 10–11
3.4 × 10–11
4.8 × 10–11
5.0 × 10–11
1.0 × 10–9
1.3 × 10–9
1.3 × 10–9
1.8 × 10–11
2.8 × 10–11
2.9 × 10–11
2.1 × 10–9
2.1 × 10–9
2.1 × 10–9
1.0 × 10–8
1.1 × 10–8
4.4 × 10–8

e(g)7–12 a1.8 × 10–11
3.2 × 10–11
3.3 × 10–11
3.5 × 10–11
4.5 × 10–11
4.6 × 10–11
2.0 × 10–11
3.0 × 10–11
3.1 × 10–11
6.4 × 10–10
9.0 × 10–10
1.0 × 10–9
1.1 × 10–11
1.8 × 10–11
1.9 × 10–11
1.3 × 10–9
1.4 × 10–9
1.4 × 10–9
6.9 × 10–9
8.6 × 10–9
3.9 × 10–8

e(g)12–17 a1.4 × 10–11
2.6 × 10–11
2.7 × 10–11
2.8 × 10–11
3.6 × 10–11
3.7 × 10–11
1.6 × 10–11
2.5 × 10–11
2.6 × 10–11
5.4 × 10–10
7.3 × 10–10
8.1 × 10–10
9.1 × 10–12
1.5 × 10–11
1.6 × 10–11
1.1 × 10–9
1.1 × 10–9
1.1 × 10–9
6.1 × 10–9
7.4 × 10–9
3.7 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

298

7.45 d

3.12 h

0.333 hAg‑111

Ag‑112

Ag‑1150.961 h6.49 h

Cd-104

Cd-107

Cadmium

250 d

Physicalhalf-life

Ag‑110m

Radionuclidea

F
M
S
F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.100
0.100
0.100
0.100
0.100
0.100

0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020
0.100
0.100
0.020

f1

Age ≤ 1 a

3.5 × 10–8
3.5 × 10–8
4.6 × 10–8
4.8 × 10–9
9.2 × 10–9
9.9 × 10–9
9.8 × 10–10
1.7 × 10–9
1.8 × 10–9
1.6 × 10–10
2.5 × 10–10
2.7 × 10–10

0.050
0.050
0.050
0.050
0.050
0.050

0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010
0.050
0.050
0.010

e(g)

2.0 × 10–10
2.6 × 10–10
2.7 × 10–10
2.3 × 10–10
5.2 × 10–10
5.5 × 10–10

f1 forg>1a

1.7 × 10–10
2.1 × 10–10
2.2 × 10–10
1.7 × 10–10
3.7 × 10–10
3.9 × 10–10

2.8 × 10–8
2.8 × 10–8
4.1 × 10–8
3.2 × 10–9
6.6 × 10–9
7.1 × 10–9
6.4 × 10–10
1.1 × 10–9
1.2 × 10–9
1.0 × 10–10
1.7 × 10–10
1.7 × 10–10e(g)Age 1–2 a

8.7 × 10–11
1.1 × 10–10
1.1 × 10–10
7.4 × 10–11
2.0 × 10–10
2.1 × 10–10

1.5 × 10–8
1.7 × 10–8
2.6 × 10–8
1.4 × 10–9
3.5 × 10–9
3.8 × 10–9
2.8 × 10–10
5.1 × 10–10
5.4 × 10–10
4.6 × 10–11
7.6 × 10–11
8.0 × 10–11

e(g)

2–7 a

5.2 × 10–11
6.9 × 10–11
7.0 × 10–11
4.6 × 10–11
1.3 × 10–10
1.4 × 10–10

9.7 × 10–9
1.2 × 10–8
1.8 × 10–8
8.8 × 10–10
2.4 × 10–9
2.7 × 10–9
1.7 × 10–10
3.2 × 10–10
3.4 × 10–10
2.9 × 10–11
4.9 × 10–11
5.2 × 10–11

e(g)7–12 a3.1 × 10–11
4.2 × 10–11
4.4 × 10–11
2.5 × 10–11
8.8 × 10–11
9.7 × 10–11

6.3 × 10–9
9.2 × 10–9
1.5 × 10–8
4.8 × 10–10
1.9 × 10–9
2.1 × 10–9
9.1 × 10–11
2.0 × 10–10
2.1 × 10–10
1.7 × 10–11
3.2 × 10–11
3.4 × 10–11

e(g)12–17 a2.4 × 10–11
3.4 × 10–11
3.5 × 10–11
2.1 × 10–11
8.3 × 10–11
7.7 × 10–11

5.5 × 10–9
7.6 × 10–9
1.2 × 10–8
4.0 × 10–10
1.5 × 10–9
1.7 × 10–9
7.6 × 10–11
1.6 × 10–10
1.7 × 10–10
1.5 × 10–11
2.7 × 10–11
2.9 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

299

1.27 a9.30 × 1015 a

13.6 a2.23 d44.6 d2.49 h

3.36 h

Cd‑113

Cd‑113m

Cd‑115

Cd‑115m

Cd‑117

Cd‑117m

Physicalhalf-life

Cd-109Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

Age ≤ 1 af1 for
g>1a
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

e(g)
4.5 × 10–8
3.0 × 10–8
2.7 × 10–8
2.6 × 10–7
1.2 × 10–7
7.8 × 10–8
3.0 × 10–7
1.4 × 10–7
1.1 × 10–7
4.0 × 10–9
6.7 × 10–9
7.2 × 10–9
4.6 × 10–8
4.0 × 10–8
3.9 × 10–8
7.4 × 10–10
1.3 × 10–9
1.4 × 10–9
8.9 × 10–10
1.5 × 10–9
1.5 × 10–9

3.7 × 10–8
2.3 × 10–8
2.1 × 10–8
2.4 × 10–7
1.0 × 10–7
5.8 × 10–8
2.7 × 10–7
1.2 × 10–7
8.4 × 10–8
2.6 × 10–9
4.8 × 10–9
5.1 × 10–9
3.2 × 10–8
2.5 × 10–8
3.0 × 10–8
5.2 × 10–10
9.3 × 10–10
9.8 × 10–10
6.7 × 10–10
1.1 × 10–9
1.1 × 10–9e(g)Age 1–2 a

2.1 × 10–8
1.4 × 10–8
1.3 × 10–8
1.7 × 10–7
7.6 × 10–8
4.1 × 10–8
1.8 × 10–7
8.1 × 10–8
5.5 × 10–8
1.2 × 10–9
2.4 × 10–9
2.6 × 10–9
1.5 × 10–8
1.4 × 10–8
1.7 × 10–8
2.4 × 10–10
4.5 × 10–10
4.8 × 10–10
3.3 × 10–10
5.5 × 10–10
5.7 × 10–10

e(g)

2–7 a

1.4 × 10–8
9.5 × 10–9
8.9 × 10–9
1.4 × 10–7
6.1 × 10–8
3.0 × 10–8
1.3 × 10–7
6.0 × 10–8
3.9 × 10–8
7.5 × 10–10
1.7 × 10–9
1.8 × 10–9
1.0 × 10–8
9.4 × 10–9
1.1 × 10–8
1.5 × 10–10
2.9 × 10–10
3.1 × 10–10
2.0 × 10–10
3.6 × 10–10
3.8 × 10–10

e(g)7–12 a9.3 × 10–9
7.8 × 10–9
7.6 × 10–9
1.2 × 10–7
5.7 × 10–8
2.7 × 10–8
1.1 × 10–7
5.3 × 10–8
3.3 × 10–8
4.3 × 10–10
1.2 × 10–9
1.3 × 10–9
6.4 × 10–9
7.3 × 10–9
8.9 × 10–9
8.1 × 10–11
2.0 × 10–10
2.1 × 10–10
1.1 × 10–10
2.4 × 10–10
2.6 × 10–10

e(g)12–17 a8.1 × 10–9
6.6 × 10–9
6.2 × 10–9
1.2 × 10–7
5.5 × 10–8
2.6 × 10–8
1.1 × 10–7
5.2 × 10–8
3.1 × 10–8
3.5 × 10–10
9.8 × 10–10
1.1 × 10–9
5.3 × 10–9
6.2 × 10–9
7.7 × 10–9
6.7 × 10–11
1.6 × 10–10
1.7 × 10–10
9.4 × 10–11
2.0 × 10–10
2.1 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

300

4.20 h

4.90 h1.15 h2.83 d0.240 h1.66 h49.5 d

5.10 × 1015 a

4.49 h

0.902 hIn‑110In‑110m

In‑111

In‑112

In‑113m

In‑114m

In‑115

In‑115m

In‑116m

Physicalhalf-life

In-109IndiumRadionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

f1

Age ≤ 1 a

2.6 × 10–10
3.3 × 10–10
8.2 × 10–10
9.9 × 10–10
3.0 × 10–10
4.5 × 10–10
1.2 × 10–9
1.5 × 10–9
4.4 × 10–11
6.5 × 10–11
1.0 × 10–10
1.6 × 10–10
1.2 × 10–7
4.8 × 10–8
8.3 × 10–7
3.0 × 10–7
2.8 × 10–10
4.7 × 10–10
2.5 × 10–10
3.6 × 10–10

e(g)
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1 forg>1a

2.1 × 10–10
2.6 × 10–10
7.1 × 10–10
8.3 × 10–10
2.1 × 10–10
3.1 × 10–10
8.6 × 10–10
1.2 × 10–9
3.0 × 10–11
4.4 × 10–11
7.0 × 10–11
1.1 × 10–10
7.7 × 10–8
3.3 × 10–8
7.8 × 10–7
2.8 × 10–7
1.9 × 10–10
3.3 × 10–10
1.9 × 10–10
2.7 × 10–10e(g)Age 1–2 a

1.0 × 10–10
1.3 × 10–10
3.7 × 10–10
4.4 × 10–10
9.9 × 10–11
1.5 × 10–10
4.2 × 10–10
6.2 × 10–10
1.3 × 10–11
2.0 × 10–11
3.2 × 10–11
5.5 × 10–11
3.4 × 10–8
1.6 × 10–8
5.5 × 10–7
2.1 × 10–7
8.4 × 10–11
1.6 × 10–10
9.2 × 10–11
1.3 × 10–10

e(g)

2–7 a

6.3 × 10–11
8.4 × 10–11
2.3 × 10–10
2.7 × 10–10
6.0 × 10–11
9.2 × 10–11
2.6 × 10–10
4.1 × 10–10
8.7 × 10–12
1.3 × 10–11
2.0 × 10–11
3.6 × 10–11
1.9 × 10–8
1.0 × 10–8
5.0 × 10–7
1.9 × 10–7
5.1 × 10–11
1.0 × 10–10
5.7 × 10–11
8.5 × 10–11

e(g)7–12 a3.6 × 10–11
5.3 × 10–11
1.3 × 10–10
1.6 × 10–10
3.5 × 10–11
5.8 × 10–11
1.5 × 10–10
2.9 × 10–10
5.4 × 10–12
8.7 × 10–12
1.2 × 10–11
2.4 × 10–11
1.1 × 10–8
7.8 × 10–9
4.2 × 10–7
1.7 × 10–7
2.8 × 10–11
7.2 × 10–11
3.4 × 10–11
5.6 × 10–11

e(g)12–17 a2.9 × 10–11
4.2 × 10–11
1.1 × 10–10
1.3 × 10–10
2.8 × 10–11
4.7 × 10–11
1.3 × 10–10
2.3 × 10–10
4.7 × 10–12
7.4 × 10–12
9.7 × 10–12
2.0 × 10–11
9.3 × 10–9
6.1 × 10–9
3.9 × 10–7
1.6 × 10–7
2.4 × 10–11
5.9 × 10–11
2.8 × 10–11
4.5 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

301

1.94 h

0.300 hIn‑117m

In‑119m

4.00 h

0.588 h115 d13.6 d293 d1.13 d55.0 aSn‑110Sn‑111

Sn‑113

Sn‑117m

Sn‑119m

Sn‑121

Sn‑121m

Tin

0.730 hPhysicalhalf-life

In‑117

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M

F
M
F
M
F
M

Type

0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

0.040
0.040
0.040
0.040
0.040
0.040

f1

Age ≤ 1 a

1.4 × 10–10
2.3 × 10–10
3.4 × 10–10
6.0 × 10–10
1.2 × 10–10
1.8 × 10–10

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020

e(g)

1.0 × 10–9
1.5 × 10–9
7.7 × 10–11
1.1 × 10–10
5.1 × 10–9
1.3 × 10–8
3.3 × 10–9
1.0 × 10–8
3.0 × 10–9
1.0 × 10–8
7.7 × 10–10
1.5 × 10–9
6.9 × 10–9
1.9 × 10–8

f1 forg>1a

7.6 × 10–10
1.1 × 10–9
5.4 × 10–11
8.0 × 10–11
3.7 × 10–9
1.0 × 10–8
2.2 × 10–9
7.7 × 10–9
2.2 × 10–9
7.9 × 10–9
5.0 × 10–10
1.1 × 10–9
5.4 × 10–9
1.5 × 10–8

9.7 × 10–11
1.6 × 10–10
2.3 × 10–10
4.0 × 10–10
7.3 × 10–11
1.1 × 10–10e(g)Age 1–2 a

3.6 × 10–10
5.1 × 10–10
2.6 × 10–11
3.8 × 10–11
1.8 × 10–9
5.8 × 10–9
1.0 × 10–9
4.6 × 10–9
1.0 × 10–9
4.7 × 10–9
2.2 × 10–10
5.1 × 10–10
2.8 × 10–9
9.2 × 10–9

4.5 × 10–11
7.5 × 10–11
1.0 × 10–10
1.9 × 10–10
3.1 × 10–11
4.9 × 10–11

e(g)

2–7 a

2.2 × 10–10
3.2 × 10–10
1.6 × 10–11
2.5 × 10–11
1.1 × 10–9
4.0 × 10–9
6.1 × 10–10
3.4 × 10–9
6.0 × 10–10
3.1 × 10–9
1.3 × 10–10
3.6 × 10–10
1.6 × 10–9
6.4 × 10–9

2.8 × 10–11
5.0 × 10–11
6.2 × 10–11
1.3 × 10–10
2.0 × 10–11
3.2 × 10–11

e(g)7–12 a

1.2 × 10–10
1.9 × 10–10
9.4 × 10–12
1.6 × 10–11
6.4 × 10–10
3.2 × 10–9
3.4 × 10–10
3.1 × 10–9
3.4 × 10–10
2.6 × 10–9
7.0 × 10–11
2.9 × 10–10
9.4 × 10–10
5.5 × 10–9

1.7 × 10–11
3.5 × 10–11
3.5 × 10–11
8.7 × 10–11
1.2 × 10–11
2.0 × 10–11

e(g)12–17 a9.9 × 10–11
1.6 × 10–10
7.8 × 10–12
1.3 × 10–11
5.4 × 10–10
2.7 × 10–9
2.8 × 10–10
2.4 × 10–9
2.8 × 10–10
2.2 × 10–9
6.0 × 10–11
2.3 × 10–10
8.0 × 10–10
4.5 × 10–9

1.5 × 10–11
2.9 × 10–11
2.9 × 10–11
7.2 × 10–11
1.0 × 10–11
1.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

302

0.668 h9.64 d

1.00 × 105 a2.10 h

0.985 hSn‑123m

Sn‑125

Sn‑126

Sn‑127

Sn‑1280.530 h0.263 hSb‑115

Sb‑116

Antimony

129 dPhysicalhalf-life

Sn‑123

Radionuclidea

F
M
S
F
M
S

F
M
F
M
F
M
F
M
F
M
F
M

Type

0.200
0.020
0.020
0.200
0.020
0.020

0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040
0.040

f1

Age ≤ 1 a

1.4 × 10–8
4.0 × 10–8
1.4 × 10–10
2.3 × 10–10
1.2 × 10–8
2.1 × 10–8
7.3 × 10–8
1.2 × 10–7
6.6 × 10–10
1.0 × 10–9
5.1 × 10–10
8.0 × 10–10

0.100
0.010
0.010
0.100
0.010
0.010

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

e(g)

8.1 × 10–11
1.2 × 10–10
1.2 × 10–10
8.4 × 10–11
1.1 × 10–10
1.2 × 10–10

f1 forg>1a

5.9 × 10–11
8.3 × 10–11
8.6 × 10–11
6.2 × 10–11
8.2 × 10–11
8.5 × 10–11

9.9 × 10–9
3.1 × 10–8
8.9 × 10–11
1.5 × 10–10
8.0 × 10–9
1.5 × 10–8
5.9 × 10–8
1.0 × 10–7
4.7 × 10–10
7.4 × 10–10
3.6 × 10–10
5.5 × 10–10e(g)Age 1–2 a

2.8 × 10–11
4.0 × 10–11
4.1 × 10–11
3.0 × 10–11
4.0 × 10–11
4.1 × 10–11

4.5 × 10–9
1.8 × 10–8
3.9 × 10–11
7.0 × 10–11
3.5 × 10–9
7.6 × 10–9
3.2 × 10–8
6.2 × 10–8
2.3 × 10–10
3.7 × 10–10
1.7 × 10–10
2.7 × 10–10

e(g)

2–7 a

1.7 × 10–11
2.5 × 10–11
2.6 × 10–11
1.9 × 10–11
2.5 × 10–11
2.6 × 10–11

2.6 × 10–9
1.2 × 10–8
2.5 × 10–11
4.6 × 10–11
2.0 × 10–9
5.0 × 10–9
2.0 × 10–8
4.1 × 10–8
1.4 × 10–10
2.4 × 10–10
1.0 × 10–10
1.7 × 10–10

e(g)7–12 a1.0 × 10–11
1.6 × 10–11
1.7 × 10–11
1.1 × 10–11
1.5 × 10–11
1.6 × 10–11

1.4 × 10–9
9.5 × 10–9
1.5 × 10–11
3.2 × 10–11
1.1 × 10–9
3.6 × 10–9
1.3 × 10–8
3.3 × 10–8
7.9 × 10–11
1.6 × 10–10
6.1 × 10–11
1.1 × 10–10

e(g)12–17 a8.5 × 10–12
1.3 × 10–11
1.4 × 10–11
9.1 × 10–12
1.3 × 10–11
1.3 × 10–1

1.2 × 10–9
8.1 × 10–9
1.3 × 10–11
2.7 × 10–11
8.9 × 10–10
3.1 × 10–9
1.1 × 10–8
2.8 × 10–8
6.5 × 10–11
1.3 × 10–10
5.0 × 10–11
9.2 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

303

1.00 h2.80 h5.00 h

1.59 d0.265 h5.76 d2.70 dSb‑117

Sb‑118m

Sb‑119Sb‑120Sb‑120m

Sb‑122

Physicalhalf-life

Sb‑116m

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020

f1

Age ≤ 1 af1 for
g>1a
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010

e(g)
2.6 × 10–10
3.6 × 10–10
3.7 × 10–10
7.7 × 10–11
1.2 × 10–10
1.3 × 10–10
7.3 × 10–10
9.3 × 10–10
9.5 × 10–10
2.7 × 10–10
4.0 × 10–10
4.1 × 10–10
4.6 × 10–11
6.6 × 10–11
6.8 × 10–11
4.1 × 10–9
6.3 × 10–9
6.6 × 10–9
4.2 × 10–9
8.3 × 10–9
8.8 × 10–9

2.1 × 10–10
2.8 × 10–10
2.9 × 10–10
6.0 × 10–11
9.1 × 10–11
9.5 × 10–11
6.2 × 10–10
7.6 × 10–10
7.8 × 10–10
2.0 × 10–10
2.8 × 10–10
2.9 × 10–10
3.1 × 10–11
4.4 × 10–11
4.6 × 10–11
3.3 × 10–9
5.0 × 10–9
5.3 × 10–9
2.8 × 10–9
5.7 × 10–9
6.1 × 10–9e(g)Age 1–2 a

1.1 × 10–10
1.5 × 10–10
1.5 × 10–10
2.9 × 10–11
4.6 × 10–11
4.8 × 10–11
3.3 × 10–10
4.0 × 10–10
4.1 × 10–10
9.4 × 10–11
1.3 × 10–10
1.4 × 10–10
1.4 × 10–11
2.0 × 10–11
2.1 × 10–11
1.8 × 10–9
2.8 × 10–9
2.9 × 10–9
1.4 × 10–9
2.8 × 10–9
3.0 × 10–9

e(g)

2–7 a

6.6 × 10–11
9.1 × 10–11
9.4 × 10–11
1.8 × 10–11
3.0 × 10–11
3.1 × 10–11
2.0 × 10–10
2.5 × 10–10
2.5 × 10–10
5.5 × 10–11
7.9 × 10–11
8.2 × 10–11
8.9 × 10–12
1.3 × 10–11
1.4 × 10–11
1.1 × 10–9
1.8 × 10–9
1.9 × 10–9
8.4 × 10–10
1.8 × 10–9
2.0 × 10–9e(g)7–12 a4.0 × 10–11
5.9 × 10–11
6.1 × 10–11
1.0 × 10–11
2.0 × 10–11
2.2 × 10–11
1.2 × 10–10
1.5 × 10–10
1.5 × 10–10
2.9 × 10–11
4.4 × 10–11
4.5 × 10–11
5.4 × 10–12
8.3 × 10–12
8.7 × 10–12
6.7 × 10–10
1.3 × 10–9
1.4 × 10–9
4.4 × 10–10
1.3 × 10–9
1.4 × 10–9e(g)12–17 a3.2 × 10–11
4.7 × 10–11
4.9 × 10–11
8.5 × 10–12
1.6 × 10–11
1.7 × 10–11
9.3 × 10–11
1.2 × 10–10
1.2 × 10–10
2.3 × 10–11
3.5 × 10–11
3.6 × 10–11
4.6 × 10–12
7.0 × 10–12
7.3 × 10–12
5.5 × 10–10
1.0 × 10–9
1.1 × 10–9
3.6 × 10–10
1.0 × 10–9
1.1 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

304

60.2 d

0.337 h2.77 a12.4 d

0.317 h3.85 d

9.01 h

Sb‑124m

Sb‑125

Sb‑126

Sb‑126m

Sb‑127

Sb‑128

Physicalhalf-life

Sb‑124

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020

f1

Age ≤ 1 af1 for
g>1a
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010

e(g)
1.2 × 10–8
3.1 × 10–8
3.9 × 10–8
2.7 × 10–11
4.3 × 10–11
4.6 × 10–11
8.7 × 10–9
2.0 × 10–8
4.2 × 10–8
8.8 × 10–9
1.7 × 10–8
1.9 × 10–8
1.2 × 10–10
1.7 × 10–10
1.8 × 10–10
5.1 × 10–9
1.0 × 10–8
1.1 × 10–8
2.1 × 10–9
3.3 × 10–9
3.4 × 10–9

8.8 × 10–9
2.4 × 10–8
3.1 × 10–8
1.9 × 10–11
3.1 × 10–11
3.3 × 10–11
6.8 × 10–9
1.6 × 10–8
3.8 × 10–8
6.6 × 10–9
1.3 × 10–8
1.5 × 10–8
8.2 × 10–11
1.2 × 10–10
1.2 × 10–10
3.5 × 10–9
7.3 × 10–9
7.9 × 10–9
1.7 × 10–9
2.5 × 10–9
2.6 × 10–9e(g)Age 1–2 a

4.3 × 10–9
1.4 × 10–8
1.8 × 10–8
9.0 × 10–12
1.5 × 10–11
1.6 × 10–11
3.7 × 10–9
1.0 × 10–8
2.4 × 10–8
3.3 × 10–9
7.4 × 10–9
8.2 × 10–9
3.8 × 10–11
5.5 × 10–11
5.7 × 10–11
1.6 × 10–9
3.9 × 10–9
4.2 × 10–9
8.3 × 10–10
1.2 × 10–9
1.3 × 10–9

e(g)

2–7 a

2.6 × 10–9
9.6 × 10–9
1.3 × 10–8
5.6 × 10–12
9.6 × 10–12
1.0 × 10–11
2.3 × 10–9
6.8 × 10–9
1.6 × 10–8
2.1 × 10–9
5.1 × 10–9
5.0 × 10–9
2.4 × 10–11
3.5 × 10–11
3.7 × 10–11
9.7 × 10–10
2.7 × 10–9
3.0 × 10–9
5.1 × 10–10
7.9 × 10–10
8.3 × 10–10

e(g)7–12 a

1.6 × 10–9
7.7 × 10–9
1.0 × 10–8
3.4 × 10–12
6.5 × 10–12
7.2 × 10–12
1.5 × 10–9
5.8 × 10–9
1.4 × 10–8
1.2 × 10–9
3.5 × 10–9
4.0 × 10–9
1.5 × 10–11
2.3 × 10–11
2.4 × 10–11
5.2 × 10–10
2.1 × 10–9
2.3 × 10–9
2.9 × 10–10
5.0 × 10–10
5.2 × 10–10

e(g)12–17 a1.3 × 10–9
6.4 × 10–9
8.6 × 10–9
2.8 × 10–12
5.4 × 10–12
5.9 × 10–12
1.4 × 10–9
4.8 × 10–9
1.2 × 10–8
1.0 × 10–9
2.8 × 10–9
3.2 × 10–9
1.2 × 10–11
1.9 × 10–11
2.0 × 10–11
4.3 × 10–10
1.7 × 10–9
1.9 × 10–9
2.3 × 10–10
4.0 × 10–10
4.2 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

305

4.32 h

0.667 h0.383 hSb‑129Sb‑130Sb‑1312.49 h

17.0 dTe‑116

Te‑121

Tellurium

0.173 hPhysicalhalf-life

Sb‑128m

Radionuclidea

F
M
S
F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.600
0.200
0.020
0.600
0.200
0.020

0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020
0.200
0.020
0.020

f1

Age ≤ 1 a

9.8 × 10–11
1.3 × 10–10
1.4 × 10–10
1.1 × 10–9
2.0 × 10–9
2.1 × 10–9
3.0 × 10–10
4.5 × 10–10
4.6 × 10–10
3.5 × 10–10
3.9 × 10–10
3.8 × 10–10

0.300
0.100
0.010
0.300
0.100
0.010

0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010
0.100
0.010
0.010

e(g)

5.3 × 10–10
8.6 × 10–10
9.1 × 10–10
1.7 × 10–9
2.3 × 10–9
2.4 × 10–9

f1 forg>1a4.2 × 10–10
6.4 × 10–10
6.7 × 10–10
1.4 × 10–9
1.9 × 10–9
2.0 × 10–9

6.9 × 10–11
9.2 × 10–11
9.4 × 10–11
8.2 × 10–10
1.4 × 10–9
1.5 × 10–9
2.2 × 10–10
3.2 × 10–10
3.3 × 10–10
2.8 × 10–10
2.6 × 10–10
2.6 × 10–10e(g)Age 1–2 a

2.1 × 10–10
3.2 × 10–10
3.3 × 10–10
7.2 × 10–10
1.0 × 10–9
1.1 × 10–9

3.2 × 10–11
4.3 × 10–11
4.4 × 10–11
3.8 × 10–10
6.8 × 10–10
7.2 × 10–10
1.1 × 10–10
1.6 × 10–10
1.6 × 10–10
1.4 × 10–10
1.3 × 10–10
1.2 × 10–10

e(g)

2–7 a

1.3 × 10–10
2.0 × 10–10
2.1 × 10–10
4.6 × 10–10
6.8 × 10–10
7.2 × 10–10

2.0 × 10–11
2.7 × 10–11
2.8 × 10–11
2.3 × 10–10
4.4 × 10–10
4.6 × 10–10
6.6 × 10–11
9.8 × 10–11
1.0 × 10–10
7.7 × 10–11
8.0 × 10–11
7.9 × 10–11

e(g)7–12 a7.2 × 10–11
1.3 × 10–10
1.4 × 10–10
2.9 × 10–10
4.7 × 10–10
5.1 × 10–10

1.2 × 10–11
1.7 × 10–11
1.8 × 10–11
1.3 × 10–10
2.9 × 10–10
3.0 × 10–10
4.0 × 10–11
6.3 × 10–11
6.5 × 10–11
4.6 × 10–11
5.3 × 10–11
5.3 × 10–11

e(g)12–17 a5.8 × 10–11
1.0 × 10–10
1.1 × 10–10
2.4 × 10–10
3.8 × 10–10
4.1 × 10–10

1.0 × 10–11
1.4 × 10–11
1.5 × 10–11
1.0 × 10–10
2.3 × 10–10
2.5 × 10–10
3.3 × 10–11
5.1 × 10–11
5.3 × 10–11
3.5 × 10–11
4.4 × 10–11
4.4 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

306

154 d

1.00 × 1013 a

120 d

58.0 d9.35 h109 d1.16 hTe‑123

Te‑123m

Te‑125m

Te‑127

Te‑127m

Te‑129Physicalhalf-life

Te‑121m

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010

e(g)
1.4 × 10–8
1.9 × 10–8
2.3 × 10–8
1.1 × 10–8
5.6 × 10–9
5.3 × 10–9
9.8 × 10–9
1.8 × 10–8
2.0 × 10–8
6.2 × 10–9
1.5 × 10–8
1.7 × 10–8
4.3 × 10–10
1.0 × 10–9
1.2 × 10–9
2.1 × 10–8
3.5 × 10–8
4.1 × 10–8
1.8 × 10–10
3.3 × 10–10
3.5 × 10–10

1.0 × 10–8
1.5 × 10–8
1.9 × 10–8
9.1 × 10–9
4.4 × 10–9
5.0 × 10–9
6.8 × 10–9
1.3 × 10–8
1.6 × 10–8
4.2 × 10–9
1.1 × 10–8
1.3 × 10–8
3.2 × 10–10
7.3 × 10–10
7.9 × 10–10
1.4 × 10–8
2.6 × 10–8
3.3 × 10–8
1.2 × 10–10
2.2 × 10–10
2.3 × 10–10e(g)Age 1–2 a

5.3 × 10–9
8.8 × 10–9
1.2 × 10–8
6.2 × 10–9
3.0 × 10–9
3.5 × 10–9
3.4 × 10–9
8.0 × 10–9
9.8 × 10–9
2.0 × 10–9
6.6 × 10–9
7.8 × 10–9
1.4 × 10–10
3.6 × 10–10
3.9 × 10–10
6.5 × 10–9
1.5 × 10–8
2.0 × 10–8
5.1 × 10–11
9.9 × 10–11
1.0 × 10–10

e(g)

2–7 a

3.3 × 10–9
6.1 × 10–9
8.1 × 10–9
4.8 × 10–9
2.3 × 10–9
2.4 × 10–9
1.9 × 10–9
5.7 × 10–9
7.1 × 10–9
1.1 × 10–9
4.8 × 10–9
5.8 × 10–9
8.5 × 10–11
2.4 × 10–10
2.6 × 10–10
3.5 × 10–9
1.1 × 10–8
1.4 × 10–8
3.2 × 10–11
6.5 × 10–11
6.9 × 10–11

e(g)7–12 a2.1 × 10–9
5.1 × 10–9
6.9 × 10–9
4.0 × 10–9
2.0 × 10–9
2.1 × 10–9
1.1 × 10–9
5.0 × 10–9
6.3 × 10–9
6.1 × 10–10
4.3 × 10–9
5.3 × 10–9
4.5 × 10–11
1.6 × 10–10
1.7 × 10–10
2.0 × 10–9
9.2 × 10–9
1.2 × 10–8
1.9 × 10–11
4.4 × 10–11
4.7 × 10–11

e(g)12–17 a1.8 × 10–9
4.2 × 10–9
5.7 × 10–9
3.9 × 10–9
1.9 × 10–9
2.0 × 10–9
9.5 × 10–10
4.0 × 10–9
5.1 × 10–9
5.1 × 10–10
3.4 × 10–9
4.2 × 10–9
3.9 × 10–11
1.3 × 10–10
1.4 × 10–10
1.5 × 10–9
7.4 × 10–9
9.8 × 10–9
1.6 × 10–11
3.7 × 10–11
3.9 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

307

33.6 d

0.417 h1.25 d3.26 d

0.207 h0.923 h0.696 hTe‑131

Te‑131m

Te‑132

Te‑133

Te‑133m

Te‑134

Physicalhalf-life

Te‑129m

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010
0.300
0.100
0.010

e(g)
2.0 × 10–8
3.5 × 10–8
3.8 × 10–8
2.3 × 10–10
2.6 × 10–10
2.4 × 10–10
8.7 × 10–9
7.9 × 10–9
7.0 × 10–9
2.2 × 10–8
1.6 × 10–8
1.5 × 10–8
2.4 × 10–10
2.0 × 10–10
1.7 × 10–10
1.0 × 10–9
8.5 × 10–10
7.4 × 10–10
4.7 × 10–10
5.5 × 10–10
5.6 × 10–10

1.3 × 10–8
2.6 × 10–8
2.9 × 10–8
2.0 × 10–10
1.7 × 10–10
1.6 × 10–10
7.6 × 10–9
5.8 × 10–9
5.1 × 10–9
1.8 × 10–8
1.3 × 10–8
1.1 × 10–8
2.1 × 10–10
1.3 × 10–10
1.2 × 10–10
8.9 × 10–10
5.8 × 10–10
5.1 × 10–10
3.7 × 10–10
3.9 × 10–10
4.0 × 10–10e(g)Age 1–2 a

5.8 × 10–9
1.4 × 10–8
1.7 × 10–8
9.9 × 10–11
8.1 × 10–11
7.4 × 10–11
3.9 × 10–9
3.0 × 10–9
2.6 × 10–9
8.5 × 10–9
6.4 × 10–9
5.8 × 10–9
9.6 × 10–11
6.1 × 10–11
5.4 × 10–11
4.1 × 10–10
2.8 × 10–10
2.5 × 10–10
1.8 × 10–10
1.9 × 10–10
1.9 × 10–10

e(g)

2–7 a

3.1 × 10–9
9.8 × 10–9
1.2 × 10–8
5.3 × 10–11
5.2 × 10–11
4.9 × 10–11
2.0 × 10–9
1.9 × 10–9
1.8 × 10–9
4.2 × 10–9
4.0 × 10–9
3.8 × 10–9
4.6 × 10–11
3.8 × 10–11
3.5 × 10–11
2.0 × 10–10
1.7 × 10–10
1.6 × 10–10
1.0 × 10–10
1.2 × 10–10
1.3 × 10–10

e(g)7–12 a1.7 × 10–9
8.0 × 10–9
9.6 × 10–9
3.3 × 10–11
3.5 × 10–11
3.3 × 10–11
1.2 × 10–9
1.2 × 10–9
1.1 × 10–9
2.6 × 10–9
2.6 × 10–9
2.5 × 10–9
2.8 × 10–11
2.4 × 10–11
2.2 × 10–11
1.2 × 10–10
1.1 × 10–10
1.0 × 10–10
6.0 × 10–11
8.1 × 10–11
8.4 × 10–11

e(g)12–17 a1.3 × 10–9
6.6 × 10–9
7.9 × 10–9
2.3 × 10–11
2.8 × 10–11
2.8 × 10–11
8.6 × 10–10
9.4 × 10–10
9.1 × 10–10
1.8 × 10–9
2.0 × 10–9
2.0 × 10–9
1.9 × 10–11
2.0 × 10–11
1.9 × 10–11
8.1 × 10–11
8.7 × 10–11
8.4 × 10–11
4.7 × 10–11
6.6 × 10–11
6.8 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

308

1.35 h

0.883 h2.12 h13.2 h

4.18 d60.1 d

13.0 dI‑120m

I‑121

I‑123

I‑124

I‑125

I‑126

Physicalhalf-life

I‑120

IodineRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

1.3 × 10–9
1.1 × 10–9
1.0 × 10–9
8.6 × 10–10
8.2 × 10–10
8.2 × 10–10
2.3 × 10–10
2.1 × 10–10
1.9 × 10–10
8.7 × 10–10
5.3 × 10–10
4.3 × 10–10
4.7 × 10–8
1.4 × 10–8
6.2 × 10–9
2.0 × 10–8
6.9 × 10–9
2.4 × 10–9
8.1 × 10–8
2.4 × 10–8
8.3 × 10–9

e(g)
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010

f1 forg>1a

1.0 × 10–9
7.3 × 10–10
6.9 × 10–10
6.9 × 10–10
5.9 × 10–10
5.8 × 10–10
2.1 × 10–10
1.5 × 10–10
1.4 × 10–10
7.9 × 10–10
3.9 × 10–10
3.2 × 10–10
4.5 × 10–8
9.3 × 10–9
4.4 × 10–9
2.3 × 10–8
5.6 × 10–9
1.8 × 10–9
8.3 × 10–8
1.7 × 10–8
5.9 × 10–9e(g)Age 1–2 a

4.8 × 10–10
3.4 × 10–10
3.2 × 10–10
3.3 × 10–10
2.9 × 10–10
2.8 × 10–10
1.1 × 10–10
7.8 × 10–11
7.0 × 10–11
3.8 × 10–10
2.0 × 10–10
1.7 × 10–10
2.2 × 10–8
4.6 × 10–9
2.2 × 10–9
1.5 × 10–8
3.6 × 10–9
1.0 × 10–9
4.5 × 10–8
9.5 × 10–9
3.3 × 10–9

e(g)

2–7 a

2.3 × 10–10
2.1 × 10–10
2.0 × 10–10
1.8 × 10–10
1.8 × 10–10
1.8 × 10–10
6.0 × 10–11
4.9 × 10–11
4.5 × 10–11
1.8 × 10–10
1.2 × 10–10
1.1 × 10–10
1.1 × 10–8
2.5 × 10–9
1.4 × 10–9
1.1 × 10–8
2.6 × 10–9
6.7 × 10–10
2.4 × 10–8
5.5 × 10–9
2.2 × 10–9e(g)7–12 a

1.4 × 10–10
1.3 × 10–10
1.2 × 10–10
1.1 × 10–10
1.1 × 10–10
1.1 × 10–10
3.8 × 10–11
3.2 × 10–11
3.0 × 10–11
1.1 × 10–10
8.2 × 10–11
7.6 × 10–11
6.7 × 10–9
1.6 × 10–9
9.4 × 10–10
7.2 × 10–9
1.8 × 10–9
4.8 × 10–10
1.5 × 10–8
3.8 × 10–9
1.8 × 10–9e(g)12–17 a1.0 × 10–10
1.0 × 10–10
1.0 × 10–10
8.2 × 10–11
8.7 × 10–11
8.8 × 10–11
2.7 × 10–11
2.5 × 10–11
2.4 × 10–11
7.4 × 10–11
6.4 × 10–11
6.0 × 10–11
4.4 × 10–9
1.2 × 10–9
7.7 × 10–10
5.1 × 10–9
1.4 × 10–9
3.8 × 10–10
9.8 × 10–9
2.7 × 10–9
1.4 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

309

0.416 h1.57 × 107 a

12.4 h8.04 d2.30 h

1.39 h20.8 h

I‑129

I‑130

I‑131

I‑132

I‑132m

I‑133

Physicalhalf-life

I‑128

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010

e(g)
1.5 × 10–10
1.9 × 10–10
1.9 × 10–10
7.2 × 10–8
3.6 × 10–8
2.9 × 10–8
8.2 × 10–9
4.3 × 10–9
3.3 × 10–9
7.2 × 10–8
2.2 × 10–8
8.8 × 10–9
1.1 × 10–9
9.9 × 10–10
9.3 × 10–10
9.6 × 10–10
7.2 × 10–10
6.6 × 10–10
1.9 × 10–8
6.6 × 10–9
3.8 × 10–9

1.1 × 10–10
1.2 × 10–10
1.2 × 10–10
8.6 × 10–8
3.3 × 10–8
2.6 × 10–8
7.4 × 10–9
3.1 × 10–9
2.4 × 10–9
7.2 × 10–8
1.5 × 10–8
6.2 × 10–9
9.6 × 10–10
7.3 × 10–10
6.8 × 10–10
8.4 × 10–10
5.3 × 10–10
4.8 × 10–10
1.8 × 10–8
4.4 × 10–9
2.9 × 10–9e(g)Age 1–2 a

4.7 × 10–11
5.3 × 10–11
5.4 × 10–11
6.1 × 10–8
2.4 × 10–8
1.8 × 10–8
3.5 × 10–9
1.5 × 10–9
1.2 × 10–9
3.7 × 10–8
8.2 × 10–9
3.5 × 10–9
4.5 × 10–10
3.6 × 10–10
3.4 × 10–10
4.0 × 10–10
2.6 × 10–10
2.4 × 10–10
8.3 × 10–9
2.1 × 10–9
1.4 × 10–9

e(g)

2–7 a

2.7 × 10–11
3.4 × 10–11
3.5 × 10–11
6.7 × 10–8
2.4 × 10–8
1.3 × 10–8
1.6 × 10–9
9.2 × 10–10
7.9 × 10–10
1.9 × 10–8
4.7 × 10–9
2.4 × 10–9
2.2 × 10–10
2.2 × 10–10
2.1 × 10–10
1.9 × 10–10
1.6 × 10–10
1.6 × 10–10
3.8 × 10–9
1.2 × 10–9
9.0 × 10–10

e(g)7–12 a

1.6 × 10–11
2.2 × 10–11
2.3 × 10–11
4.6 × 10–8
1.9 × 10–8
1.1 × 10–8
1.0 × 10–9
5.8 × 10–10
5.1 × 10–10
1.1 × 10–8
3.4 × 10–9
2.0 × 10–9
1.3 × 10–10
1.4 × 10–10
1.4 × 10–10
1.2 × 10–10
1.1 × 10–10
1.1 × 10–10
2.2 × 10–9
7.4 × 10–10
5.3 × 10–10

e(g)12–17 a1.3 × 10–11
1.9 × 10–11
2.0 × 10–11
3.6 × 10–8
1.5 × 10–8
9.8 × 10–9
6.7 × 10–10
4.5 × 10–10
4.1 × 10–10
7.4 × 10–9
2.4 × 10–9
1.6 × 10–9
9.4 × 10–11
1.1 × 10–10
1.1 × 10–10
7.9 × 10–11
8.7 × 10–11
8.5 × 10–11
1.5 × 10–9
5.5 × 10–10
4.3 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

310

6.61 hI‑1350.750 h6.25 h1.34 d

0.498 hCs‑125

Cs‑127

Cs‑129Cs‑130

Caesium

0.876 hPhysicalhalf-life

I‑134

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S

F
M
S
F
M
S

Type

1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

4.6 × 10–10
4.8 × 10–10
4.8 × 10–10
4.1 × 10–9
2.2 × 10–9
1.8 × 10–9

1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010

1.000
0.100
0.010
1.000
0.100
0.010

e(g)

1.2 × 10–10
2.0 × 10–10
2.1 × 10–10
1.6 × 10–10
2.8 × 10–10
3.0 × 10–10
3.4 × 10–10
5.7 × 10–10
6.3 × 10–10
8.3 × 10–11
1.3 × 10–10
1.4 × 10–10

f1 forg>1a

8.3 × 10–11
1.4 × 10–10
1.4 × 10–10
1.3 × 10–10
2.2 × 10–10
2.3 × 10–10
2.8 × 10–10
4.6 × 10–10
4.9 × 10–10
5.6 × 10–11
8.7 × 10–11
9.0 × 10–11

3.7 × 10–10
3.4 × 10–10
3.4 × 10–10
3.7 × 10–9
1.6 × 10–9
1.3 × 10–9e(g)Age 1–2 a

3.9 × 10–11
6.5 × 10–11
6.8 × 10–11
6.9 × 10–11
1.1 × 10–10
1.2 × 10–10
1.4 × 10–10
2.4 × 10–10
2.5 × 10–10
2.5 × 10–11
4.0 × 10–11
4.1 × 10–11

1.8 × 10–10
1.7 × 10–10
1.7 × 10–10
1.7 × 10–9
7.8 × 10–10
6.5 × 10–10

e(g)

2–7 a

2.4 × 10–11
4.2 × 10–11
4.4 × 10–11
4.2 × 10–11
7.3 × 10–11
7.6 × 10–11
8.7 × 10–11
1.5 × 10–10
1.6 × 10–10
1.6 × 10–11
2.5 × 10–11
2.6 × 10–11

9.7 × 10–11
1.0 × 10–10
1.1 × 10–10
7.9 × 10–10
4.7 × 10–10
4.2 × 10–10

e(g)7–12 a

1.4 × 10–11
2.7 × 10–11
2.8 × 10–11
2.5 × 10–11
4.6 × 10–11
4.8 × 10–11
5.2 × 10–11
9.1 × 10–11
9.7 × 10–11
9.4 × 10–12
1.6 × 10–11
1.7 × 10–11

5.9 × 10–11
6.7 × 10–11
6.8 × 10–11
4.8 × 10–10
3.0 × 10–10
2.7 × 10–10

e(g)12–17 a1.2 × 10–11
2.2 × 10–11
2.3 × 10–11
2.0 × 10–11
3.6 × 10–11
3.8 × 10–11
4.2 × 10–11
7.3 × 10–11
7.7 × 10–11
7.8 × 10–12
1.4 × 10–11
1.4 × 10–11

4.5 × 10–11
5.4 × 10–11
5.5 × 10–11
3.2 × 10–10
2.4 × 10–10
2.2 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

311

9.69 d6.48 d

2.06 a2.90 h2.30 × 106 a

0.883 h13.1 dCs‑132

Cs‑134

Cs‑134m

Cs‑135

Cs‑135m

Cs‑136

Physicalhalf-lifeCs‑131

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010
1.000
0.100
0.010

e(g)
2.4 × 10–10
3.5 × 10–10
3.8 × 10–10
1.5 × 10–9
1.9 × 10–9
2.0 × 10–9
1.1 × 10–8
3.2 × 10–8
7.0 × 10–8
1.3 × 10–10
3.3 × 10–10
3.6 × 10–10
1.7 × 10–9
1.2 × 10–8
2.7 × 10–8
9.2 × 10–11
1.2 × 10–10
1.2 × 10–10
7.3 × 10–9
1.3 × 10–8
1.5 × 10–8

1.7 × 10–10
2.6 × 10–10
2.8 × 10–10
1.2 × 10–9
1.5 × 10–9
1.6 × 10–9
7.3 × 10–9
2.6 × 10–8
6.3 × 10–8
8.6 × 10–11
2.3 × 10–10
2.5 × 10–10
9.9 × 10–10
9.3 × 10–9
2.4 × 10–8
7.8 × 10–11
9.9 × 10–11
1.0 × 10–10
5.2 × 10–9
1.0 × 10–8
1.1 × 10–8e(g)Age 1–2 a

8.4 × 10–11
1.4 × 10–10
1.4 × 10–10
6.4 × 10–10
8.4 × 10–10
8.7 × 10–10
5.2 × 10–9
1.6 × 10–8
4.1 × 10–8
3.8 × 10–11
1.2 × 10–10
1.3 × 10–10
6.2 × 10–10
5.7 × 10–9
1.6 × 10–8
4.1 × 10–11
5.2 × 10–11
5.3 × 10–11
2.9 × 10–9
6.0 × 10–9
5.7 × 10–9

e(g)

2–7 a

5.3 × 10–11
8.5 × 10–11
9.1 × 10–11
4.1 × 10–10
5.4 × 10–10
5.6 × 10–10
5.3 × 10–9
1.2 × 10–8
2.8 × 10–8
2.5 × 10–11
8.3 × 10–11
9.2 × 10–11
6.1 × 10–10
4.1 × 10–9
1.1 × 10–8
2.4 × 10–11
3.2 × 10–11
3.3 × 10–11
2.0 × 10–9
3.7 × 10–9
4.1 × 10–9e(g)7–12 a3.2 × 10–11
5.5 × 10–11
5.9 × 10–11
2.7 × 10–10
3.7 × 10–10
3.8 × 10–10
6.3 × 10–9
1.1 × 10–8
2.3 × 10–8
1.6 × 10–11
6.6 × 10–11
7.4 × 10–11
6.8 × 10–10
3.8 × 10–9
9.5 × 10–9
1.5 × 10–11
1.9 × 10–11
2.0 × 10–11
1.4 × 10–9
3.1 × 10–9
3.5 × 10–9e(g)12–17 a2.7 × 10–11
4.4 × 10–11
4.7 × 10–11
2.3 × 10–10
2.9 × 10–10
3.0 × 10–10
6.6 × 10–9
9.1 × 10–9
2.0 × 10–8
1.4 × 10–11
5.4 × 10–11
6.0 × 10–11
6.9 × 10–10
3.1 × 10–9
8.6 × 10–9
1.2 × 10–11
1.5 × 10–11
1.6 × 10–11
1.2 × 10–9
2.5 × 10–9
2.8 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

312

0.536 hCs‑1381.61 h

2.43 d11.8 d0.243 hBa‑126

Ba‑128

Ba‑131

Ba‑131m

Bariumf

30.0 aPhysicalhalf-lifeCs‑137

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S

F
M
S
F
M
S

Type

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

1.000
0.200
0.020
1.000
0.200
0.020

f1

Age ≤ 1 a

8.8 × 10–9
3.6 × 10–8
1.1 × 10–7
2.6 × 10–10
4.0 × 10–10
4.2 × 10–10

0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010

1.000
0.100
0.010
1.000
0.100
0.010

e(g)

6.7 × 10–10
1.0 × 10–9
1.1 × 10–9
5.9 × 10–9
1.1 × 10–8
1.2 × 10–8
2.1 × 10–9
3.7 × 10–9
4.0 × 10–9
2.7 × 10–11
4.8 × 10–11
5.0 × 10–11

f1 forg>1a5.2 × 10–10
7.0 × 10–10
7.2 × 10–10
5.4 × 10–9
7.8 × 10–9
8.3 × 10–9
1.4 × 10–9
3.1 × 10–9
3.0 × 10–9
2.1 × 10–11
3.3 × 10–11
3.5 × 10–11

5.4 × 10–9
2.9 × 10–8
1.0 × 10–7
1.8 × 10–10
2.7 × 10–10
2.8 × 10–10e(g)Age 1–2 a

2.4 × 10–10
3.2 × 10–10
3.3 × 10–10
2.5 × 10–9
3.7 × 10–9
4.0 × 10–9
7.1 × 10–10
1.6 × 10–9
1.8 × 10–9
1.0 × 10–11
1.7 × 10–11
1.8 × 10–11

3.6 × 10–9
1.8 × 10–8
7.0 × 10–8
8.1 × 10–11
1.3 × 10–10
1.3 × 10–10

e(g)

2–7 a

1.4 × 10–10
2.0 × 10–10
2.1 × 10–10
1.4 × 10–9
2.4 × 10–9
2.6 × 10–9
4.7 × 10–10
1.1 × 10–9
1.3 × 10–9
6.7 × 10–12
1.2 × 10–11
1.2 × 10–11

3.7 × 10–9
1.3 × 10–8
4.8 × 10–8
5.0 × 10–11
7.8 × 10–11
8.2 × 10–11

e(g)7–12 a6.9 × 10–11
1.2 × 10–10
1.3 × 10–10
7.4 × 10–10
1.5 × 10–9
1.6 × 10–9
3.1 × 10–10
9.7 × 10–10
1.1 × 10–9
4.7 × 10–12
9.0 × 10–12
9.5 × 10–12

4.4 × 10–9
1.1 × 10–8
4.2 × 10–8
2.9 × 10–11
4.9 × 10–11
5.1 × 10–11

e(g)12–17 a7.4 × 10–11
1.0 × 10–10
1.1 × 10–10
7.6 × 10–10
1.3 × 10–9
1.4 × 10–9
2.2 × 10–10
7.6 × 10–10
8.7 × 10–10
4.0 × 10–12
7.4 × 10–12
7.8 × 10–12

4.6 × 10–9
9.7 × 10–9
3.9 × 10–8
2.4 × 10–11
4.1 × 10–11
4.3 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

313

10.7 a1.62 d

1.20 d1.38 h12.7 d0.305 h0.177 hBa‑133m

Ba‑135m

Ba‑139Ba‑140Ba‑141

Ba‑142

Physicalhalf-life

Ba‑133

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010

e(g)
1.1 × 10–8
1.5 × 10–8
3.2 × 10–8
1.4 × 10–9
3.0 × 10–9
3.1 × 10–9
1.1 × 10–9
2.4 × 10–9
2.7 × 10–9
3.3 × 10–10
5.4 × 10–10
5.7 × 10–10
1.4 × 10–8
2.7 × 10–8
2.9 × 10–8
1.9 × 10–10
3.0 × 10–10
3.2 × 10–10
1.3 × 10–10
1.8 × 10–10
1.9 × 10–10

4.5 × 10–9
1.0 × 10–8
2.9 × 10–8
1.1 × 10–9
2.2 × 10–9
2.4 × 10–9
1.0 × 10–9
1.8 × 10–9
1.9 × 10–9
2.4 × 10–10
3.5 × 10–10
3.6 × 10–10
7.8 × 10–9
2.0 × 10–8
2.2 × 10–8
1.4 × 10–10
2.0 × 10–10
2.1 × 10–10
9.6 × 10–11
1.3 × 10–10
1.3 × 10–10e(g)Age 1–2 a

2.6 × 10–9
6.4 × 10–9
2.0 × 10–8
4.9 × 10–10
1.0 × 10–9
1.1 × 10–9
4.6 × 10–10
8.9 × 10–10
8.6 × 10–10
1.1 × 10–10
1.6 × 10–10
1.6 × 10–10
3.6 × 10–9
1.1 × 10–8
1.2 × 10–8
6.4 × 10–11
9.3 × 10–11
9.7 × 10–11
4.5 × 10–11
6.1 × 10–11
6.2 × 10–11

e(g)

2–7 a

3.7 × 10–9
5.1 × 10–9
1.3 × 10–8
3.1 × 10–10
6.9 × 10–10
7.6 × 10–10
2.5 × 10–10
5.4 × 10–10
5.9 × 10–10
6.0 × 10–11
1.0 × 10–10
1.1 × 10–10
2.4 × 10–9
7.6 × 10–9
8.6 × 10–9
3.8 × 10–11
5.9 × 10–11
6.2 × 10–11
2.7 × 10–11
3.9 × 10–11
4.0 × 10–11

e(g)7–12 a6.0 × 10–9
5.5 × 10–9
1.1 × 10–8
1.5 × 10–10
5.2 × 10–10
5.8 × 10–10
1.2 × 10–10
4.1 × 10–10
4.5 × 10–10
3.1 × 10–11
6.6 × 10–11
7.0 × 10–11
1.6 × 10–9
6.2 × 10–9
7.1 × 10–9
2.1 × 10–11
3.8 × 10–11
4.0 × 10–11
1.6 × 10–11
2.5 × 10–11
2.6 × 10–11

e(g)12–17 a1.5 × 10–9
3.1 × 10–9
1.0 × 10–8
1.8 × 10–10
4.2 × 10–10
4.6 × 10–10
1.4 × 10–10
3.3 × 10–10
3.6 × 10–10
3.4 × 10–11
5.6 × 10–11
5.9 × 10–11
1.0 × 10–9
5.1 × 10–9
5.8 × 10–9
2.1 × 10–11
3.2 × 10–11
3.4 × 10–11
1.5 × 10–11
2.1 × 10–11
2.2 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

314

0.983 h4.80 h19.5 h6.00 × 104 a

1.35 × 1011 a

1.68 d

3.93 h

1.54 h

0.237 hLa‑132

La‑135

La‑137

La‑138

La‑140La‑141

La‑142

La‑143

Physicalhalf-life

La‑131LanthanumRadionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.2 × 10–10
1.8 × 10–10
1.0 × 10–9
1.5 × 10–9
1.0 × 10–10
1.3 × 10–10
2.5 × 10–8
8.6 × 10–9
3.7 × 10–7
1.3 × 10–7
5.8 × 10–9
8.8 × 10–9
8.6 × 10–10
1.4 × 10–9
5.3 × 10–10
8.1 × 10–10
1.4 × 10–10
2.1 × 10–10e(g)5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

8.7 × 10–11
1.3 × 10–10
7.7 × 10–10
1.1 × 10–9
7.7 × 10–11
1.0 × 10–10
2.3 × 10–8
8.1 × 10–9
3.5 × 10–7
1.2 × 10–7
4.2 × 10–9
6.3 × 10–9
5.5 × 10–10
9.3 × 10–10
3.8 × 10–10
5.7 × 10–10
8.6 × 10–11
1.3 × 10–10e(g)Age 1–2 a

4.2 × 10–11
6.4 × 10–11
3.7 × 10–10
5.4 × 10–10
3.8 × 10–11
4.9 × 10–11
1.5 × 10–8
5.6 × 10–9
2.4 × 10–7
9.1 × 10–8
2.0 × 10–9
3.1 × 10–9
2.3 × 10–10
4.3 × 10–10
1.8 × 10–10
2.7 × 10–10
3.7 × 10–11
6.0 × 10–11

e(g)

2–7 a

2.6 × 10–11
4.1 × 10–11
2.2 × 10–10
3.4 × 10–10
2.3 × 10–11
3.0 × 10–11
1.1 × 10–8
4.0 × 10–9
1.8 × 10–7
6.8 × 10–8
1.2 × 10–9
2.0 × 10–9
1.4 × 10–10
2.8 × 10–10
1.1 × 10–10
1.7 × 10–10
2.3 × 10–11
3.9 × 10–11

e(g)7–12 a

1.5 × 10–11
2.8 × 10–11
1.2 × 10–10
2.0 × 10–10
1.3 × 10–11
1.7 × 10–11
8.9 × 10–9
3.6 × 10–9
1.6 × 10–7
6.4 × 10–8
6.9 × 10–10
1.3 × 10–9
7.5 × 10–11
1.8 × 10–10
6.3 × 10–11
1.1 × 10–10
1.4 × 10–11
2.5 × 10–11

e(g)12–17 a1.3 × 10–11
2.3 × 10–11
1.0 × 10–10
1.6 × 10–10
1.0 × 10–11
1.4 × 10–11
8.7 × 10–9
3.6 × 10–9
1.5 × 10–7
6.4 × 10–8
5.7 × 10–10
1.1 × 10–9
6.3 × 10–11
1.5 × 10–10
5.2 × 10–11
8.9 × 10–11
1.2 × 10–11
2.1 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

315

3.00 d

17.6 h9.00 h

1.43 d138 d32.5 dCe‑135

Ce‑137

Ce‑137m

Ce‑139Ce‑141

Physicalhalf-life

Ce‑134

CeriumRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

7.6 × 10–9
1.1 × 10–8
1.2 × 10–8
2.3 × 10–9
3.6 × 10–9
3.7 × 10–9
7.5 × 10–11
1.1 × 10–10
1.1 × 10–10
1.6 × 10–9
3.1 × 10–9
3.3 × 10–9
1.1 × 10–8
7.5 × 10–9
7.8 × 10–9
1.1 × 10–8
1.4 × 10–8
1.6 × 10–8e(g)5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a5.3 × 10–9
7.6 × 10–9
8.0 × 10–9
1.7 × 10–9
2.7 × 10–9
2.8 × 10–9
5.6 × 10–11
7.6 × 10–11
7.8 × 10–11
1.1 × 10–9
2.2 × 10–9
2.3 × 10–9
8.5 × 10–9
6.1 × 10–9
6.3 × 10–9
7.3 × 10–9
1.1 × 10–8
1.2 × 10–8e(g)Age 1–2 a

2.3 × 10–9
3.7 × 10–9
3.8 × 10–9
8.5 × 10–10
1.4 × 10–9
1.4 × 10–9
2.7 × 10–11
3.6 × 10–11
3.7 × 10–11
4.6 × 10–10
1.1 × 10–9
1.0 × 10–9
4.5 × 10–9
3.6 × 10–9
3.9 × 10–9
3.5 × 10–9
6.3 × 10–9
7.1 × 10–9

e(g)

2–7 a

1.4 × 10–9
2.4 × 10–9
2.5 × 10–9
5.3 × 10–10
8.9 × 10–10
9.4 × 10–10
1.6 × 10–11
2.2 × 10–11
2.3 × 10–11
2.8 × 10–10
6.7 × 10–10
7.3 × 10–10
2.8 × 10–9
2.5 × 10–9
2.7 × 10–9
2.0 × 10–9
4.6 × 10–9
5.3 × 10–9e(g)7–12 a7.7 × 10–10
1.5 × 10–9
1.6 × 10–9
3.0 × 10–10
5.9 × 10–10
6.3 × 10–10
8.7 × 10–12
1.2 × 10–11
1.3 × 10–11
1.5 × 10–10
5.1 × 10–10
5.6 × 10–10
1.8 × 10–9
2.1 × 10–9
2.4 × 10–9
1.2 × 10–9
4.1 × 10–9
4.8 × 10–9e(g)12–17 a5.7 × 10–10
1.3 × 10–9
1.3 × 10–9
2.4 × 10–10
4.8 × 10–10
5.0 × 10–10
7.0 × 10–12
9.8 × 10–12
1.0 × 10–11
1.2 × 10–10
4.1 × 10–10
4.4 × 10–10
1.5 × 10–9
1.7 × 10–9
1.9 × 10–9
9.3 × 10–10
3.2 × 10–9
3.8 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

316

284 d

Ce‑1440.218 h1.28 h2.10 h

4.51 h19.1 h0.243 h13.6 dPr‑136

Pr‑137

Pr‑138m

Pr‑139Pr‑142

Pr‑142m

Pr‑143

Praseodymium

1.38 dPhysicalhalf-life

Ce‑143

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M
S
F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

3.6 × 10–9
5.6 × 10–9
5.9 × 10–9
3.6 × 10–7
1.9 × 10–7
2.1 × 10–7

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)1.3 × 10–10
1.3 × 10–10
1.8 × 10–10
1.9 × 10–10
5.9 × 10–10
6.0 × 10–10
1.5 × 10–10
1.6 × 10–10
5.3 × 10–9
5.5 × 10–9
6.7 × 10–11
7.0 × 10–11
1.2 × 10–8
1.3 × 10–8

f1 forg>1a

8.8 × 10–11
9.0 × 10–11
1.3 × 10–10
1.3 × 10–10
4.5 × 10–10
4.7 × 10–10
1.1 × 10–10
1.2 × 10–10
3.5 × 10–9
3.7 × 10–9
4.5 × 10–11
4.7 × 10–11
8.4 × 10–9
9.2 × 10–9

2.3 × 10–9
3.9 × 10–9
4.1 × 10–9
2.7 × 10–7
1.6 × 10–7
1.8 × 10–7e(g)Age 1–2 a

4.2 × 10–11
4.3 × 10–11
6.1 × 10–11
6.4 × 10–11
2.3 × 10–10
2.4 × 10–10
5.5 × 10–11
5.7 × 10–11
1.6 × 10–9
1.7 × 10–9
2.0 × 10–11
2.2 × 10–11
4.6 × 10–9
5.1 × 10–9

1.0 × 10–9
1.9 × 10–9
2.1 × 10–9
1.4 × 10–7
8.8 × 10–8
1.1 × 10–7

e(g)

2–7 a

2.6 × 10–11
2.7 × 10–11
3.9 × 10–11
4.0 × 10–11
1.4 × 10–10
1.5 × 10–10
3.5 × 10–11
3.7 × 10–11
1.0 × 10–9
1.1 × 10–9
1.3 × 10–11
1.4 × 10–11
3.2 × 10–9
3.6 × 10–9

6.2 × 10–10
1.3 × 10–9
1.4 × 10–9
7.8 × 10–8
5.5 × 10–8
7.3 × 10–8

e(g)7–12 a

1.6 × 10–11
1.7 × 10–11
2.4 × 10–11
2.5 × 10–11
9.0 × 10–11
9.3 × 10–11
2.3 × 10–11
2.4 × 10–11
6.2 × 10–10
6.6 × 10–10
7.9 × 10–12
8.4 × 10–12
2.7 × 10–9
3.0 × 10–9

3.3 × 10–10
9.3 × 10–10
1.0 × 10–9
4.8 × 10–8
4.1 × 10–8
5.8 × 10–8

e(g)12–17 a1.3 × 10–11
1.4 × 10–11
2.0 × 10–11
2.1 × 10–11
7.2 × 10–11
7.4 × 10–11
1.8 × 10–11
2.0 × 10–11
5.2 × 10–10
5.5 × 10–10
6.6 × 10–12
7.0 × 10–12
2.2 × 10–9
2.4 × 10–9

2.7 × 10–10
7.5 × 10–10
8.3 × 10–10
4.0 × 10–8
3.6 × 10–8
5.3 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

317

5.98 h

0.227 hPr‑145

Pr‑1470.844 h5.04 h

0.495 h5.50 h

2.49 h

11.0 d1.73 h

Nd‑136

Nd‑138

Nd‑139Nd‑139m

Nd‑141

Nd‑147

Nd‑149Neodymium0.288 hPhysicalhalf-life

Pr‑144

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S

M
S
M
S
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.9 × 10–10
1.9 × 10–10
1.6 × 10–9
1.6 × 10–9
1.5 × 10–10
1.6 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4e(g)4.6 × 10–10
4.8 × 10–10
2.3 × 10–9
2.4 × 10–9
9.0 × 10–11
9.4 × 10–11
1.1 × 10–9
1.2 × 10–9
4.1 × 10–11
4.3 × 10–11
1.1 × 10–8
1.2 × 10–8
6.8 × 10–10
7.1 × 10–10

f1 forg>1a

3.2 × 10–10
3.3 × 10–10
1.7 × 10–9
1.8 × 10–9
6.2 × 10–11
6.4 × 10–11
8.8 × 10–10
9.1 × 10–10
3.1 × 10–11
3.2 × 10–11
8.0 × 10–9
8.6 × 10–9
4.6 × 10–10
4.8 × 10–10

1.2 × 10–10
1.2 × 10–10
1.0 × 10–9
1.1 × 10–9
1.0 × 10–10
1.1 × 10–10e(g)Age 1–2 a

1.6 × 10–10
1.6 × 10–10
7.7 × 10–10
8.0 × 10–10
3.0 × 10–11
3.1 × 10–11
4.5 × 10–10
4.6 × 10–10
1.5 × 10–11
1.6 × 10–11
4.5 × 10–9
4.9 × 10–9
2.2 × 10–10
2.3 × 10–10

5.0 × 10–11
5.2 × 10–11
4.7 × 10–10
4.9 × 10–10
4.8 × 10–11
5.0 × 10–11

e(g)

2–7 a

9.8 × 10–11
1.0 × 10–10
4.8 × 10–10
5.0 × 10–10
1.9 × 10–11
2.0 × 10–11
2.9 × 10–10
3.0 × 10–10
9.6 × 10–12
1.0 × 10–11
3.2 × 10–9
3.5 × 10–9
1.5 × 10–10
1.5 × 10–10

3.2 × 10–11
3.4 × 10–11
3.0 × 10–10
3.2 × 10–10
3.1 × 10–11
3.3 × 10–11

e(g)7–12 a6.3 × 10–11
6.6 × 10–11
2.8 × 10–10
3.0 × 10–10
1.2 × 10–11
1.3 × 10–11
1.8 × 10–10
1.9 × 10–10
6.0 × 10–12
6.2 × 10–12
2.6 × 10–9
3.0 × 10–9
1.0 × 10–10
1.1 × 10–10

2.1 × 10–11
2.1 × 10–11
1.9 × 10–10
2.0 × 10–10
2.1 × 10–11
2.2 × 10–11

e(g)12–17 a5.1 × 10–11
5.4 × 10–11
2.3 × 10–10
2.5 × 10–10
9.9 × 10–12
1.0 × 10–11
1.5 × 10–10
1.5 × 10–10
4.8 × 10–12
5.0 × 10–12
2.1 × 10–9
2.4 × 10–9
8.4 × 10–11
8.9 × 10–11

1.8 × 10–11
1.8 × 10–11
1.6 × 10–10
1.7 × 10–10
1.8 × 10–11
1.8 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

318

0.348 h

265 d

363 d

17.7 a5.53 a2.62 a5.37 d41.3 d

2.21 d

Pm‑143Pm‑144Pm‑145

Pm‑146

Pm‑147

Pm‑148Pm‑148m

Pm‑1490.207 hPhysicalhalf-life

Pm‑141

Promethium

Nd‑151

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005

f1

Age ≤ 1 a

1.5 × 10–10
1.5 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4e(g)1.4 × 10–10
1.5 × 10–10
6.2 × 10–9
5.5 × 10–9
3.1 × 10–8
2.6 × 10–8
1.1 × 10–8
7.1 × 10–9
6.4 × 10–8
5.3 × 10–8
2.1 × 10–8
1.9 × 10–8
1.5 × 10–8
1.5 × 10–8
2.4 × 10–8
2.5 × 10–8
5.0 × 10–9
5.3 × 10–9

f1 forg>1a9.4 × 10–11
9.7 × 10–11
5.4 × 10–9
4.8 × 10–9
2.8 × 10–8
2.4 × 10–8
9.8 × 10–9
6.5 × 10–9
5.9 × 10–8
4.9 × 10–8
1.8 × 10–8
1.6 × 10–8
1.0 × 10–8
1.1 × 10–8
1.9 × 10–8
2.0 × 10–8
3.5 × 10–9
3.6 × 10–9

9.9 × 10–11
1.0 × 10–10e(g)Age 1–2 a

4.3 × 10–11
4.4 × 10–11
3.3 × 10–9
3.1 × 10–9
1.8 × 10–8
1.6 × 10–8
6.4 × 10–9
4.3 × 10–9
3.9 × 10–8
3.3 × 10–8
1.1 × 10–8
1.0 × 10–8
5.2 × 10–9
5.5 × 10–9
1.1 × 10–8
1.2 × 10–8
1.7 × 10–9
1.8 × 10–9

4.6 × 10–11
4.8 × 10–11

e(g)

2–7 a

2.7 × 10–11
2.8 × 10–11
2.2 × 10–9
2.1 × 10–9
1.2 × 10–8
1.1 × 10–8
4.3 × 10–9
2.9 × 10–9
2.6 × 10–8
2.2 × 10–8
7.0 × 10–9
6.8 × 10–9
3.4 × 10–9
3.7 × 10–9
7.7 × 10–9
8.3 × 10–9
1.1 × 10–9
1.2 × 10–9

3.0 × 10–11
3.1 × 10–11

e(g)7–12 a1.7 × 10–11
1.8 × 10–11
1.7 × 10–9
1.7 × 10–9
9.3 × 10–9
8.9 × 10–9
3.7 × 10–9
2.4 × 10–9
2.2 × 10–8
1.9 × 10–8
5.7 × 10–9
5.8 × 10–9
2.4 × 10–9
2.6 × 10–9
6.3 × 10–9
7.1 × 10–9
8.3 × 10–10
9.0 × 10–10

2.0 × 10–11
2.1 × 10–11

e(g)12–17 a1.4 × 10–11
1.5 × 10–11
1.5 × 10–9
1.4 × 10–9
8.2 × 10–9
7.5 × 10–9
3.6 × 10–9
2.3 × 10–9
2.1 × 10–8
1.7 × 10–8
5.0 × 10–9
4.9 × 10–9
2.0 × 10–9
2.2 × 10–9
5.1 × 10–9
5.7 × 10–9
6.7 × 10–10
7.3 × 10–10

1.7 × 10–11
1.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

319

Eu‑145
Eu‑146
Eu‑147
Eu‑148Europium

Sm‑141
Sm‑141m
Sm‑142
Sm‑145
Sm‑146
Sm‑147
Sm‑151
Sm‑153
Sm‑155
Sm‑156

5.94 d
4.61 d24.0 d54.5 d0.170 h0.377 h1.21 h340 d1.03 × 108 a
1.06 × 1011 a
90.0 a1.95 d
0.368 h9.40 h

1.18 d

Pm‑151Samarium2.68 hPhysicalhalf-life

Pm‑150Radionuclidea

M
M
M
M

M
M
M
M
M
M
M
M
M
M

M
S
M
S

Type

0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.2 × 10–9
1.2 × 10–9
3.3 × 10–9
3.4 × 10–9

3.6 × 10–9
5.5 × 10–9
4.9 × 10–9
1.4 × 10–8

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)1.5 × 10–10
3.0 × 10–10
7.5 × 10–10
8.1 × 10–9
2.7 × 10–5
2.5 × 10–5
1.1 × 10–8
4.2 × 10–9
1.5 × 10–10
1.6 × 10–9

f1 forg>1a2.9 × 10–9
4.4 × 10–9
3.7 × 10–9
1.2 × 10–8

1.0 × 10–10
2.1 × 10–10
4.8 × 10–10
6.8 × 10–9
2.6 × 10–5
2.3 × 10–5
1.0 × 10–8
2.9 × 10–9
9.9 × 10–11
1.1 × 10–9

7.9 × 10–10
8.2 × 10–10
2.5 × 10–9
2.6 × 10–9e(g)Age 1–2 a

1.6 × 10–9
2.4 × 10–9
2.2 × 10–9
6.8 × 10–9

4.7 × 10–11
9.7 × 10–11
2.2 × 10–10
4.0 × 10–9
1.7 × 10–5
1.6 × 10–5
6.7 × 10–9
1.5 × 10–9
4.4 × 10–11
5.8 × 10–10

3.8 × 10–10
3.9 × 10–10
1.2 × 10–9
1.3 × 10–9

e(g)

2–7 a

1.0 × 10–9
1.5 × 10–9
1.6 × 10–9
4.6 × 10–9

2.9 × 10–11
6.1 × 10–11
1.4 × 10–10
2.5 × 10–9
1.2 × 10–5
1.1 × 10–5
4.5 × 10–9
1.0 × 10–9
2.9 × 10–11
3.5 × 10–10

2.4 × 10–10
2.5 × 10–10
8.3 × 10–10
7.9 × 10–10

e(g)7–12 a6.8 × 10–10
1.0 × 10–9
1.3 × 10–9
3.2 × 10–9

1.8 × 10–11
3.9 × 10–11
8.5 × 10–11
1.9 × 10–9
1.1 × 10–5
9.6 × 10–6
4.0 × 10–9
7.9 × 10–10
2.0 × 10–11
2.7 × 10–10

1.5 × 10–10
1.6 × 10–10
5.3 × 10–10
5.7 × 10–10

e(g)12–17 a5.5 × 10–10
8.0 × 10–10
1.1 × 10–9
2.6 × 10–9

1.5 × 10–11
3.2 × 10–11
7.1 × 10–11
1.6 × 10–9
1.1 × 10–5
9.6 × 10–6
4.0 × 10–9
6.3 × 10–10
1.7 × 10–11
2.2 × 10–10

1.2 × 10–10
1.3 × 10–10
4.3 × 10–10
4.6 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

320

0.382 h48.3 d

1.59 d93.0 a9.40 d

Gd‑146

Gd‑147

Gd‑148

Gd‑14993.1 d34.2 a12.6 h13.3 a9.32 h8.80 a4.96 a15.2 d15.1 h
0.765 hPhysicalhalf-life

Gd‑145Gadolinium

Eu‑149Eu‑150Eu‑150m
Eu‑152
Eu‑152m
Eu‑154Eu‑155
Eu‑156
Eu‑157
Eu‑158

Radionuclidea

F
M
F
M
F
M
F
M
F
M

M
M
M
M
M
M
M
M
M
M

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.6 × 10–9
1.1 × 10–7
1.6 × 10–9
1.1 × 10–7
1.9 × 10–9
1.6 × 10–7
2.6 × 10–8
1.9 × 10–8
2.5 × 10–9
4.3 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)1.3 × 10–10
1.8 × 10–10
2.9 × 10–8
2.8 × 10–8
2.1 × 10–9
2.8 × 10–9
8.3 × 10–5
3.2 × 10–5
2.6 × 10–9
3.6 × 10–9

f1 forg>1a

9.6 × 10–11
1.3 × 10–10
2.3 × 10–8
2.2 × 10–8
1.7 × 10–9
2.2 × 10–9
7.6 × 10–5
2.9 × 10–5
2.0 × 10–9
3.0 × 10–9

1.3 × 10–9
1.1 × 10–7
1.1 × 10–9
1.0 × 10–7
1.3 × 10–9
1.5 × 10–7
2.3 × 10–8
1.4 × 10–8
1.9 × 10–9
2.9 × 10–10e(g)Age 1–2 a

4.7 × 10–11
6.2 × 10–11
1.2 × 10–8
1.3 × 10–8
8.4 × 10–10
1.1 × 10–9
4.7 × 10–5
1.9 × 10–5
8.0 × 10–10
1.5 × 10–9

7.3 × 10–10
7.8 × 10–8
5.2 × 10–10
7.0 × 10–8
6.6 × 10–10
9.7 × 10–8
1.4 × 10–8
7.7 × 10–9
8.9 × 10–10
1.3 × 10–10

e(g)

2–7 a

2.9 × 10–11
3.9 × 10–11
7.8 × 10–9
9.3 × 10–9
5.3 × 10–10
7.5 × 10–10
3.2 × 10–5
1.3 × 10–5
5.1 × 10–10
1.1 × 10–9

4.7 × 10–10
5.7 × 10–8
3.4 × 10–10
4.9 × 10–8
4.2 × 10–10
6.5 × 10–8
9.2 × 10–9
5.3 × 10–9
5.9 × 10–10
8.5 × 10–11

e(g)7–12 a1.7 × 10–11
2.4 × 10–11
5.1 × 10–9
7.9 × 10–9
3.1 × 10–10
5.1 × 10–10
2.6 × 10–5
1.2 × 10–5
3.1 × 10–10
9.2 × 10–10

3.5 × 10–10
5.3 × 10–8
2.3 × 10–10
4.3 × 10–8
2.4 × 10–10
5.6 × 10–8
7.6 × 10–9
4.2 × 10–9
3.5 × 10–10
5.6 × 10–11

e(g)12–17 a1.4 × 10–11
2.0 × 10–11
4.4 × 10–9
6.4 × 10–9
2.6 × 10–10
4.0 × 10–10
2.6 × 10–5
1.1 × 10–5
2.6 × 10–10
7.3 × 10–10

2.9 × 10–10
5.3 × 10–8
1.9 × 10–10
4.2 × 10–8
2.2 × 10–10
5.3 × 10–8
6.9 × 10–9
3.4 × 10–9
2.8 × 10–10
4.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

321

242 d

18.6 h

Gd‑153

Gd‑159Tb‑147
Tb‑149Tb‑150Tb‑151
Tb‑153
Tb‑154
Tb‑155
Tb‑156
Tb‑156m
Tb‑156mʹ
Tb‑157
Tb‑1581.65 h4.15 h3.27 h
17.6 h2.34 d
21.4 h5.32 d5.34 d
1.02 d
5.00 h
1.50 × 102 a
1.50 × 102 a

1.08 × 1014 a

Gd‑152

Terbium

120 dPhysicalhalf-life

Gd‑151

Radionuclidea

M
M
M
M
M
M
M
M
M
M
M
M

F
M
F
M
F
M
F
M

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

6.3 × 10–9
4.5 × 10–9
5.9 × 10–5
2.1 × 10–5
1.5 × 10–8
9.9 × 10–9
1.2 × 10–9
2.2 × 10–9

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)6.7 × 10–10
2.1 × 10–8
1.0 × 10–9
1.6 × 10–9
1.4 × 10–9
2.7 × 10–9
1.4 × 10–9
7.0 × 10–9
1.1 × 10–9
6.2 × 10–10
3.2 × 10–9
1.1 × 10–7

f1 forg>1a

4.8 × 10–10
1.5 × 10–8
7.4 × 10–10
1.2 × 10–9
1.0 × 10–9
2.1 × 10–9
1.0 × 10–9
5.4 × 10–9
9.4 × 10–10
4.5 × 10–10
3.0 × 10–9
1.0 × 10–7

4.9 × 10–9
3.5 × 10–9
5.4 × 10–5
1.9 × 10–5
1.2 × 10–8
7.9 × 10–9
8.9 × 10–10
1.5 × 10–9e(g)Age 1–2 a

2.3 × 10–10
9.6 × 10–9
3.5 × 10–10
6.3 × 10–10
5.4 × 10–10
1.1 × 10–9
5.6 × 10–10
3.0 × 10–9
4.7 × 10–10
2.4 × 10–10
2.0 × 10–9
7.0 × 10–8

2.5 × 10–9
2.0 × 10–9
3.4 × 10–5
1.3 × 10–5
6.5 × 10–9
4.8 × 10–9
3.8 × 10–10
7.3 × 10–10

e(g)

2–7 a

1.5 × 10–10
6.6 × 10–9
2.2 × 10–10
4.2 × 10–10
3.6 × 10–10
7.1 × 10–10
3.4 × 10–10
2.0 × 10–9
3.3 × 10–10
1.7 × 10–10
1.4 × 10–9
5.1 × 10–8

1.5 × 10–9
1.3 × 10–9
2.4 × 10–5
8.9 × 10–6
3.9 × 10–9
3.1 × 10–9
2.3 × 10–10
4.9 × 10–10

e(g)7–12 a9.3 × 10–11
5.8 × 10–9
1.3 × 10–10
2.8 × 10–10
2.3 × 10–10
4.5 × 10–10
2.7 × 10–10
1.5 × 10–9
2.7 × 10–10
1.2 × 10–10
1.2 × 10–9
4.7 × 10–8

9.2 × 10–10
1.0 × 10–9
1.9 × 10–5
7.9 × 10–6
2.4 × 10–9
2.5 × 10–9
1.2 × 10–10
3.4 × 10–10

e(g)12–17 a7.6 × 10–11
4.9 × 10–9
1.1 × 10–10
2.3 × 10–10
1.9 × 10–10
3.6 × 10–10
2.2 × 10–10
1.2 × 10–9
2.1 × 10–10
9.6 × 10–11
1.2 × 10–9
4.6 × 10–8

7.8 × 10–10
8.6 × 10–10
1.9 × 10–5
8.0 × 10–6
2.1 × 10–9
2.1 × 10–9
1.0 × 10–10
2.7 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)322

Ho‑155
Ho‑157
Ho‑159Ho‑161
Ho‑162
Ho‑162m
Ho‑164
Ho‑164m
Ho‑166
Ho‑166m
Ho‑167

Holmium

Dy‑155
Dy‑157
Dy‑159Dy‑165
Dy‑166

Dysprosium

Tb‑160Tb‑161

Radionuclidea

0.800 h0.210 h0.550 h2.50 h
0.250 h1.13 h
0.483 h0.625 h1.12 d
1.20 × 103 a
3.10 h

10.0 h8.10 h144 d2.33 h
3.40 d72.3 d
6.91 dPhysicalhalf-life

M
M
M
M
M
M
M
M
M
M
M

M
M
M
M
M

M
M

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005

f1

Age ≤ 1 a

3.2 × 10–8
6.6 × 10–9

1.7 × 10–10
3.4 × 10–11
4.6 × 10–11
5.7 × 10–11
2.1 × 10–11
1.5 × 10–10
6.8 × 10–11
9.1 × 10–11
6.0 × 10–9
2.6 × 10–7
5.2 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4

e(g)5.6 × 10–10
2.4 × 10–10
2.1 × 10–9
5.2 × 10–10
1.2 × 10–8

f1 forg>1a

1.2 × 10–10
2.5 × 10–11
3.3 × 10–11
4.0 × 10–11
1.5 × 10–11
1.1 × 10–10
4.5 × 10–11
5.9 × 10–11
4.0 × 10–9
2.5 × 10–7
3.6 × 10–10

4.4 × 10–10
1.9 × 10–10
1.7 × 10–9
3.4 × 10–10
8.3 × 10–9

2.5 × 10–8
4.7 × 10–9e(g)Age 1–2 a

5.8 × 10–11
1.3 × 10–11
1.7 × 10–11
2.0 × 10–11
7.2 × 10–12
5.8 × 10–11
2.1 × 10–11
3.0 × 10–11
1.9 × 10–9
1.8 × 10–7
1.8 × 10–10

2.3 × 10–10
9.9 × 10–11
9.6 × 10–10
1.6 × 10–10
4.4 × 10–9

1.5 × 10–8
2.6 × 10–9

e(g)

2–7 a

3.7 × 10–11
8.0 × 10–12
1.1 × 10–11
1.2 × 10–11
4.8 × 10–12
3.8 × 10–11
1.4 × 10–11
2.0 × 10–11
1.2 × 10–9
1.3 × 10–7
1.2 × 10–10

1.5 × 10–10
6.2 × 10–11
6.0 × 10–10
1.1 × 10–10
3.0 × 10–9

1.0 × 10–8
1.9 × 10–9e(g)7–12 a2.4 × 10–11
5.1 × 10–12
7.5 × 10–12
7.5 × 10–12
3.4 × 10–12
2.6 × 10–11
9.9 × 10–12
1.3 × 10–11
7.9 × 10–10
1.2 × 10–7
8.7 × 10–11

9.6 × 10–11
3.8 × 10–11
4.4 × 10–10
7.2 × 10–11
2.3 × 10–9

8.6 × 10–9
1.6 × 10–9e(g)12–17 a2.0 × 10–11
4.2 × 10–12
6.1 × 10–12
6.0 × 10–12
2.8 × 10–12
2.1 × 10–11
8.4 × 10–12
1.2 × 10–11
6.5 × 10–10
1.2 × 10–7
7.1 × 10–11

7.7 × 10–11
3.0 × 10–11
3.7 × 10–10
6.0 × 10–11
1.9 × 10–9

7.0 × 10–9
1.3 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

323

0.315 h2.36 dYb‑166

0.362 h7.70 h
9.24 d129 d1.92 a2.65 d8.24 h
0.253 h3.24 h10.4 h
9.30 d7.52 h2.05 dPhysicalhalf-life

Yb‑162

Ytterbium

Tm‑162
Tm‑166
Tm‑167
Tm‑170Tm‑171
Tm‑172
Tm‑173
Tm‑175

Thulium

Er‑161Er‑165
Er‑169Er‑171
Er‑172

ErbiumRadionuclidea

M
S
M
S

M
M
M
M
M
M
M
M

M
M
M
M
M

Type

0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.1 × 10–10
1.2 × 10–10
4.7 × 10–9
4.9 × 10–9

1.3 × 10–10
1.3 × 10–9
5.6 × 10–9
3.6 × 10–8
6.8 × 10–9
8.4 × 10–9
1.5 × 10–9
1.6 × 10–10

3.8 × 10–10
7.2 × 10–11
4.7 × 10–9
1.8 × 10–9
6.6 × 10–9e(g)5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

7.9 × 10–11
8.2 × 10–11
3.5 × 10–9
3.7 × 10–9

9.6 × 10–11
9.9 × 10–10
4.1 × 10–9
2.8 × 10–8
5.7 × 10–9
5.8 × 10–9
1.0 × 10–9
1.1 × 10–10

2.9 × 10–10
5.3 × 10–11
3.5 × 10–9
1.2 × 10–9
4.7 × 10–9e(g)Age 1–2 a

3.9 × 10–11
4.0 × 10–11
1.9 × 10–9
2.0 × 10–9

4.7 × 10–11
5.2 × 10–10
2.3 × 10–9
1.6 × 10–8
3.4 × 10–9
2.9 × 10–9
5.0 × 10–10
5.0 × 10–11

1.5 × 10–10
2.6 × 10–11
2.0 × 10–9
5.9 × 10–10
2.5 × 10–9

e(g)

2–7 a

2.5 × 10–11
2.6 × 10–11
1.3 × 10–9
1.3 × 10–9

3.0 × 10–11
3.3 × 10–10
1.7 × 10–9
1.1 × 10–8
2.0 × 10–9
1.9 × 10–9
3.3 × 10–10
3.3 × 10–11

9.5 × 10–11
1.6 × 10–11
1.5 × 10–9
3.9 × 10–10
1.7 × 10–9e(g)7–12 a

1.6 × 10–11
1.7 × 10–11
9.0 × 10–10
9.6 × 10–10

1.9 × 10–11
2.2 × 10–10
1.4 × 10–9
8.5 × 10–9
1.6 × 10–9
1.4 × 10–9
2.2 × 10–10
2.2 × 10–11

6.0 × 10–11
9.6 × 10–12
1.3 × 10–9
2.7 × 10–10
1.4 × 10–9e(g)12–17 a1.3 × 10–11
1.4 × 10–11
7.2 × 10–10
7.7 × 10–10

1.6 × 10–11
1.7 × 10–10
1.1 × 10–9
7.0 × 10–9
1.4 × 10–9
1.1 × 10–9
1.8 × 10–10
1.8 × 10–11

4.8 × 10–11
7.9 × 10–12
1.0 × 10–9
2.2 × 10–10
1.1 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

324

32.0 d

4.19 d

1.90 h1.23 h

Yb‑169

Yb‑175

Yb‑177

Yb‑1781.42 d2.00 d8.22 d6.70 d1.37 aLu‑169Lu‑170Lu‑171

Lu‑172

Lu‑173

Lutetium

0.292 hPhysicalhalf-life

Yb‑167

Radionuclidea

M
S
M
S
M
S
M
S
M
S

M
S
M
S
M
S
M
S
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

4.4 × 10–11
4.6 × 10–11
1.2 × 10–8
1.3 × 10–8
3.5 × 10–9
3.7 × 10–9
5.0 × 10–10
5.3 × 10–10
5.9 × 10–10
6.2 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)2.3 × 10–9
2.4 × 10–9
4.3 × 10–9
4.5 × 10–9
5.0 × 10–9
4.7 × 10–9
8.7 × 10–9
9.3 × 10–9
1.0 × 10–8
1.0 × 10–8

f1 forg>1a

1.8 × 10–9
1.9 × 10–9
3.4 × 10–9
3.5 × 10–9
3.7 × 10–9
3.9 × 10–9
6.7 × 10–9
7.1 × 10–9
8.5 × 10–9
8.7 × 10–9

3.1 × 10–11
3.2 × 10–11
8.7 × 10–9
9.8 × 10–9
2.5 × 10–9
2.7 × 10–9
3.3 × 10–10
3.5 × 10–10
3.9 × 10–10
4.1 × 10–10e(g)Age 1–2 a

9.5 × 10–10
1.0 × 10–9
1.8 × 10–9
1.8 × 10–9
2.1 × 10–9
2.0 × 10–9
3.8 × 10–9
4.0 × 10–9
5.1 × 10–9
5.4 × 10–9

1.6 × 10–11
1.7 × 10–11
5.1 × 10–9
5.9 × 10–9
1.4 × 10–9
1.5 × 10–9
1.6 × 10–10
1.7 × 10–10
1.8 × 10–10
1.9 × 10–10

e(g)

2–7 a

6.3 × 10–10
6.7 × 10–10
1.2 × 10–9
1.2 × 10–9
1.2 × 10–9
1.4 × 10–9
2.6 × 10–9
2.8 × 10–9
3.2 × 10–9
3.6 × 10–9

1.1 × 10–11
1.1 × 10–11
3.7 × 10–9
4.2 × 10–9
9.8 × 10–10
1.1 × 10–9
1.1 × 10–10
1.2 × 10–10
1.2 × 10–10
1.3 × 10–10

e(g)7–12 a4.4 × 10–10
4.8 × 10–10
7.8 × 10–10
8.2 × 10–10
9.8 × 10–10
1.1 × 10–9
1.8 × 10–9
2.0 × 10–9
2.5 × 10–9
2.9 × 10–9

7.9 × 10–12
8.4 × 10–12
3.2 × 10–9
3.7 × 10–9
8.3 × 10–10
9.2 × 10–10
7.8 × 10–11
8.4 × 10–11
8.5 × 10–11
9.1 × 10–11

e(g)12–17 a3.5 × 10–10
3.8 × 10–10
6.3 × 10–10
6.6 × 10–10
8.0 × 10–10
8.8 × 10–10
1.4 × 10–9
1.6 × 10–9
2.2 × 10–9
2.4 × 10–9

6.5 × 10–12
6.9 × 10–12
2.5 × 10–9
3.0 × 10–9
6.5 × 10–10
7.3 × 10–10
6.4 × 10–11
6.9 × 10–11
7.0 × 10–11
7.5 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

325

3.60 × 1010 a

3.68 h

6.71 d161 d0.473 h0.378 h4.59 hLu‑176

Lu‑176m

Lu‑177

Lu‑177m

Lu‑178

Lu‑178m

Lu‑179Hf‑17016.0 h142 d

Lu‑174m

Hafnium

3.31 aPhysicalhalf-life

Lu‑174

Radionuclidea

F
M

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type

0.020
0.020

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.7 × 10–8
1.6 × 10–8
1.9 × 10–8
2.0 × 10–8
1.8 × 10–7
1.5 × 10–7
8.9 × 10–10
9.3 × 10–10
5.3 × 10–9
5.7 × 10–9
5.8 × 10–8
6.5 × 10–8
2.3 × 10–10
2.4 × 10–10
2.6 × 10–10
2.7 × 10–10
9.9 × 10–10
1.0 × 10–9

0.002
0.002

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4e(g)1.4 × 10–9
2.2 × 10–9

f1 forg>1a

1.1 × 10–9
1.7 × 10–9

1.5 × 10–8
1.4 × 10–8
1.4 × 10–8
1.5 × 10–8
1.7 × 10–7
1.4 × 10–7
5.9 × 10–10
6.2 × 10–10
3.8 × 10–9
4.1 × 10–9
4.6 × 10–8
5.3 × 10–8
1.5 × 10–10
1.5 × 10–10
1.8 × 10–10
1.9 × 10–10
6.5 × 10–10
6.8 × 10–10e(g)Age 1–2 a

5.4 × 10–10
8.7 × 10–10

9.1 × 10–9
8.9 × 10–9
8.6 × 10–9
9.2 × 10–9
1.1 × 10–7
9.4 × 10–8
2.8 × 10–10
3.0 × 10–10
2.2 × 10–9
2.4 × 10–9
2.8 × 10–8
3.2 × 10–8
6.6 × 10–11
6.9 × 10–11
8.3 × 10–11
8.7 × 10–11
3.0 × 10–10
3.2 × 10–10

e(g)

2–7 a

3.4 × 10–10
5.8 × 10–10

5.8 × 10–9
5.9 × 10–9
5.4 × 10–9
6.1 × 10–9
7.8 × 10–8
6.5 × 10–8
1.9 × 10–10
2.0 × 10–10
1.6 × 10–9
1.7 × 10–9
1.9 × 10–8
2.3 × 10–8
4.3 × 10–11
4.5 × 10–11
5.6 × 10–11
5.8 × 10–11
2.0 × 10–10
2.1 × 10–10

e(g)7–12 a2.0 × 10–10
3.9 × 10–10

4.7 × 10–9
4.9 × 10–9
4.3 × 10–9
5.0 × 10–9
7.1 × 10–8
5.9 × 10–8
1.2 × 10–10
1.2 × 10–10
1.4 × 10–9
1.5 × 10–9
1.6 × 10–8
2.0 × 10–8
2.9 × 10–11
3.0 × 10–11
3.8 × 10–11
4.0 × 10–11
1.2 × 10–10
1.3 × 10–10

e(g)12–17 a1.6 × 10–10
3.2 × 10–10

4.2 × 10–9
4.2 × 10–9
3.7 × 10–9
4.2 × 10–9
7.0 × 10–8
5.6 × 10–8
1.1 × 10–10
1.2 × 10–10
1.1 × 10–9
1.2 × 10–9
1.3 × 10–8
1.6 × 10–8
2.4 × 10–11
2.6 × 10–11
3.2 × 10–11
3.3 × 10–11
1.1 × 10–10
1.2 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

326

1.87 a24.0 h

70.0 d

0.856 h31.0 a25.1 d5.50 h42.4 d

9.00 × 106 a

1.02 h1.07 hHf‑173

Hf‑175

Hf‑177m

Hf‑178m

Hf‑179m

Hf‑180m

Hf‑181

Hf‑182

Hf‑182m

Hf‑183

Physicalhalf-life

Hf‑172

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 af1 for
g>1a
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002
0.002

e(g)
1.5 × 10–7
8.1 × 10–8
6.6 × 10–10
1.1 × 10–9
5.4 × 10–9
5.8 × 10–9
3.9 × 10–10
6.5 × 10–10
6.2 × 10–7
2.6 × 10–7
9.7 × 10–9
1.7 × 10–8
5.4 × 10–10
9.1 × 10–10
1.3 × 10–8
2.2 × 10–8
6.5 × 10–7
2.4 × 10–7
1.9 × 10–10
3.2 × 10–10
2.5 × 10–10
4.4 × 10–10

1.3 × 10–7
6.9 × 10–8
5.0 × 10–10
8.2 × 10–10
4.0 × 10–9
4.5 × 10–9
2.8 × 10–10
4.7 × 10–10
5.8 × 10–7
2.4 × 10–7
6.8 × 10–9
1.3 × 10–8
4.1 × 10–10
6.8 × 10–10
9.6 × 10–9
1.7 × 10–8
6.2 × 10–7
2.3 × 10–7
1.4 × 10–10
2.3 × 10–10
1.7 × 10–10
3.0 × 10–10e(g)Age 1–2 a

7.8 × 10–8
4.3 × 10–8
2.5 × 10–10
4.3 × 10–10
2.1 × 10–9
2.6 × 10–9
1.3 × 10–10
2.3 × 10–10
4.0 × 10–7
1.7 × 10–7
3.4 × 10–9
7.6 × 10–9
2.0 × 10–10
3.6 × 10–10
4.8 × 10–9
9.9 × 10–9
4.4 × 10–7
1.7 × 10–7
6.6 × 10–11
1.2 × 10–10
7.9 × 10–11
1.5 × 10–10

e(g)

2–7 a

4.9 × 10–8
2.8 × 10–8
1.5 × 10–10
2.9 × 10–10
1.3 × 10–9
1.8 × 10–9
8.5 × 10–11
1.5 × 10–10
3.1 × 10–7
1.3 × 10–7
2.1 × 10–9
5.5 × 10–9
1.3 × 10–10
2.4 × 10–10
2.8 × 10–9
7.1 × 10–9
3.6 × 10–7
1.3 × 10–7
4.2 × 10–11
7.8 × 10–11
4.9 × 10–11
9.8 × 10–11

e(g)7–12 a3.5 × 10–8
2.3 × 10–8
8.9 × 10–11
2.0 × 10–10
8.5 × 10–10
1.4 × 10–9
5.2 × 10–11
1.1 × 10–10
2.7 × 10–7
1.2 × 10–7
1.2 × 10–9
4.8 × 10–9
7.2 × 10–11
1.7 × 10–10
1.7 × 10–9
6.3 × 10–9
3.1 × 10–7
1.3 × 10–7
2.6 × 10–11
5.6 × 10–11
2.8 × 10–11
7.0 × 10–11

e(g)12–17 a3.2 × 10–8
2.0 × 10–8
7.4 × 10–11
1.6 × 10–10
7.2 × 10–10
1.2 × 10–9
4.4 × 10–11
9.0 × 10–11
2.6 × 10–7
1.2 × 10–7
1.1 × 10–9
3.8 × 10–9
5.9 × 10–11
1.3 × 10–10
1.4 × 10–9
5.0 × 10–9
3.1 × 10–7
1.3 × 10–7
2.1 × 10–11
4.6 × 10–11
2.4 × 10–11
5.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

327

0.613 h3.65 h1.20 h10.5 h8.08 h2.36 d

2.20 h1.82 a1.00 × 1013 a

Ta‑173

Ta‑174

Ta‑175

Ta‑176

Ta‑177

Ta‑178

Ta‑179Ta‑1804.12 hPhysicalhalf-life

Ta‑172

Tantalum

Hf‑184

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M

Type

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.020
0.020

f1

Age ≤ 1 a

1.4 × 10–9
2.6 × 10–9

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

0.002
0.002

e(g)

2.8 × 10–10
2.9 × 10–10
8.8 × 10–10
9.2 × 10–10
3.2 × 10–10
3.4 × 10–10
9.1 × 10–10
9.5 × 10–10
1.4 × 10–9
1.4 × 10–9
6.5 × 10–10
6.9 × 10–10
4.4 × 10–10
4.6 × 10–10
1.2 × 10–9
2.4 × 10–9
2.7 × 10–8
7.0 × 10–8

f1 forg>1a

1.9 × 10–10
2.0 × 10–10
6.2 × 10–10
6.5 × 10–10
2.2 × 10–10
2.3 × 10–10
7.0 × 10–10
7.3 × 10–10
1.1 × 10–9
1.1 × 10–9
4.7 × 10–10
5.0 × 10–10
3.3 × 10–10
3.4 × 10–10
9.6 × 10–10
2.1 × 10–9
2.2 × 10–8
6.5 × 10–8

9.6 × 10–10
1.8 × 10–9e(g)Age 1–2 a

9.3 × 10–11
9.8 × 10–11
3.0 × 10–10
3.2 × 10–10
1.1 × 10–10
1.1 × 10–10
3.7 × 10–10
3.8 × 10–10
5.7 × 10–10
5.9 × 10–10
2.5 × 10–10
2.7 × 10–10
1.7 × 10–10
1.8 × 10–10
5.5 × 10–10
1.3 × 10–9
1.3 × 10–8
4.5 × 10–8

4.3 × 10–10
8.9 × 10–10

e(g)

2–7 a

6.0 × 10–11
6.3 × 10–11
2.0 × 10–10
2.1 × 10–10
7.1 × 10–11
7.5 × 10–11
2.4 × 10–10
2.5 × 10–10
3.7 × 10–10
3.8 × 10–10
1.5 × 10–10
1.7 × 10–10
1.1 × 10–10
1.2 × 10–10
3.5 × 10–10
8.3 × 10–10
9.2 × 10–9
3.1 × 10–8

2.7 × 10–10
5.9 × 10–10

e(g)7–12 a4.0 × 10–11
4.2 × 10–11
1.3 × 10–10
1.4 × 10–10
5.0 × 10–11
5.3 × 10–11
1.5 × 10–10
1.6 × 10–10
2.4 × 10–10
2.5 × 10–10
1.2 × 10–10
1.3 × 10–10
8.0 × 10–11
8.5 × 10–11
2.6 × 10–10
6.4 × 10–10
7.9 × 10–9
2.8 × 10–8

1.4 × 10–10
4.0 × 10–10

e(g)12–17 a3.3 × 10–11
3.5 × 10–11
1.1 × 10–10
1.1 × 10–10
4.1 × 10–11
4.3 × 10–11
1.2 × 10–10
1.3 × 10–10
1.9 × 10–10
2.0 × 10–10
9.6 × 10–11
1.1 × 10–10
6.5 × 10–11
6.8 × 10–11
2.2 × 10–10
5.6 × 10–10
6.4 × 10–9
2.6 × 10–8

1.2 × 10–10
3.3 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

328

0.264 h5.10 d8.70 h

0.816 h0.175 hTa‑182m

Ta‑183

Ta‑184

Ta‑185

Ta‑186

W‑176
W‑177
W‑178
W‑179
W‑181
W‑185

2.30 h2.25 h21.7 d
0.625 h121 d75.1 d115 d

Ta‑182Tungsten

8.10 hPhysicalhalf-life

Ta‑180m

Radionuclidea

F
F
F
F
F
F

M
S
M
S
M
S
M
S
M
S
M
S
M
S

Type

0.600
0.600
0.600
0.600
0.600
0.600

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

f1

Age ≤ 1 a

3.1 × 10–10
3.3 × 10–10
3.2 × 10–8
4.2 × 10–8
1.6 × 10–10
1.6 × 10–10
1.0 × 10–8
1.1 × 10–8
3.2 × 10–9
3.4 × 10–9
3.8 × 10–10
4.0 × 10–10
1.6 × 10–10
1.6 × 10–10

0.300
0.300
0.300
0.300
0.300
0.300

0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001
0.001

e(g)

3.3 × 10–10
2.0 × 10–10
7.2 × 10–10
9.3 × 10–12
2.5 × 10–10
1.4 × 10–9

f1 forg>1a2.7 × 10–10
1.6 × 10–10
5.4 × 10–10
6.8 × 10–12
1.9 × 10–10
1.0 × 10–9

2.2 × 10–10
2.3 × 10–10
2.6 × 10–8
3.4 × 10–8
1.1 × 10–10
1.1 × 10–10
7.4 × 10–9
8.0 × 10–9
2.3 × 10–9
2.4 × 10–9
2.5 × 10–10
2.6 × 10–10
1.1 × 10–10
1.1 × 10–10e(g)Age 1–2 a

1.4 × 10–10
8.2 × 10–11
2.5 × 10–10
3.3 × 10–12
9.2 × 10–11
4.4 × 10–10

1.1 × 10–10
1.2 × 10–10
1.5 × 10–8
2.1 × 10–8
4.9 × 10–11
5.2 × 10–11
4.1 × 10–9
4.5 × 10–9
1.1 × 10–9
1.2 × 10–9
1.2 × 10–10
1.2 × 10–10
4.8 × 10–11
5.0 × 10–11

e(g)

2–7 a

8.6 × 10–11
5.1 × 10–11
1.6 × 10–10
2.0 × 10–12
5.7 × 10–11
2.7 × 10–10

7.4 × 10–11
7.9 × 10–11
1.1 × 10–8
1.5 × 10–8
3.4 × 10–11
3.6 × 10–11
2.9 × 10–9
3.2 × 10–9
7.5 × 10–10
7.9 × 10–10
7.7 × 10–11
8.2 × 10–11
3.1 × 10–11
3.2 × 10–11

e(g)7–12 a5.0 × 10–11
3.0 × 10–11
8.7 × 10–11
1.2 × 10–12
3.2 × 10–11
1.4 × 10–10

4.8 × 10–11
5.2 × 10–11
9.5 × 10–9
1.3 × 10–8
2.4 × 10–11
2.5 × 10–11
2.4 × 10–9
2.7 × 10–9
5.0 × 10–10
5.4 × 10–10
5.4 × 10–11
5.7 × 10–11
2.0 × 10–11
2.1 × 10–11

e(g)12–17 a4.1 × 10–11
2.4 × 10–11
7.2 × 10–11
9.2 × 10–13
2.7 × 10–11
1.2 × 10–10

4.4 × 10–11
4.2 × 10–11
7.6 × 10–9
1.0 × 10–8
2.0 × 10–11
2.1 × 10–11
1.9 × 10–9
2.1 × 10–9
4.1 × 10–10
4.3 × 10–10
4.5 × 10–11
4.8 × 10–11
1.7 × 10–11
1.8 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

329

0.233 h0.220 h20.0 h

2.67 d12.7 h

38.0 d165 d3.78 d2.00 × 105 a

Re‑178

Re‑181

Re‑182

Re‑182m

Re‑184

Re‑184m

Re‑186

Re‑186m

23.9 h69.4 dPhysicalhalf-life

Re‑177

Rhenium

W‑187
W‑188

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

F
F

Type

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

0.600
0.600

f1

Age ≤ 1 a

2.0 × 10–9
7.1 × 10–9

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

0.300
0.300

e(g)

9.4 × 10–11
1.1 × 10–10
9.9 × 10–11
1.3 × 10–10
2.0 × 10–9
2.1 × 10–9
6.5 × 10–9
8.7 × 10–9
1.3 × 10–9
1.4 × 10–9
4.1 × 10–9
9.1 × 10–9
6.6 × 10–9
2.9 × 10–8
7.3 × 10–9
8.7 × 10–9
1.2 × 10–8
5.9 × 10–8

f1 forg>1a6.7 × 10–11
7.9 × 10–11
6.8 × 10–11
8.5 × 10–11
1.4 × 10–9
1.5 × 10–9
4.7 × 10–9
6.3 × 10–9
1.0 × 10–9
1.1 × 10–9
2.9 × 10–9
6.8 × 10–9
4.6 × 10–9
2.2 × 10–8
4.7 × 10–9
5.7 × 10–9
7.0 × 10–9
4.6 × 10–8

1.5 × 10–9
5.0 × 10–9e(g)Age 1–2 a

3.2 × 10–11
3.9 × 10–11
3.1 × 10–11
3.9 × 10–11
6.7 × 10–10
7.4 × 10–10
2.2 × 10–9
3.4 × 10–9
4.9 × 10–10
5.7 × 10–10
1.4 × 10–9
4.0 × 10–9
2.0 × 10–9
1.3 × 10–8
2.0 × 10–9
2.8 × 10–9
2.9 × 10–9
2.7 × 10–8

7.0 × 10–10
2.2 × 10–9

e(g)

2–7 a

1.9 × 10–11
2.5 × 10–11
1.9 × 10–11
2.6 × 10–11
3.8 × 10–10
4.6 × 10–10
1.3 × 10–9
2.2 × 10–9
2.8 × 10–10
3.6 × 10–10
8.6 × 10–10
2.8 × 10–9
1.2 × 10–9
9.3 × 10–9
1.1 × 10–9
1.8 × 10–9
1.7 × 10–9
1.8 × 10–8

4.3 × 10–10
1.3 × 10–9e(g)7–12 a

1.2 × 10–11
1.7 × 10–11
1.2 × 10–11
1.7 × 10–11
2.3 × 10–10
3.1 × 10–10
8.0 × 10–10
1.5 × 10–9
1.7 × 10–10
2.5 × 10–10
5.4 × 10–10
2.4 × 10–9
7.3 × 10–10
8.1 × 10–9
6.6 × 10–10
1.4 × 10–9
1.0 × 10–9
1.4 × 10–8

2.3 × 10–10
6.8 × 10–10

e(g)12–17 a9.7 × 10–12
1.4 × 10–11
1.0 × 10–11
1.4 × 10–11
1.8 × 10–10
2.5 × 10–10
6.4 × 10–10
1.2 × 10–9
1.4 × 10–10
2.0 × 10–10
4.4 × 10–10
1.9 × 10–9
5.9 × 10–10
6.5 × 10–9
5.2 × 10–10
1.1 × 10–9
8.3 × 10–10
1.2 × 10–8

1.9 × 10–10
5.7 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

330

17.0 h

0.310 h1.01 dRe‑188

Re‑188m

Re‑1890.366 h1.75 h

22.0 h

94.0 dOs‑180Os‑181

Os‑182

Os‑185

Osmium5.00 × 1010 a

Physicalhalf-life

Re‑187

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S

F
M
F
M
F
M
F
M

Type

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

Age ≤ 1 a

7.1 × 10–11
1.1 × 10–10
1.1 × 10–10
3.0 × 10–10
4.5 × 10–10
4.7 × 10–10
1.6 × 10–9
2.5 × 10–9
2.6 × 10–9
7.2 × 10–9
6.6 × 10–9
7.0 × 10–9

2.6 × 10–11
5.7 × 10–11
6.5 × 10–9
6.0 × 10–9
1.4 × 10–10
1.3 × 10–10
3.7 × 10–9
3.9 × 10–9

e(g)

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.800
0.800
0.800
0.800
0.800
0.800
0.800
0.800

f1 forg>1a5.3 × 10–11
7.9 × 10–11
8.2 × 10–11
2.3 × 10–10
3.4 × 10–10
3.6 × 10–10
1.2 × 10–9
1.9 × 10–9
2.0 × 10–9
5.8 × 10–9
5.4 × 10–9
5.8 × 10–9

1.6 × 10–11
4.1 × 10–11
4.4 × 10–9
4.0 × 10–9
9.1 × 10–11
8.6 × 10–11
2.5 × 10–9
2.6 × 10–9e(g)Age 1–2 a

2.6 × 10–11
3.9 × 10–11
4.1 × 10–11
1.1 × 10–10
1.8 × 10–10
1.8 × 10–10
6.0 × 10–10
1.0 × 10–9
1.0 × 10–9
3.1 × 10–9
2.9 × 10–9
3.6 × 10–9

6.8 × 10–12
2.0 × 10–11
1.9 × 10–9
1.8 × 10–9
4.0 × 10–11
4.0 × 10–11
1.1 × 10–9
1.2 × 10–9

e(g)

2–7 a

1.6 × 10–11
2.5 × 10–11
2.6 × 10–11
7.0 × 10–11
1.1 × 10–10
1.2 × 10–10
3.7 × 10–10
6.6 × 10–10
6.9 × 10–10
1.9 × 10–9
2.0 × 10–9
2.4 × 10–9

3.8 × 10–12
1.2 × 10–11
1.0 × 10–9
1.0 × 10–9
2.1 × 10–11
2.7 × 10–11
5.8 × 10–10
7.6 × 10–10

e(g)7–12 a1.0 × 10–11
1.7 × 10–11
1.8 × 10–11
4.1 × 10–11
7.6 × 10–11
8.1 × 10–11
2.1 × 10–10
4.5 × 10–10
4.8 × 10–10
1.2 × 10–9
1.5 × 10–9
1.9 × 10–9

2.3 × 10–12
7.5 × 10–12
6.1 × 10–10
6.8 × 10–10
1.3 × 10–11
1.6 × 10–11
3.5 × 10–10
5.5 × 10–10

e(g)12–17 a8.2 × 10–12
1.4 × 10–11
1.5 × 10–11
3.3 × 10–11
6.2 × 10–11
6.5 × 10–11
1.7 × 10–10
3.6 × 10–10
3.8 × 10–10
1.1 × 10–9
1.3 × 10–9
1.6 × 10–9

1.8 × 10–12
6.3 × 10–12
4.6 × 10–10
5.4 × 10–10
1.0 × 10–11
1.3 × 10–11
2.7 × 10–10
4.3 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

331

13.0 h1.25 d

6.00 aOs‑191m

Os‑193

Os‑194

Ir‑1820.250 h15.4 dOs‑191

Iridium

6.00 hPhysicalhalf-life

Os‑189m

Radionuclidea

F
M
S

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type

0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 a

3.8 × 10–11
6.5 × 10–11
6.8 × 10–11
2.8 × 10–9
8.0 × 10–9
9.0 × 10–9
3.0 × 10–10
7.8 × 10–10
8.5 × 10–10
1.9 × 10–9
3.8 × 10–9
4.0 × 10–9
8.7 × 10–8
9.9 × 10–8
2.6 × 10–7

0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)

1.4 × 10–10
2.1 × 10–10
2.2 × 10–10

f1 forg>1a

9.8 × 10–11
1.4 × 10–10
1.5 × 10–10

2.8 × 10–11
4.1 × 10–11
4.3 × 10–11
1.9 × 10–9
5.8 × 10–9
6.5 × 10–9
2.0 × 10–10
5.4 × 10–10
6.0 × 10–10
1.2 × 10–9
2.6 × 10–9
2.7 × 10–9
6.8 × 10–8
8.3 × 10–8
2.4 × 10–7e(g)Age 1–2 a

4.5 × 10–11
6.7 × 10–11
6.9 × 10–11

1.2 × 10–11
1.8 × 10–11
1.9 × 10–11
8.5 × 10–10
3.4 × 10–9
3.9 × 10–9
8.8 × 10–11
3.1 × 10–10
3.4 × 10–10
5.2 × 10–10
1.3 × 10–9
1.3 × 10–9
3.4 × 10–8
4.8 × 10–8
1.6 × 10–7

e(g)

2–7 a

2.8 × 10–11
4.3 × 10–11
4.4 × 10–11

7.0 × 10–12
1.1 × 10–11
1.2 × 10–11
5.3 × 10–10
2.4 × 10–9
2.7 × 10–9
5.4 × 10–11
2.1 × 10–10
2.4 × 10–10
3.2 × 10–10
8.4 × 10–10
9.0 × 10–10
2.1 × 10–8
3.1 × 10–8
1.1 × 10–7

e(g)7–12 a1.7 × 10–11
2.8 × 10–11
2.9 × 10–11

3.5 × 10–12
6.0 × 10–12
6.3 × 10–12
3.0 × 10–10
2.0 × 10–9
2.3 × 10–9
2.9 × 10–11
1.7 × 10–10
2.0 × 10–10
1.8 × 10–10
5.9 × 10–10
6.4 × 10–10
1.3 × 10–8
2.4 × 10–8
8.8 × 10–8

e(g)12–17 a1.4 × 10–11
2.3 × 10–11
2.4 × 10–11

2.5 × 10–12
5.0 × 10–12
5.3 × 10–12
2.5 × 10–10
1.7 × 10–9
1.9 × 10–9
2.4 × 10–11
1.4 × 10–10
1.6 × 10–10
1.6 × 10–10
4.8 × 10–10
5.2 × 10–10
1.1 × 10–8
2.1 × 10–8
8.5 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

332

3.02 h

14.0 h15.8 h

1.75 h10.5 h1.73 d13.3 dIr‑185

Ir‑186

Ir‑186m

Ir‑187

Ir‑188

Ir‑189Physicalhalf-life

Ir‑184

Radionuclidea
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

f1

F
M

Type

Age ≤ 1 af1 for
g>1a
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)
5.7 × 10–10
8.6 × 10–10
8.9 × 10–10
8.0 × 10–10
1.3 × 10–9
1.4 × 10–9
1.5 × 10–9
2.2 × 10–9
2.3 × 10–9
2.1 × 10–10
3.3 × 10–10
3.4 × 10–10
3.6 × 10–10
5.8 × 10–10
6.0 × 10–10
2.0 × 10–9
2.7 × 10–9
2.8 × 10–9
1.2 × 10–9
2.7 × 10–9
3.0 × 10–9

6.6 × 10–10
6.1 × 10–10
9.7 × 10–10
1.0 × 10–9
1.2 × 10–9
1.7 × 10–9
1.8 × 10–9
1.6 × 10–10
2.4 × 10–10
2.5 × 10–10
2.8 × 10–10
4.3 × 10–10
4.5 × 10–10
1.6 × 10–9
2.1 × 10–9
2.2 × 10–9
8.2 × 10–10
1.9 × 10–9
2.2 × 10–9

4.4 × 10–10
6.4 × 10–10e(g)Age 1–2 a

3.4 × 10–10
2.9 × 10–10
4.9 × 10–10
5.2 × 10–10
5.9 × 10–10
8.8 × 10–10
9.2 × 10–10
7.7 × 10–11
1.2 × 10–10
1.2 × 10–10
1.4 × 10–10
2.2 × 10–10
2.3 × 10–10
8.0 × 10–10
1.1 × 10–9
1.2 × 10–9
3.8 × 10–10
1.1 × 10–9
1.3 × 10–9

2.1 × 10–10
3.2 × 10–10

e(g)

2–7 a

2.2 × 10–10
1.8 × 10–10
3.2 × 10–10
3.4 × 10–10
3.6 × 10–10
5.8 × 10–10
6.0 × 10–10
4.8 × 10–11
7.7 × 10–11
8.1 × 10–11
8.2 × 10–11
1.4 × 10–10
1.5 × 10–10
5.0 × 10–10
7.5 × 10–10
7.8 × 10–10
2.4 × 10–10
7.7 × 10–10
8.7 × 10–10

1.3 × 10–10
2.1 × 10–10

e(g)7–12 a

1.4 × 10–10
1.0 × 10–10
2.2 × 10–10
2.3 × 10–10
2.1 × 10–10
3.8 × 10–10
4.0 × 10–10
2.8 × 10–11
5.1 × 10–11
5.4 × 10–11
4.6 × 10–11
9.2 × 10–11
9.7 × 10–11
2.9 × 10–10
5.0 × 10–10
5.2 × 10–10
1.3 × 10–10
6.4 × 10–10
7.3 × 10–10

7.6 × 10–11
1.4 × 10–10

e(g)12–17 a1.2 × 10–10
8.2 × 10–11
1.8 × 10–10
1.9 × 10–10
1.7 × 10–10
3.1 × 10–10
3.2 × 10–10
2.3 × 10–11
4.2 × 10–11
4.4 × 10–11
3.7 × 10–11
7.4 × 10–11
7.9 × 10–11
2.4 × 10–10
4.0 × 10–10
4.2 × 10–10
1.1 × 10–10
5.2 × 10–10
6.0 × 10–10

6.2 × 10–11
1.1 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

333

12.1 d

3.10 h1.20 h

74.0 d

2.41 × 102 a

11.9 d19.1 hIr‑190m

Ir‑190mʹ

Ir‑192

Ir‑192m

Ir‑193m

Ir‑194

Physicalhalf-life

Ir‑190Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 af1 for
g>1a
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)
6.2 × 10–9
1.1 × 10–8
1.1 × 10–8
4.2 × 10–10
6.0 × 10–10
6.2 × 10–10
3.2 × 10–11
5.7 × 10–11
5.5 × 10–11
1.5 × 10–8
2.3 × 10–8
2.8 × 10–8
2.7 × 10–8
2.3 × 10–8
9.2 × 10–8
1.2 × 10–9
4.8 × 10–9
5.4 × 10–9
2.9 × 10–9
5.3 × 10–9
5.5 × 10–9

4.7 × 10–9
8.6 × 10–9
9.4 × 10–9
3.4 × 10–10
4.7 × 10–10
4.8 × 10–10
2.4 × 10–11
4.2 × 10–11
4.5 × 10–11
1.1 × 10–8
1.8 × 10–8
2.2 × 10–8
2.3 × 10–8
2.1 × 10–8
9.1 × 10–8
8.4 × 10–10
3.5 × 10–9
4.0 × 10–9
1.9 × 10–9
3.5 × 10–9
3.7 × 10–9e(g)Age 1–2 a

2.4 × 10–9
4.4 × 10–9
4.8 × 10–9
1.7 × 10–10
2.4 × 10–10
2.5 × 10–10
1.2 × 10–11
2.0 × 10–11
2.2 × 10–11
5.7 × 10–9
1.1 × 10–8
1.3 × 10–8
1.4 × 10–8
1.3 × 10–8
6.5 × 10–8
3.7 × 10–10
2.1 × 10–9
2.4 × 10–9
8.1 × 10–10
1.6 × 10–9
1.7 × 10–9

e(g)

2–7 a

1.5 × 10–9
3.1 × 10–9
3.5 × 10–9
1.0 × 10–10
1.5 × 10–10
1.6 × 10–10
7.2 × 10–12
1.4 × 10–11
1.6 × 10–11
3.3 × 10–9
7.6 × 10–9
9.5 × 10–9
8.2 × 10–9
8.4 × 10–9
4.5 × 10–8
2.2 × 10–10
1.5 × 10–9
1.8 × 10–9
4.9 × 10–10
1.0 × 10–9
1.1 × 10–9e(g)7–12 a9.1 × 10–10
2.7 × 10–9
3.0 × 10–9
6.0 × 10–11
9.9 × 10–11
1.0 × 10–10
4.3 × 10–12
1.2 × 10–11
1.3 × 10–11
2.1 × 10–9
6.4 × 10–9
8.1 × 10–9
5.4 × 10–9
6.6 × 10–9
4.0 × 10–8
1.2 × 10–10
1.4 × 10–9
1.6 × 10–9
2.5 × 10–10
6.3 × 10–10
6.7 × 10–10

e(g)12–17 a7.7 × 10–10
2.1 × 10–9
2.4 × 10–9
4.9 × 10–11
7.9 × 10–11
8.3 × 10–11
3.6 × 10–12
9.3 × 10–12
1.0 × 10–11
1.8 × 10–9
5.2 × 10–9
6.6 × 10–9
4.8 × 10–9
5.8 × 10–9
3.9 × 10–8
1.0 × 10–10
1.1 × 10–9
1.3 × 10–9
2.1 × 10–10
5.2 × 10–10
5.6 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

334

3.80 hIr‑195m

Pt‑186
Pt‑188Pt‑189Pt‑191
Pt‑193
Pt‑193m
Pt‑195m
Pt‑197
Pt‑197m
Pt‑199Pt‑2002.00 h10.2 d10.9 h2.80 d50.0 a4.33 d
4.02 d18.3 h
1.57 h
0.513 h12.5 h

2.50 hIr‑195

Platinum

171 dPhysicalhalf-life

Ir‑194m

Radionuclidea

F
F
F
F
F
F
F
F
F
F
F

F
M
S
F
M
S
F
M
S

Type

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020
0.020

f1

Age ≤ 1 a

3.4 × 10–8
3.9 × 10–8
5.0 × 10–8
2.9 × 10–10
5.4 × 10–10
5.7 × 10–10
6.9 × 10–10
1.2 × 10–9
1.3 × 10–9

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010
0.010

e(g)

3.0 × 10–10
3.6 × 10–9
3.8 × 10–10
1.1 × 10–9
2.2 × 10–10
1.6 × 10–9
2.2 × 10–9
1.1 × 10–9
2.8 × 10–10
1.3 × 10–10
2.6 × 10–9

f1 forg>1a2.4 × 10–10
2.7 × 10–9
2.9 × 10–10
7.9 × 10–10
1.6 × 10–10
1.0 × 10–9
1.5 × 10–9
7.3 × 10–10
1.8 × 10–10
8.3 × 10–11
1.7 × 10–9

2.7 × 10–8
3.2 × 10–8
4.2 × 10–8
1.9 × 10–10
3.6 × 10–10
3.8 × 10–10
4.8 × 10–10
8.6 × 10–10
9.0 × 10–10e(g)Age 1–2 a

1.2 × 10–10
1.3 × 10–9
1.4 × 10–10
3.7 × 10–10
7.2 × 10–11
4.5 × 10–10
6.4 × 10–10
3.1 × 10–10
7.9 × 10–11
3.6 × 10–11
7.2 × 10–10

1.4 × 10–8
1.9 × 10–8
2.6 × 10–8
8.1 × 10–11
1.7 × 10–10
1.8 × 10–10
2.1 × 10–10
4.2 × 10–10
4.4 × 10–10

e(g)

2–7 a

7.2 × 10–11
8.4 × 10–10
8.4 × 10–11
2.3 × 10–10
4.3 × 10–11
2.7 × 10–10
3.9 × 10–10
1.9 × 10–10
4.9 × 10–11
2.3 × 10–11
5.1 × 10–10

9.5 × 10–9
1.3 × 10–8
1.8 × 10–8
5.1 × 10–11
1.1 × 10–10
1.2 × 10–10
1.3 × 10–10
2.7 × 10–10
2.9 × 10–10

e(g)7–12 a4.1 × 10–11
5.0 × 10–10
4.7 × 10–11
1.3 × 10–10
2.5 × 10–11
1.4 × 10–10
2.1 × 10–10
1.0 × 10–10
2.8 × 10–11
1.4 × 10–11
2.6 × 10–10

6.2 × 10–9
1.1 × 10–8
1.5 × 10–8
2.9 × 10–11
8.1 × 10–11
8.7 × 10–11
7.2 × 10–11
1.9 × 10–10
2.0 × 10–10

e(g)12–17 a3.3 × 10–11
4.2 × 10–10
3.8 × 10–11
1.1 × 10–10
2.1 × 10–11
1.2 × 10–10
1.8 × 10–10
8.5 × 10–11
2.4 × 10–11
1.2 × 10–11
2.2 × 10–10

5.4 × 10–9
9.0 × 10–9
1.3 × 10–8
2.4 × 10–11
6.7 × 10–11
7.1 × 10–11
6.0 × 10–11
1.6 × 10–10
1.7 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)335

17.6 h

1.65 d183 d2.69 d2.30 d

3.14 d0.807 hAu‑194

Au‑195

Au‑198

Au‑198m

Au‑199Au‑200Physicalhalf-life

Au‑193

Gold

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200
0.200

f1

Age ≤ 1 a

3.7 × 10–10
7.5 × 10–10
7.9 × 10–10
1.2 × 10–9
1.7 × 10–9
1.7 × 10–9
7.2 × 10–10
5.2 × 10–9
8.1 × 10–9
2.4 × 10–9
5.0 × 10–9
5.4 × 10–9
3.3 × 10–9
8.7 × 10–9
9.5 × 10–9
1.1 × 10–9
3.4 × 10–9
3.8 × 10–9
1.9 × 10–10
3.2 × 10–10
3.4 × 10–10

e(g)
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1 forg>1a2.8 × 10–10
5.6 × 10–10
5.9 × 10–10
9.6 × 10–10
1.4 × 10–9
1.4 × 10–9
5.3 × 10–10
4.1 × 10–9
6.6 × 10–9
1.7 × 10–9
4.1 × 10–9
4.4 × 10–9
2.4 × 10–9
6.5 × 10–9
7.1 × 10–9
7.9 × 10–10
2.5 × 10–9
2.8 × 10–9
1.2 × 10–10
2.1 × 10–10
2.1 × 10–10e(g)Age 1–2 a

1.3 × 10–10
2.8 × 10–10
3.0 × 10–10
4.9 × 10–10
7.1 × 10–10
7.3 × 10–10
2.5 × 10–10
2.4 × 10–9
3.9 × 10–9
7.6 × 10–10
1.9 × 10–9
2.0 × 10–9
1.1 × 10–9
3.6 × 10–9
4.0 × 10–9
3.5 × 10–10
1.4 × 10–9
1.6 × 10–9
5.2 × 10–11
9.3 × 10–11
9.8 × 10–11

e(g)

2–7 a

7.9 × 10–11
1.9 × 10–10
2.0 × 10–10
3.0 × 10–10
4.6 × 10–10
4.7 × 10–10
1.5 × 10–10
1.6 × 10–9
2.6 × 10–9
4.7 × 10–10
1.3 × 10–9
1.4 × 10–9
6.9 × 10–10
2.6 × 10–9
2.9 × 10–9
2.2 × 10–10
1.0 × 10–9
1.2 × 10–9
3.2 × 10–11
6.0 × 10–11
6.3 × 10–11

e(g)7–12 a4.3 × 10–11
1.4 × 10–10
1.5 × 10–10
1.8 × 10–10
2.9 × 10–10
3.0 × 10–10
8.1 × 10–11
1.4 × 10–9
2.1 × 10–9
2.5 × 10–10
9.7 × 10–10
1.1 × 10–9
3.7 × 10–10
2.2 × 10–9
2.5 × 10–9
1.1 × 10–10
9.0 × 10–10
1.0 × 10–9
1.9 × 10–11
4.0 × 10–11
4.2 × 10–11

e(g)12–17 a3.6 × 10–11
1.1 × 10–10
1.2 × 10–10
1.4 × 10–10
2.3 × 10–10
2.4 × 10–10
6.6 × 10–11
1.1 × 10–9
1.7 × 10–9
2.1 × 10–10
7.8 × 10–10
8.6 × 10–10
3.2 × 10–10
1.8 × 10–9
2.0 × 10–9
9.8 × 10–11
7.1 × 10–10
7.9 × 10–10
1.6 × 10–11
3.3 × 10–11
3.5 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

336

Hg‑193(organic)
Hg‑193(inorganic)
Hg‑193m(organic)
Hg‑193m(inorganic)
Hg‑194(organic)
Hg‑194(inorganic)
Hg‑195(organic)

F
M
F

11.1 h

9.90 h

2.60 × 102 a2.60 × 102 a

F
M
F

F
M
F

3.50 h11.1 h

F

F
M
S
F
M
S

Type

3.50 h

0.440 hAu‑201

Mercury

18.7 hPhysicalhalf-life

Au‑200m

Radionuclidea

0.040
0.040
0.800

0.040
0.040
0.800

0.040
0.040
0.800

0.800

0.200
0.200
0.200
0.200
0.200
0.200

f1

Age ≤ 1 a

0.020
0.020
0.400

0.020
0.020
0.400

1.1 × 10–9
1.9 × 10–9
4.9 × 10–8
3.2 × 10–8
2.1 × 10–8
2.0 × 10–10

0.020
0.020
0.400

2.7 × 10–10
5.3 × 10–10
8.4 × 10–10

2.7 × 10–9
4.8 × 10–9
5.1 × 10–9
9.0 × 10–11
1.5 × 10–10
1.5 × 10–10

0.400

0.100
0.100
0.100
0.100
0.100
0.100

e(g)

2.2 × 10–10

f1 forg>1a2.9 × 10–8
1.9 × 10–8
1.8 × 10–10

8.5 × 10–10
1.4 × 10–9
3.7 × 10–8

2.0 × 10–10
3.8 × 10–10
7.6 × 10–10

1.8 × 10–10

2.1 × 10–9
3.7 × 10–9
3.9 × 10–9
5.7 × 10–11
9.6 × 10–11
1.0 × 10–10e(g)Age 1–2 a

2.0 × 10–8
1.3 × 10–8
8.5 × 10–11

4.1 × 10–10
7.2 × 10–10
2.4 × 10–8

8.9 × 10–11
1.9 × 10–10
3.7 × 10–10

8.2 × 10–11

1.0 × 10–9
1.9 × 10–9
2.0 × 10–9
2.5 × 10–11
4.3 × 10–11
4.5 × 10–11

e(g)

2–7 a

1.6 × 10–8
1.0 × 10–8
5.1 × 10–11

2.5 × 10–10
4.7 × 10–10
1.9 × 10–8

5.5 × 10–11
1.3 × 10–10
2.2 × 10–10

5.0 × 10–11

6.4 × 10–10
1.2 × 10–9
1.3 × 10–9
1.6 × 10–11
2.9 × 10–11
3.0 × 10–11

e(g)7–12 a

1.4 × 10–8
8.9 × 10–9
2.8 × 10–11

1.4 × 10–10
3.2 × 10–10
1.5 × 10–8

3.1 × 10–11
9.2 × 10–11
1.3 × 10–10

2.9 × 10–11

3.6 × 10–10
8.4 × 10–10
8.9 × 10–10
1.0 × 10–11
2.0 × 10–11
2.1 × 10–11

e(g)12–17 a1.3 × 10–8
8.3 × 10–9
2.3 × 10–11

1.1 × 10–10
2.6 × 10–10
1.4 × 10–8

2.6 × 10–11
7.5 × 10–11
1.0 × 10–10

2.4 × 10–11

2.9 × 10–10
6.8 × 10–10
7.2 × 10–10
8.7 × 10–12
1.7 × 10–11
1.7 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

337

Hg‑195(inorganic)
Hg‑195m(organic)
Hg‑195m(inorganic)
Hg‑197(organic)
Hg‑197(inorganic)
Hg‑197m(organic)
Hg‑197m(inorganic)
Hg‑199m(organic)
Hg‑199m(inorganic)
Hg‑203(organic)
Hg‑203(inorganic)

Radionuclidea

F
M
F

F
M
F

2.67 d23.8 hFM46.6 d46.6 dF
M
F

0.710 h0.710 h23.8 h

2.67 d

F
M
F

F
M
F

Type

1.73 d1.73 d

9.90 hPhysicalhalf-life

0.040
0.040

0.040
0.040
0.800

0.040
0.040
0.800

0.040
0.040
0.800

0.040
0.040
0.800

0.040
0.040
0.800

f1

Age ≤ 1 af1 for
g>1a
0.020
0.020
0.400
0.020
0.020
0.400
0.020
0.020
0.400
0.020
0.020
0.400
0.020
0.020
0.400
0.020
0.020

e(g)
2.7 × 10–10
5.3 × 10–10
1.1 × 10–9
1.6 × 10–9
3.7 × 10–9
4.7 × 10–10
6.8 × 10–10
1.7 × 10–9
9.3 × 10–10
1.4 × 10–9
3.5 × 10–9
1.4 × 10–10
1.4 × 10–10
2.5 × 10–10
5.7 × 10–9
4.2 × 10–9
1.0 × 10–8

2.9 × 10–9
7.9 × 10–9

9.6 × 10–11
1.7 × 10–10
3.7 × 10–9

9.3 × 10–10
2.5 × 10–9
9.6 × 10–11

4.7 × 10–10
1.2 × 10–9
7.8 × 10–10

1.1 × 10–9
2.6 × 10–9
4.0 × 10–10

2.0 × 10–10
3.9 × 10–10
9.7 × 10–10e(g)Age 1–2 a

1.4 × 10–9
4.7 × 10–9

4.2 × 10–11
7.9 × 10–11
1.7 × 10–9

4.0 × 10–10
1.1 × 10–9
4.2 × 10–11

2.1 × 10–10
6.6 × 10–10
3.4 × 10–10

5.1 × 10–10
1.4 × 10–9
1.8 × 10–10

9.5 × 10–11
2.0 × 10–10
4.4 × 10–10

e(g)

2–7 a

9.0 × 10–10
3.4 × 10–9

2.7 × 10–11
5.4 × 10–11
1.1 × 10–9

2.5 × 10–10
8.2 × 10–10
2.7 × 10–11

1.3 × 10–10
4.6 × 10–10
2.1 × 10–10

3.1 × 10–10
8.5 × 10–10
1.1 × 10–10

5.7 × 10–11
1.3 × 10–10
2.7 × 10–10

e(g)7–12 a5.5 × 10–10
3.0 × 10–9

1.7 × 10–11
3.8 × 10–11
6.6 × 10–10

1.3 × 10–10
6.7 × 10–10
1.7 × 10–11

6.8 × 10–11
3.8 × 10–10
1.1 × 10–10

1.7 × 10–10
6.7 × 10–10
5.8 × 10–11

3.1 × 10–11
9.0 × 10–11
1.4 × 10–10

e(g)12–17 a4.6 × 10–10
2.4 × 10–9

1.5 × 10–11
3.2 × 10–11
5.6 × 10–10

1.1 × 10–10
5.3 × 10–10
1.5 × 10–11

5.6 × 10–11
3.0 × 10–10
9.6 × 10–11

1.4 × 10–10
5.3 × 10–10
4.7 × 10–11

2.5 × 10–11
7.3 × 10–11
1.2 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

338

0.263 h2.40 h

Pb‑1980.550 h0.546 h1.16 h2.84 h5.30 h
1.87 h
7.42 h1.09 d
3.04 d12.2 d3.78 aPhysicalhalf-life

Pb‑195m

Leadg

Tl‑194Tl‑194m
Tl‑195
Tl‑197
Tl‑198Tl‑198m
Tl‑199Tl‑200Tl‑201
Tl‑202
Tl‑204

ThalliumRadionuclidea

F
M
S
F
M
S

F
F
F
F
F
F
F
F
F
F
F

Type

0.600
0.200
0.020
0.600
0.200
0.020

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1

Age ≤ 1 a

1.3 × 10–10
2.0 × 10–10
2.1 × 10–10
3.4 × 10–10
5.0 × 10–10
5.4 × 10–10

3.6 × 10–11
1.7 × 10–10
1.3 × 10–10
1.3 × 10–10
4.7 × 10–10
3.2 × 10–10
1.7 × 10–10
1.0 × 10–9
4.5 × 10–10
1.5 × 10–9
5.0 × 10–9

e(g)

0.200
0.100
0.010
0.200
0.100
0.010

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

f1 forg>1a

1.0 × 10–10
1.5 × 10–10
1.5 × 10–10
2.9 × 10–10
4.0 × 10–10
4.2 × 10–10

3.0 × 10–11
1.2 × 10–10
1.0 × 10–10
9.7 × 10–11
4.0 × 10–10
2.5 × 10–10
1.3 × 10–10
8.7 × 10–10
3.3 × 10–10
1.2 × 10–9
3.3 × 10–9e(g)Age 1–2 a

4.9 × 10–11
7.1 × 10–11
7.4 × 10–11
1.5 × 10–10
2.1 × 10–10
2.2 × 10–10

1.5 × 10–11
6.1 × 10–11
5.3 × 10–11
4.7 × 10–11
2.1 × 10–10
1.2 × 10–10
6.4 × 10–11
4.6 × 10–10
1.5 × 10–10
5.9 × 10–10
1.5 × 10–9

e(g)

2–7 a

3.1 × 10–11
4.6 × 10–11
4.8 × 10–11
8.9 × 10–11
1.3 × 10–10
1.4 × 10–10

9.2 × 10–12
3.8 × 10–11
3.2 × 10–11
2.9 × 10–11
1.3 × 10–10
7.5 × 10–11
3.9 × 10–11
2.8 × 10–10
9.4 × 10–11
3.8 × 10–10
8.8 × 10–10

e(g)7–12 a1.9 × 10–11
3.1 × 10–11
3.2 × 10–11
5.2 × 10–11
8.3 × 10–11
8.7 × 10–11

5.5 × 10–12
2.3 × 10–11
1.9 × 10–11
1.7 × 10–11
7.5 × 10–11
4.5 × 10–11
2.3 × 10–11
1.6 × 10–10
5.4 × 10–11
2.3 × 10–10
4.7 × 10–10

e(g)12–17 a1.6 × 10–11
2.5 × 10–11
2.7 × 10–11
4.3 × 10–11
6.6 × 10–11
7.0 × 10–11

4.4 × 10–12
1.9 × 10–11
1.5 × 10–11
1.4 × 10–11
6.0 × 10–11
3.7 × 10–11
1.9 × 10–11
1.3 × 10–10
4.4 × 10–11
1.9 × 10–10
3.9 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

339

1.50 h21.5 h

9.40 h3.00 × 105 a

3.62 h2.17 d1.43 × 107 a

Pb‑200Pb‑201

Pb‑202

Pb‑202m

Pb‑203

Pb‑205

Physicalhalf-life

Pb‑199Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 af1 for
g>1a
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010

e(g)
1.9 × 10–10
2.8 × 10–10
2.9 × 10–10
1.1 × 10–9
2.2 × 10–9
2.4 × 10–9
4.8 × 10–10
8.0 × 10–10
8.8 × 10–10
1.9 × 10–8
1.2 × 10–8
2.8 × 10–8
4.7 × 10–10
6.9 × 10–10
7.3 × 10–10
7.2 × 10–10
1.3 × 10–9
1.5 × 10–9
1.1 × 10–9
1.1 × 10–9
2.9 × 10–9

1.6 × 10–10
2.2 × 10–10
2.3 × 10–10
9.3 × 10–10
1.7 × 10–9
1.8 × 10–9
4.1 × 10–10
6.4 × 10–10
6.7 × 10–10
1.3 × 10–8
8.9 × 10–9
2.8 × 10–8
4.0 × 10–10
5.6 × 10–10
5.8 × 10–10
5.8 × 10–10
1.0 × 10–9
1.1 × 10–9
6.9 × 10–10
7.7 × 10–10
2.7 × 10–9e(g)Age 1–2 a

8.2 × 10–11
1.1 × 10–10
1.2 × 10–10
4.6 × 10–10
8.6 × 10–10
9.2 × 10–10
2.0 × 10–10
3.3 × 10–10
3.5 × 10–10
8.9 × 10–9
6.2 × 10–9
2.0 × 10–8
2.1 × 10–10
2.9 × 10–10
3.0 × 10–10
2.8 × 10–10
5.4 × 10–10
5.8 × 10–10
4.0 × 10–10
4.3 × 10–10
1.7 × 10–9

e(g)

2–7 a

4.9 × 10–11
7.1 × 10–11
7.4 × 10–11
2.8 × 10–10
5.7 × 10–10
6.2 × 10–10
1.2 × 10–10
2.1 × 10–10
2.2 × 10–10
1.3 × 10–8
6.7 × 10–9
1.4 × 10–8
1.3 × 10–10
1.9 × 10–10
1.9 × 10–10
1.7 × 10–10
3.6 × 10–10
3.8 × 10–10
4.1 × 10–10
3.2 × 10–10
1.1 × 10–9e(g)7–12 a2.9 × 10–11
4.5 × 10–11
4.7 × 10–11
1.6 × 10–10
4.1 × 10–10
4.4 × 10–10
7.1 × 10–11
1.4 × 10–10
1.5 × 10–10
1.8 × 10–8
8.7 × 10–9
1.3 × 10–8
7.5 × 10–11
1.2 × 10–10
1.3 × 10–10
9.9 × 10–11
2.5 × 10–10
2.8 × 10–10
4.3 × 10–10
2.9 × 10–10
9.2 × 10–10

e(g)12–17 a2.3 × 10–11
3.6 × 10–11
3.7 × 10–11
1.4 × 10–10
3.3 × 10–10
3.5 × 10–10
6.0 × 10–11
1.1 × 10–10
1.2 × 10–10
1.1 × 10–8
6.3 × 10–9
1.2 × 10–8
6.2 × 10–11
9.5 × 10–11
1.0 × 10–10
8.5 × 10–11
2.0 × 10–10
2.2 × 10–10
3.3 × 10–10
2.5 × 10–10
8.5 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

340

22.3 a0.601 h10.6 h

0.447 hPb‑210Pb‑211

Pb‑212

Pb‑2140.606 h1.80 h

Bi‑200Bi‑201

Bismuth

3.25 hPhysicalhalf-life

Pb‑209Radionuclidea

F
M
F
M

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type

0.100
0.100
0.100
0.100

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

f1

Age ≤ 1 a

1.8 × 10–10
4.0 × 10–10
4.4 × 10–10
4.7 × 10–6
5.0 × 10–6
1.8 × 10–5
2.5 × 10–8
6.2 × 10–8
6.6 × 10–8
1.9 × 10–7
6.2 × 10–7
6.7 × 10–7
2.2 × 10–8
6.4 × 10–8
6.9 × 10–8

0.050
0.050
0.050
0.050

0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010

e(g)

1.9 × 10–10
2.5 × 10–10
4.0 × 10–10
5.5 × 10–10

f1 forg>1a

1.5 × 10–10
1.9 × 10–10
3.1 × 10–10
4.1 × 10–10

1.2 × 10–10
2.7 × 10–10
2.9 × 10–10
2.9 × 10–6
3.7 × 10–6
1.8 × 10–5
1.7 × 10–8
4.5 × 10–8
4.8 × 10–8
1.2 × 10–7
4.6 × 10–7
5.0 × 10–7
1.5 × 10–8
4.6 × 10–8
5.0 × 10–8e(g)Age 1–2 a

7.4 × 10–11
9.9 × 10–11
1.5 × 10–10
2.0 × 10–10

5.3 × 10–11
1.3 × 10–10
1.4 × 10–10
1.5 × 10–6
2.2 × 10–6
1.1 × 10–5
8.7 × 10–9
2.5 × 10–8
2.7 × 10–8
5.4 × 10–8
3.0 × 10–7
3.3 × 10–7
6.9 × 10–9
2.6 × 10–8
2.8 × 10–8

e(g)

2–7 a

4.5 × 10–11
6.3 × 10–11
9.3 × 10–11
1.3 × 10–10

3.4 × 10–11
9.2 × 10–11
9.9 × 10–11
1.4 × 10–6
1.5 × 10–6
7.2 × 10–6
6.1 × 10–9
1.9 × 10–8
2.0 × 10–8
3.5 × 10–8
2.2 × 10–7
2.5 × 10–7
4.8 × 10–9
1.9 × 10–8
2.1 × 10–8

e(g)7–12 a2.7 × 10–11
4.1 × 10–11
5.4 × 10–11
8.3 × 10–11

1.9 × 10–11
6.9 × 10–11
7.5 × 10–11
1.3 × 10–6
1.3 × 10–6
5.9 × 10–6
4.6 × 10–9
1.4 × 10–8
1.5 × 10–8
2.0 × 10–8
2.2 × 10–7
2.4 × 10–7
3.3 × 10–9
1.4 × 10–8
1.5 × 10–8

e(g)12–17 a2.2 × 10–11
3.3 × 10–11
4.4 × 10–11
6.6 × 10–11

1.7 × 10–11
5.6 × 10–11
6.1 × 10–11
9.0 × 10–7
1.1 × 10–6
5.6 × 10–6
3.9 × 10–9
1.1 × 10–8
1.2 × 10–8
1.8 × 10–8
1.7 × 10–7
1.9 × 10–7
2.8 × 10–9
1.4 × 10–8
1.5 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

341

1.67 h11.8 h15.3 d6.24 d38.0 a5.01 d3.00 × 106 a

1.01 h

0.761 h0.332 hBi‑203

Bi‑205

Bi‑206

Bi‑207

Bi‑210Bi‑210m

Bi‑212

Bi‑213

Bi‑214

Physicalhalf-life

Bi‑202

Radionuclidea

F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M
F
M

Type
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100
0.100

f1

Age ≤ 1 af1 for
g>1a
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050
0.050

e(g)
3.4 × 10–10
4.2 × 10–10
1.5 × 10–9
2.0 × 10–9
3.0 × 10–9
5.5 × 10–9
6.1 × 10–9
1.0 × 10–8
4.3 × 10–9
2.3 × 10–8
1.1 × 10–8
3.9 × 10–7
4.1 × 10–7
1.5 × 10–5
6.5 × 10–8
1.6 × 10–7
7.7 × 10–8
1.6 × 10–7
5.0 × 10–8
8.7 × 10–8

2.8 × 10–10
3.4 × 10–10
1.2 × 10–9
1.6 × 10–9
2.4 × 10–9
4.4 × 10–9
4.8 × 10–9
8.0 × 10–9
3.3 × 10–9
2.0 × 10–8
6.9 × 10–9
3.0 × 10–7
2.6 × 10–7
1.1 × 10–5
4.5 × 10–8
1.1 × 10–7
5.3 × 10–8
1.2 × 10–7
3.5 × 10–8
6.1 × 10–8e(g)Age 1–2 a

1.5 × 10–10
1.8 × 10–10
6.4 × 10–10
8.2 × 10–10
1.3 × 10–9
2.5 × 10–9
2.5 × 10–9
4.4 × 10–9
1.7 × 10–9
1.2 × 10–8
3.2 × 10–9
1.9 × 10–7
1.3 × 10–7
7.0 × 10–6
2.1 × 10–8
6.0 × 10–8
2.5 × 10–8
6.0 × 10–8
1.6 × 10–8
3.1 × 10–8

e(g)

2–7 a

9.0 × 10–11
1.1 × 10–10
4.0 × 10–10
5.3 × 10–10
8.0 × 10–10
1.6 × 10–9
1.6 × 10–9
2.9 × 10–9
1.0 × 10–9
8.2 × 10–9
2.1 × 10–9
1.3 × 10–7
8.3 × 10–8
4.8 × 10–6
1.5 × 10–8
4.4 × 10–8
1.7 × 10–8
4.4 × 10–8
1.1 × 10–8
2.2 × 10–8

e(g)7–12 a5.3 × 10–11
6.9 × 10–11
2.3 × 10–10
3.3 × 10–10
4.7 × 10–10
1.2 × 10–9
9.1 × 10–10
2.1 × 10–9
6.0 × 10–10
6.5 × 10–9
1.3 × 10–9
1.1 × 10–7
5.6 × 10–8
4.1 × 10–6
1.0 × 10–8
3.8 × 10–8
1.2 × 10–8
3.6 × 10–8
8.2 × 10–9
1.7 × 10–8

e(g)12–17 a4.3 × 10–11
5.5 × 10–11
1.9 × 10–10
2.6 × 10–10
3.8 × 10–10
9.3 × 10–10
7.4 × 10–10
1.7 × 10–9
4.9 × 10–10
5.6 × 10–9
1.1 × 10–9
9.3 × 10–8
4.6 × 10–8
3.4 × 10–6
9.1 × 10–9
3.1 × 10–8
1.0 × 10–8
3.0 × 10–8
7.1 × 10–9
1.4 × 10–8

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

342

1.80 h5.83 h138 d

Po‑205

Po‑207

Po‑2101.80 h7.21 hAt‑207

At‑211

Astatine

0.612 hPhysicalhalf-life

Po‑203

PoloniumRadionuclidea

F
M
F
M

F
M
S
F
M
S
F
M
S
F
M
S

Type

1.000
1.000
1.000
1.000

0.200
0.200
0.020
0.200
0.200
0.020
0.200
0.200
0.020
0.200
0.200
0.020

f1

Age ≤ 1 a

2.4 × 10–9
9.2 × 10–9
1.4 × 10–7
5.2 × 10–7

1.9 × 10–10
2.7 × 10–10
2.8 × 10–10
2.6 × 10–10
4.0 × 10–10
4.2 × 10–10
4.8 × 10–10
6.2 × 10–10
6.6 × 10–10
7.4 × 10–6
1.5 × 10–5
1.8 × 10–5

e(g)

1.000
1.000
1.000
1.000

0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010
0.100
0.100
0.010

f1 forg>1a

1.7 × 10–9
6.7 × 10–9
9.7 × 10–8
3.7 × 10–7

1.5 × 10–10
2.1 × 10–10
2.2 × 10–10
2.1 × 10–10
3.1 × 10–10
3.2 × 10–10
4.0 × 10–10
5.1 × 10–10
5.3 × 10–10
4.8 × 10–6
1.1 × 10–5
1.4 × 10–5e(g)Age 1–2 a

8.9 × 10–10
4.3 × 10–9
4.3 × 10–8
1.9 × 10–7

7.7 × 10–11
1.1 × 10–10
1.1 × 10–10
1.1 × 10–10
1.7 × 10–10
1.8 × 10–10
2.1 × 10–10
2.6 × 10–10
2.7 × 10–10
2.2 × 10–6
6.7 × 10–6
8.6 × 10–6

e(g)

2–7 a

5.9 × 10–10
3.1 × 10–9
2.8 × 10–8
1.4 × 10–7

4.7 × 10–11
6.7 × 10–11
7.0 × 10–11
6.6 × 10–11
1.1 × 10–10
1.2 × 10–10
1.3 × 10–10
1.6 × 10–10
1.7 × 10–10
1.3 × 10–6
4.6 × 10–6
5.9 × 10–6

e(g)7–12 a4.0 × 10–10
2.9 × 10–9
1.7 × 10–8
1.3 × 10–7

2.8 × 10–11
4.3 × 10–11
4.5 × 10–11
4.1 × 10–11
8.1 × 10–11
8.5 × 10–11
7.3 × 10–11
9.9 × 10–11
1.0 × 10–10
7.7 × 10–7
4.0 × 10–6
5.1 × 10–6

e(g)12–17 a3.3 × 10–10
2.3 × 10–9
1.6 × 10–8
1.1 × 10–7

2.3 × 10–11
3.5 × 10–11
3.6 × 10–11
3.3 × 10–11
6.5 × 10–11
6.9 × 10–11
5.8 × 10–11
7.8 × 10–11
8.2 × 10–11
6.1 × 10–7
3.3 × 10–6
4.3 × 10–6

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

343

11.4 d

3.66 d

14.8 d

1.60 × 103 a

0.703 hRa‑224

Ra‑225

Ra‑226

Ra‑2270.240 h0.363 hPhysicalhalf-life

Ra‑223Radiumh

Fr‑222
Fr‑223

FranciumRadionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
F

Type

0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020
0.600
0.200
0.020

1.000
1.000

f1

Age ≤ 1 a

3.0 × 10–6
2.8 × 10–5
3.2 × 10–5
1.5 × 10–6
1.1 × 10–5
1.2 × 10–5
4.0 × 10–6
2.4 × 10–5
2.8 × 10–5
2.6 × 10–6
1.5 × 10–5
3.4 × 10–5
1.5 × 10–9
8.0 × 10–10
1.0 × 10–9

9.1 × 10–8
1.1 × 10–8

e(g)

0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010
0.200
0.100
0.010

1.000
1.000

f1 forg>1a

1.0 × 10–6
2.1 × 10–5
2.4 × 10–5
6.0 × 10–7
8.2 × 10–6
9.2 × 10–6
1.2 × 10–6
1.8 × 10–5
2.2 × 10–5
9.4 × 10–7
1.1 × 10–5
2.9 × 10–5
1.2 × 10–9
6.7 × 10–10
8.5 × 10–10

6.3 × 10–8
7.3 × 10–9e(g)Age 1–2 a

4.9 × 10–7
1.3 × 10–5
1.5 × 10–5
2.9 × 10–7
5.3 × 10–6
5.9 × 10–6
5.6 × 10–7
1.1 × 10–5
1.4 × 10–5
5.5 × 10–7
7.0 × 10–6
1.9 × 10–5
7.8 × 10–10
4.4 × 10–10
4.4 × 10–10

3.0 × 10–8
3.2 × 10–9

e(g)

2–7 a

4.0 × 10–7
9.9 × 10–6
1.1 × 10–5
2.2 × 10–7
3.9 × 10–6
4.4 × 10–6
4.6 × 10–7
8.4 × 10–6
1.0 × 10–5
7.2 × 10–7
4.9 × 10–6
1.2 × 10–5
6.1 × 10–10
3.2 × 10–10
2.9 × 10–10

2.1 × 10–8
1.9 × 10–9e(g)7–12 a3.3 × 10–7
9.4 × 10–6
1.1 × 10–5
1.7 × 10–7
3.7 × 10–6
4.2 × 10–6
3.8 × 10–7
7.9 × 10–6
9.8 × 10–6
1.3 × 10–6
4.5 × 10–6
1.0 × 10–5
5.3 × 10–10
2.9 × 10–10
2.4 × 10–10

1.6 × 10–8
1.0 × 10–9e(g)12–17 a1.2 × 10–7
7.4 × 10–6
8.7 × 10–6
7.5 × 10–8
3.0 × 10–6
3.4 × 10–6
1.3 × 10–7
6.3 × 10–6
7.7 × 10–6
3.6 × 10–7
3.5 × 10–6
9.5 × 10–6
4.6 × 10–10
2.8 × 10–10
2.2 × 10–10

1.4 × 10–8
8.9 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

344

2.90 h

10.0 d

1.21 d21.8 a6.13 h

Ac‑225

Ac‑226

Ac‑227

Ac‑2285.75 aPhysicalhalf-life

Ac‑224

ActiniumRa‑228

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.600
0.200
0.020

f1

Age ≤ 1 a

1.7 × 10–5
1.5 × 10–5
4.9 × 10–5

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

0.200
0.100
0.010

e(g)

1.3 × 10–7
4.2 × 10–7
4.6 × 10–7
1.1 × 10–5
2.8 × 10–5
3.1 × 10–5
1.5 × 10–6
4.3 × 10–6
4.7 × 10–6
1.7 × 10–3
5.7 × 10–4
2.2 × 10–4
1.8 × 10–7
8.4 × 10–8
6.4 × 10–8

f1 forg>1a

8.9 × 10–8
3.2 × 10–7
3.5 × 10–7
7.7 × 10–6
2.1 × 10–5
2.3 × 10–5
1.1 × 10–6
3.2 × 10–6
3.5 × 10–6
1.6 × 10–3
5.5 × 10–4
2.0 × 10–4
1.6 × 10–7
7.3 × 10–8
5.3 × 10–8

5.7 × 10–6
1.0 × 10–5
4.8 × 10–5e(g)Age 1–2 a

4.7 × 10–8
2.0 × 10–7
2.2 × 10–7
4.0 × 10–6
1.3 × 10–5
1.5 × 10–5
4.0 × 10–7
2.1 × 10–6
2.3 × 10–6
1.0 × 10–3
3.9 × 10–4
1.3 × 10–4
9.7 × 10–8
4.7 × 10–8
3.3 × 10–8

3.1 × 10–6
6.3 × 10–6
3.2 × 10–5

e(g)

2–7 a

3.1 × 10–8
1.5 × 10–7
1.7 × 10–7
2.6 × 10–6
1.0 × 10–5
1.1 × 10–5
2.6 × 10–7
1.5 × 10–6
1.7 × 10–6
7.2 × 10–4
2.6 × 10–4
8.7 × 10–5
5.7 × 10–8
2.9 × 10–8
2.2 × 10–8

3.6 × 10–6
4.6 × 10–6
2.0 × 10–5

e(g)7–12 a

1.4 × 10–8
1.4 × 10–7
1.6 × 10–7
1.1 × 10–6
9.3 × 10–6
1.1 × 10–5
1.2 × 10–7
1.5 × 10–6
1.6 × 10–6
5.6 × 10–4
2.3 × 10–4
7.6 × 10–5
2.9 × 10–8
2.0 × 10–8
1.9 × 10–8

4.6 × 10–6
4.4 × 10–6
1.6 × 10–5

e(g)12–17 a1.1 × 10–8
1.1 × 10–7
1.3 × 10–7
8.8 × 10–7
7.4 × 10–6
8.5 × 10–6
9.6 × 10–8
1.2 × 10–6
1.3 × 10–6
5.5 × 10–4
2.2 × 10–4
7.2 × 10–5
2.5 × 10–8
1.7 × 10–8
1.6 × 10–8

9.0 × 10–7
2.6 × 10–6
1.6 × 10–5

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

345

0.515 h18.7 d

1.91 a7.34 × 103 a

7.70 × 104 a

1.06 d

1.40 × 1010 a

Th‑227

Th‑228

Th‑229Th‑230Th‑231

Th‑232

Physicalhalf-life

Th‑226

Thorium

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

1.4 × 10–7
3.0 × 10–7
3.1 × 10–7
8.4 × 10–6
3.2 × 10–5
3.9 × 10–5
1.8 × 10–4
1.3 × 10–4
1.6 × 10–4
5.4 × 10–4
2.3 × 10–4
2.1 × 10–4
2.1 × 10–4
7.7 × 10–5
4.0 × 10–5
1.1 × 10–9
2.2 × 10–9
2.4 × 10–9
2.3 × 10–4
8.3 × 10–5
5.4 × 10–5e(g)5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

1.0 × 10–7
2.1 × 10–7
2.2 × 10–7
5.2 × 10–6
2.5 × 10–5
3.0 × 10–5
1.5 × 10–4
1.1 × 10–4
1.3 × 10–4
5.1 × 10–4
2.1 × 10–4
1.9 × 10–4
2.0 × 10–4
7.4 × 10–5
3.5 × 10–5
7.2 × 10–10
1.6 × 10–9
1.7 × 10–9
2.2 × 10–4
8.1 × 10–5
5.0 × 10–5e(g)Age 1–2 a

4.8 × 10–8
1.1 × 10–7
1.2 × 10–7
2.6 × 10–6
1.6 × 10–5
1.9 × 10–5
8.3 × 10–5
6.8 × 10–5
8.2 × 10–5
3.6 × 10–4
1.6 × 10–4
1.3 × 10–4
1.4 × 10–4
5.5 × 10–5
2.4 × 10–5
2.6 × 10–10
8.0 × 10–10
7.6 × 10–10
1.6 × 10–4
6.3 × 10–5
3.7 × 10–5

e(g)

2–7 a

3.4 × 10–8
8.3 × 10–8
8.8 × 10–8
1.6 × 10–6
1.1 × 10–5
1.4 × 10–5
5.2 × 10–5
4.6 × 10–5
5.5 × 10–5
2.9 × 10–4
1.2 × 10–4
8.7 × 10–5
1.1 × 10–4
4.3 × 10–5
1.6 × 10–5
1.6 × 10–10
4.8 × 10–10
5.2 × 10–10
1.3 × 10–4
5.0 × 10–5
2.6 × 10–5

e(g)7–12 a2.5 × 10–8
7.0 × 10–8
7.5 × 10–8
1.0 × 10–6
1.1 × 10–5
1.3 × 10–5
3.6 × 10–5
3.9 × 10–5
4.7 × 10–5
2.4 × 10–4
1.1 × 10–4
7.6 × 10–5
9.9 × 10–5
4.2 × 10–5
1.5 × 10–5
9.2 × 10–11
3.8 × 10–10
4.1 × 10–10
1.2 × 10–4
4.7 × 10–5
2.5 × 10–5

e(g)12–17 a2.2 × 10–8
5.8 × 10–8
6.1 × 10–8
6.7 × 10–7
8.5 × 10–6
1.0 × 10–5
2.9 × 10–5
3.2 × 10–5
4.0 × 10–5
2.4 × 10–4
1.1 × 10–4
7.1 × 10–5
1.0 × 10–4
4.3 × 10–5
1.4 × 10–5
7.8 × 10–11
3.1 × 10–10
3.3 × 10–10
1.1 × 10–4
4.5 × 10–5
2.5 × 10–5

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

346

0.638 h22.0 h

17.4 d3.27 × 104 a

1.31 d

27.0 d6.70 hPa‑228

Pa‑230

Pa‑231

Pa‑232

Pa‑233

Pa‑23424.1 dPhysicalhalf-life

Pa‑227

Protactinium

Th‑234

Radionuclidea

M
S
M
S
M
S
M
S
M
S
M
S
M
S

F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005

f1

Age ≤ 1 a

4.0 × 10–8
3.9 × 10–8
4.1 × 10–8

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)3.6 × 10–7
3.8 × 10–7
2.6 × 10–7
2.9 × 10–7
2.4 × 10–6
2.9 × 10–6
2.2 × 10–4
7.4 × 10–5
1.9 × 10–8
1.0 × 10–8
1.5 × 10–8
1.7 × 10–8
2.8 × 10–9
2.9 × 10–9

f1 forg>1a2.6 × 10–7
2.8 × 10–7
2.1 × 10–7
2.4 × 10–7
1.8 × 10–6
2.2 × 10–6
2.3 × 10–4
6.9 × 10–5
1.8 × 10–8
8.7 × 10–9
1.1 × 10–8
1.3 × 10–8
2.0 × 10–9
2.1 × 10–9

2.5 × 10–8
2.9 × 10–8
3.1 × 10–8e(g)Age 1–2 a

1.4 × 10–7
1.5 × 10–7
1.3 × 10–7
1.5 × 10–7
1.1 × 10–6
1.4 × 10–6
1.9 × 10–4
5.2 × 10–5
1.4 × 10–8
5.9 × 10–9
6.5 × 10–9
7.5 × 10–9
1.0 × 10–9
1.1 × 10–9

1.1 × 10–8
1.5 × 10–8
1.7 × 10–8

e(g)

2–7 a

1.0 × 10–7
1.1 × 10–7
8.8 × 10–8
1.0 × 10–7
8.3 × 10–7
1.0 × 10–6
1.5 × 10–4
3.9 × 10–5
1.1 × 10–8
4.1 × 10–9
4.7 × 10–9
5.5 × 10–9
6.8 × 10–10
7.1 × 10–10

6.1 × 10–9
1.0 × 10–8
1.1 × 10–8

e(g)7–12 a9.0 × 10–8
8.1 × 10–8
7.7 × 10–8
9.1 × 10–8
7.6 × 10–7
9.6 × 10–7
1.5 × 10–4
3.6 × 10–5
1.0 × 10–8
3.7 × 10–9
4.1 × 10–9
4.9 × 10–9
4.7 × 10–10
5.0 × 10–10

3.5 × 10–9
7.9 × 10–9
9.1 × 10–9e(g)12–17 a7.4 × 10–8
8.0 × 10–8
6.4 × 10–8
7.5 × 10–8
6.1 × 10–7
7.6 × 10–7
1.4 × 10–4
3.4 × 10–5
1.0 × 10–8
3.5 × 10–9
3.3 × 10–9
3.9 × 10–9
3.8 × 10–10
4.0 × 10–10

2.5 × 10–9
6.6 × 10–9
7.7 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

347

20.8 d

4.20 d72.0 a1.58 × 105 a

2.44 × 105 a

7.04 × 108 a

2.34 × 107 a

U‑231

U‑232

U‑233

U‑234

U‑235

U‑236

Physicalhalf-life

U‑230

Uranium

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020

f1

Age ≤ 1 a

3.2 × 10–6
4.9 × 10–5
5.8 × 10–5
8.9 × 10–10
2.4 × 10–9
2.6 × 10–9
1.6 × 10–5
3.0 × 10–5
1.0 × 10–4
2.2 × 10–6
1.5 × 10–5
3.4 × 10–5
2.1 × 10–6
1.5 × 10–5
3.3 × 10–5
2.0 × 10–6
1.3 × 10–5
3.0 × 10–5
2.0 × 10–6
1.4 × 10–5
3.1 × 10–5

e(g)
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002

f1 forg>1a

1.5 × 10–6
3.7 × 10–5
4.4 × 10–5
6.2 × 10–10
1.7 × 10–9
1.9 × 10–9
1.0 × 10–5
2.4 × 10–5
9.7 × 10–5
1.4 × 10–6
1.1 × 10–5
3.0 × 10–5
1.4 × 10–6
1.1 × 10–5
2.9 × 10–5
1.3 × 10–6
1.0 × 10–5
2.6 × 10–5
1.3 × 10–6
1.0 × 10–5
2.7 × 10–5e(g)Age 1–2 a

7.2 × 10–7
2.4 × 10–5
2.8 × 10–5
3.1 × 10–10
9.4 × 10–10
9.0 × 10–10
6.9 × 10–6
1.6 × 10–5
6.6 × 10–5
9.4 × 10–7
7.2 × 10–6
1.9 × 10–5
9.0 × 10–7
7.0 × 10–6
1.9 × 10–5
8.5 × 10–7
6.3 × 10–6
1.7 × 10–5
8.5 × 10–7
6.5 × 10–6
1.8 × 10–5

e(g)

2–7 a

5.4 × 10–7
1.8 × 10–5
2.1 × 10–5
1.4 × 10–10
5.5 × 10–10
6.1 × 10–10
6.8 × 10–6
1.1 × 10–5
4.3 × 10–5
8.4 × 10–7
4.9 × 10–6
1.2 × 10–5
8.0 × 10–7
4.8 × 10–6
1.2 × 10–5
7.5 × 10–7
4.3 × 10–6
1.1 × 10–5
7.5 × 10–7
4.5 × 10–6
1.1 × 10–5

e(g)7–12 a4.1 × 10–7
1.7 × 10–5
2.0 × 10–5
1.0 × 10–10
4.6 × 10–10
4.9 × 10–10
7.5 × 10–6
1.0 × 10–5
3.8 × 10–5
8.6 × 10–7
4.3 × 10–6
1.1 × 10–5
8.2 × 10–7
4.2 × 10–6
1.0 × 10–5
7.7 × 10–7
3.7 × 10–6
9.2 × 10–6
7.8 × 10–7
3.9 × 10–6
9.5 × 10–6

e(g)12–17 a3.8 × 10–7
1.3 × 10–5
1.6 × 10–5
6.2 × 10–11
3.8 × 10–10
4.0 × 10–10
4.0 × 10–6
7.8 × 10–6
3.7 × 10–5
5.8 × 10–7
3.6 × 10–6
9.6 × 10–6
5.6 × 10–7
3.5 × 10–6
9.4 × 10–6
5.2 × 10–7
3.1 × 10–6
8.5 × 10–6
5.3 × 10–7
3.2 × 10–6
8.7 × 10–6

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

348

4.47 × 109 a

0.392 h14.1 h

U‑238

U‑239

U‑240

0.245 h0.603 hNp‑232

Np‑233

Neptunium

6.75 dPhysicalhalf-life

U‑237Radionuclidea

F
M
S
F
M
S

F
M
S
F
M
S
F
M
S
F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005

0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020
0.040
0.040
0.020

f1

Age ≤ 1 a

1.8 × 10–9
7.8 × 10–9
8.7 × 10–9
1.9 × 10–6
1.2 × 10–5
2.9 × 10–5
1.0 × 10–10
1.8 × 10–10
1.9 × 10–10
2.4 × 10–9
4.6 × 10–9
4.9 × 10–9

5.0 × 10–04
5.0 × 10–04
5.0 × 10–04
5.0 × 10–04
5.0 × 10–04
5.0 × 10–04

0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002
0.020
0.020
0.002

e(g)

2.0 × 10–10
8.9 × 10–11
1.2 × 10–10
1.1 × 10–11
1.5 × 10–11
1.5 × 10–11

f1 forg>1a

1.9 × 10–10
8.1 × 10–11
9.7 × 10–11
8.7 × 10–12
1.1 × 10–11
1.2 × 10–11

1.5 × 10–9
5.7 × 10–9
6.4 × 10–9
1.3 × 10–6
9.4 × 10–6
2.5 × 10–5
6.6 × 10–11
1.2 × 10–10
1.2 × 10–10
1.6 × 10–9
3.1 × 10–9
3.3 × 10–9e(g)Age 1–2 a

1.2 × 10–10
5.5 × 10–11
5.8 × 10–11
4.2 × 10–12
5.5 × 10–12
5.7 × 10–12

6.6 × 10–10
3.3 × 10–9
3.7 × 10–9
8.2 × 10–7
5.9 × 10–6
1.6 × 10–5
2.9 × 10–11
5.6 × 10–11
5.9 × 10–11
7.1 × 10–10
1.7 × 10–9
1.6 × 10–9

e(g)

2–7 a

1.1 × 10–10
4.5 × 10–11
3.9 × 10–11
2.5 × 10–12
3.3 × 10–12
3.4 × 10–12

4.2 × 10–10
2.4 × 10–9
2.7 × 10–9
7.3 × 10–7
4.0 × 10–6
1.0 × 10–5
1.9 × 10–11
3.8 × 10–11
4.0 × 10–11
4.5 × 10–10
1.1 × 10–9
1.1 × 10–9e(g)7–12 a1.1 × 10–10
4.7 × 10–11
2.5 × 10–11
1.4 × 10–12
2.1 × 10–12
2.1 × 10–12

1.9 × 10–10
2.1 × 10–9
2.4 × 10–9
7.4 × 10–7
3.4 × 10–6
8.7 × 10–6
1.2 × 10–11
2.7 × 10–11
2.9 × 10–11
2.3 × 10–10
6.5 × 10–10
7.0 × 10–10

e(g)12–17 a1.2 × 10–10
5.0 × 10–11
2.4 × 10–11
1.1 × 10–12
1.6 × 10–12
1.7 × 10–12

1.8 × 10–10
1.7 × 10–9
1.9 × 10–9
5.0 × 10–7
2.9 × 10–6
8.0 × 10–6
1.0 × 10–11
2.2 × 10–11
2.4 × 10–11
2.0 × 10–10
5.3 × 10–10
5.8 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

349

4.40 d1.08 a1.15 × 105 a

22.5 h2.14 × 106 a

2.12 d2.36 d

Np‑235

Np‑236

Np‑236m

Np‑237

Np‑238

Np‑239Physicalhalf-life

Np‑234

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 af1 forg>1a
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)2.9 × 10–9
3.8 × 10–9
3.9 × 10–9
4.2 × 10–9
2.3 × 10–9
2.6 × 10–9
8.9 × 10–6
3.0 × 10–6
1.6 × 10–6
2.8 × 10–8
1.6 × 10–8
1.6 × 10–8
9.8 × 10–5
4.4 × 10–5
3.7 × 10–5
9.0 × 10–9
7.3 × 10–9
8.1 × 10–9
2.6 × 10–9
5.9 × 10–9
5.6 × 10–9

2.2 × 10–9
3.0 × 10–9
3.1 × 10–9
3.5 × 10–9
1.9 × 10–9
2.2 × 10–9
9.1 × 10–6
3.1 × 10–6
1.6 × 10–6
2.6 × 10–8
1.4 × 10–8
1.3 × 10–8
9.3 × 10–5
4.0 × 10–5
3.2 × 10–5
7.9 × 10–9
5.8 × 10–9
6.2 × 10–9
1.4 × 10–9
4.2 × 10–9
4.0 × 10–9e(g)Age 1–2 a

1.1 × 10–9
1.6 × 10–9
1.6 × 10–9
1.9 × 10–9
1.1 × 10–9
1.3 × 10–9
7.2 × 10–6
2.7 × 10–6
1.3 × 10–6
1.5 × 10–8
8.9 × 10–9
8.5 × 10–9
6.0 × 10–5
2.8 × 10–5
2.1 × 10–5
4.8 × 10–9
3.4 × 10–9
3.2 × 10–9
6.3 × 10–10
2.0 × 10–9
2.2 × 10–9

e(g)

2–7 a

7.2 × 10–10
1.0 × 10–9
1.0 × 10–9
1.1 × 10–9
6.8 × 10–10
8.3 × 10–10
7.5 × 10–6
2.7 × 10–6
1.0 × 10–6
1.1 × 10–8
6.2 × 10–9
5.7 × 10–9
5.0 × 10–5
2.2 × 10–5
1.4 × 10–5
3.7 × 10–9
2.5 × 10–9
2.1 × 10–9
3.8 × 10–10
1.4 × 10–9
1.6 × 10–9e(g)7–12 a4.3 × 10–10
6.5 × 10–10
6.8 × 10–10
7.5 × 10–10
5.1 × 10–10
6.3 × 10–10
7.9 × 10–6
3.1 × 10–6
1.0 × 10–6
8.9 × 10–9
5.6 × 10–9
4.8 × 10–9
4.7 × 10–5
2.2 × 10–5
1.3 × 10–5
3.3 × 10–9
2.2 × 10–9
1.7 × 10–9
2.1 × 10–10
1.2 × 10–9
1.3 × 10–9e(g)12–17 a3.5 × 10–10
5.3 × 10–10
5.5 × 10–10
6.3 × 10–10
4.2 × 10–10
5.2 × 10–10
8.0 × 10–6
3.2 × 10–6
1.0 × 10–6
9.0 × 10–9
5.3 × 10–9
4.2 × 10–9
5.0 × 10–5
2.3 × 10–5
1.2 × 10–5
3.5 × 10–9
2.1 × 10–9
1.5 × 10–9
1.7 × 10–10
9.3 × 10–10
1.0 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

350

8.80 h

0.422 h2.85 a45.3 d87.7 aPu‑235

Pu‑236m

Pu‑237

Pu‑2381.08 hPhysicalhalf-life

Pu‑234

Plutonium

Np‑240Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4

0.005
0.005
0.005

f1

Age ≤ 1 a

3.6 × 10–10
6.3 × 10–10
6.5 × 10–10

5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4e(g)3.0 × 10–8
7.8 × 10–8
8.7 × 10–8
1.0 × 10–11
1.3 × 10–11
1.3 × 10–11
1.0 × 10–4
4.8 × 10–5
3.6 × 10–5
2.2 × 10–9
1.9 × 10–9
2.0 × 10–9
2.0 × 10–4
7.8 × 10–5
4.5 × 10–5

f1 forg>1a2.0 × 10–8
5.9 × 10–8
6.6 × 10–8
7.9 × 10–12
1.0 × 10–11
1.0 × 10–11
9.5 × 10–5
4.3 × 10–5
3.1 × 10–5
1.6 × 10–9
1.4 × 10–9
1.5 × 10–9
1.9 × 10–4
7.4 × 10–5
4.0 × 10–5

2.6 × 10–10
4.4 × 10–10
4.6 × 10–10e(g)Age 1–2 a

9.8 × 10–9
3.7 × 10–8
4.2 × 10–8
3.9 × 10–12
5.0 × 10–12
5.1 × 10–12
6.1 × 10–5
2.9 × 10–5
2.0 × 10–5
7.9 × 10–10
8.2 × 10–10
8.8 × 10–10
1.4 × 10–4
5.6 × 10–5
2.7 × 10–5

1.2 × 10–10
2.2 × 10–10
2.3 × 10–10

e(g)

2–7 a

5.7 × 10–9
2.8 × 10–8
3.1 × 10–8
2.2 × 10–12
2.9 × 10–12
3.0 × 10–12
4.4 × 10–5
2.1 × 10–5
1.4 × 10–5
4.8 × 10–10
5.4 × 10–10
5.9 × 10–10
1.1 × 10–4
4.4 × 10–5
1.9 × 10–5

7.7 × 10–11
1.4 × 10–10
1.5 × 10–10

e(g)7–12 a3.6 × 10–9
2.6 × 10–8
3.0 × 10–8
1.3 × 10–12
1.9 × 10–12
1.9 × 10–12
3.7 × 10–5
1.9 × 10–5
1.2 × 10–5
2.9 × 10–10
4.3 × 10–10
4.8 × 10–10
1.0 × 10–4
4.3 × 10–5
1.7 × 10–5

4.7 × 10–11
1.0 × 10–10
1.1 × 10–10

e(g)12–17 a3.0 × 10–9
2.1 × 10–8
2.4 × 10–8
1.0 × 10–12
1.4 × 10–12
1.5 × 10–12
4.0 × 10–5
2.0 × 10–5
1.0 × 10–5
2.6 × 10–10
3.5 × 10–10
3.9 × 10–10
1.1 × 10–4
4.6 × 10–5
1.6 × 10–5

4.0 × 10–11
8.5 × 10–11
9.0 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

351

2.41 × 104 a

6.54 × 103 a

14.4 a3.76 × 105 a4.95 h8.26 × 107 a

10.5 hPu‑240Pu‑241

Pu‑242

Pu‑243

Pu‑244Pu‑245

Physicalhalf-life

Pu‑239Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4
0.005
0.005
1.0 × 10–4

f1

Age ≤ 1 a

2.1 × 10–4
8.0 × 10–5
4.3 × 10–5
2.1 × 10–4
8.0 × 10–5
4.3 × 10–5
2.8 × 10–6
9.1 × 10–7
2.2 × 10–7
2.0 × 10–4
7.6 × 10–5
4.0 × 10–5
2.7 × 10–10
5.6 × 10–10
6.0 × 10–10
2.0 × 10–4
7.4 × 10–5
3.9 × 10–5
1.8 × 10–9
3.6 × 10–9
3.8 × 10–9e(g)5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5
5.0 × 10–4
5.0 × 10–4
1.0 × 10–5

f1 forg>1a2.0 × 10–4
7.7 × 10–5
3.9 × 10–5
2.0 × 10–4
7.7 × 10–5
3.9 × 10–5
2.9 × 10–6
9.7 × 10–7
2.3 × 10–7
1.9 × 10–4
7.3 × 10–5
3.6 × 10–5
1.9 × 10–10
3.9 × 10–10
4.1 × 10–10
1.9 × 10–4
7.2 × 10–5
3.5 × 10–5
1.3 × 10–9
2.5 × 10–9
2.6 × 10–9e(g)Age 1–2 a

1.5 × 10–4
6.0 × 10–5
2.7 × 10–5
1.5 × 10–4
6.0 × 10–5
2.7 × 10–5
2.6 × 10–6
9.2 × 10–7
2.0 × 10–7
1.4 × 10–4
5.7 × 10–5
2.5 × 10–5
8.8 × 10–11
1.9 × 10–10
2.0 × 10–10
1.4 × 10–4
5.6 × 10–5
2.4 × 10–5
5.6 × 10–10
1.2 × 10–9
1.3 × 10–9

e(g)

2–7 a

1.2 × 10–4
4.8 × 10–5
1.9 × 10–5
1.2 × 10–4
4.8 × 10–5
1.9 × 10–5
2.4 × 10–6
8.3 × 10–7
1.7 × 10–7
1.2 × 10–4
4.5 × 10–5
1.7 × 10–5
5.7 × 10–11
1.3 × 10–10
1.4 × 10–10
1.2 × 10–4
4.5 × 10–5
1.7 × 10–5
3.5 × 10–10
8.0 × 10–10
8.5 × 10–10

e(g)7–12 a1.1 × 10–4
4.7 × 10–5
1.7 × 10–5
1.1 × 10–4
4.7 × 10–5
1.7 × 10–5
2.2 × 10–6
8.6 × 10–7
1.7 × 10–7
1.1 × 10–4
4.5 × 10–5
1.6 × 10–5
3.5 × 10–11
8.7 × 10–11
9.2 × 10–11
1.1 × 10–4
4.4 × 10–5
1.5 × 10–5
1.9 × 10–10
5.0 × 10–10
5.4 × 10–10

e(g)12–17 a1.2 × 10–4
5.0 × 10–5
1.6 × 10–5
1.2 × 10–4
5.0 × 10–5
1.6 × 10–5
2.3 × 10–6
9.0 × 10–7
1.7 × 10–7
1.1 × 10–4
4.8 × 10–5
1.5 × 10–5
3.2 × 10–11
8.3 × 10–11
8.6 × 10–11
1.1 × 10–4
4.7 × 10–5
1.5 × 10–5
1.6 × 10–10
4.0 × 10–10
4.3 × 10–10

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

352

1.22 h

1.63 h11.9 h2.12 d

4.32 × 102 a

Am‑238

Am‑239Am‑240Am‑241

10.9 dPhysicalhalf-life

Am‑237

AmericiumPu‑246

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
1.0 × 10–4

f1

Age ≤ 1 a

2.0 × 10–8
3.5 × 10–8
3.8 × 10–8

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
1.0 × 10–5e(g)9.8 × 10–11
1.7 × 10–10
1.7 × 10–10
4.1 × 10–10
3.1 × 10–10
2.7 × 10–10
8.1 × 10–10
1.5 × 10–9
1.6 × 10–9
2.0 × 10–9
2.9 × 10–9
3.0 × 10–9
1.8 × 10–4
7.3 × 10–5
4.6 × 10–5

f1 forg>1a

7.3 × 10–11
1.2 × 10–10
1.3 × 10–10
3.8 × 10–10
2.6 × 10–10
2.2 × 10–10
5.8 × 10–10
1.1 × 10–9
1.1 × 10–9
1.7 × 10–9
2.2 × 10–9
2.3 × 10–9
1.8 × 10–4
6.9 × 10–5
4.0 × 10–5

1.4 × 10–8
2.6 × 10–8
2.8 × 10–8e(g)Age 1–2 a

3.5 × 10–11
6.2 × 10–11
6.5 × 10–11
2.5 × 10–10
1.3 × 10–10
1.3 × 10–10
2.6 × 10–10
5.6 × 10–10
5.9 × 10–10
8.8 × 10–10
1.2 × 10–9
1.2 × 10–9
1.2 × 10–4
5.1 × 10–5
2.7 × 10–5

7.0 × 10–9
1.5 × 10–8
1.6 × 10–8

e(g)

2–7 a

2.2 × 10–11
4.1 × 10–11
4.3 × 10–11
2.0 × 10–10
9.6 × 10–11
8.2 × 10–11
1.6 × 10–10
3.7 × 10–10
4.0 × 10–10
5.7 × 10–10
7.7 × 10–10
7.8 × 10–10
1.0 × 10–4
4.0 × 10–5
1.9 × 10–5

4.4 × 10–9
1.1 × 10–8
1.2 × 10–8

e(g)7–12 a1.3 × 10–11
3.0 × 10–11
3.2 × 10–11
1.8 × 10–10
8.8 × 10–11
6.1 × 10–11
9.1 × 10–11
2.7 × 10–10
2.5 × 10–10
3.6 × 10–10
5.3 × 10–10
5.3 × 10–10
9.2 × 10–5
4.0 × 10–5
1.7 × 10–5

2.8 × 10–9
9.1 × 10–9
1.0 × 10–8

e(g)12–17 a1.1 × 10–11
2.5 × 10–11
2.6 × 10–11
1.9 × 10–10
9.0 × 10–11
5.4 × 10–11
7.6 × 10–11
2.2 × 10–10
2.4 × 10–10
2.3 × 10–10
4.3 × 10–10
4.3 × 10–10
9.6 × 10–5
4.2 × 10–5
1.6 × 10–5

2.5 × 10–9
7.4 × 10–9
8.0 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

353

16.0 h1.52 × 102 a

7.38 × 103 a

10.1 h

0.433 h2.05 h

0.650 hAm‑242m

Am‑243

Am‑244

Am‑244m

Am‑245

Am‑246

Physicalhalf-life

Am‑242

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 af1 forg>1a
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)9.2 × 10–8
7.6 × 10–8
8.0 × 10–8
1.6 × 10–4
5.2 × 10–5
2.5 × 10–5
1.8 × 10–4
7.2 × 10–5
4.4 × 10–5
1.0 × 10–8
6.0 × 10–9
6.1 × 10–9
4.6 × 10–10
3.3 × 10–10
3.0 × 10–10
2.1 × 10–10
3.9 × 10–10
4.1 × 10–10
3.0 × 10–10
5.0 × 10–10
5.3 × 10–10

7.1 × 10–8
5.9 × 10–8
6.2 × 10–8
1.5 × 10–4
5.3 × 10–5
2.4 × 10–5
1.7 × 10–4
6.8 × 10–5
3.9 × 10–5
9.2 × 10–9
5.0 × 10–9
4.8 × 10–9
4.0 × 10–10
2.1 × 10–10
2.2 × 10–10
1.4 × 10–10
2.6 × 10–10
2.8 × 10–10
2.0 × 10–10
3.4 × 10–10
3.6 × 10–10e(g)Age 1–2 a

3.5 × 10–8
3.6 × 10–8
3.9 × 10–8
1.1 × 10–4
4.1 × 10–5
1.7 × 10–5
1.2 × 10–4
5.0 × 10–5
2.6 × 10–5
5.6 × 10–9
3.2 × 10–9
2.4 × 10–9
2.4 × 10–10
1.3 × 10–10
1.2 × 10–10
6.2 × 10–11
1.3 × 10–10
1.3 × 10–10
9.3 × 10–11
1.6 × 10–10
1.7 × 10–10

e(g)

2–7 a

2.1 × 10–8
2.4 × 10–8
2.7 × 10–8
9.4 × 10–5
3.4 × 10–5
1.2 × 10–5
1.0 × 10–4
4.0 × 10–5
1.8 × 10–5
4.1 × 10–9
2.2 × 10–9
1.6 × 10–9
1.8 × 10–10
9.2 × 10–11
8.1 × 10–11
4.0 × 10–11
8.7 × 10–11
9.2 × 10–11
6.1 × 10–11
1.1 × 10–10
1.2 × 10–10

e(g)7–12 a

1.4 × 10–8
2.1 × 10–8
2.4 × 10–8
8.8 × 10–5
3.5 × 10–5
1.1 × 10–5
9.1 × 10–5
4.0 × 10–5
1.6 × 10–5
3.5 × 10–9
2.0 × 10–9
1.4 × 10–9
1.5 × 10–10
8.3 × 10–11
5.5 × 10–11
2.4 × 10–11
6.4 × 10–11
6.8 × 10–11
3.8 × 10–11
7.9 × 10–11
8.3 × 10–11

e(g)12–17 a1.1 × 10–8
1.7 × 10–8
2.0 × 10–8
9.2 × 10–5
3.7 × 10–5
1.1 × 10–5
9.6 × 10–5
4.1 × 10–5
1.5 × 10–5
3.7 × 10–9
2.0 × 10–9
1.2 × 10–9
1.6 × 10–10
8.4 × 10–11
5.7 × 10–11
2.1 × 10–11
5.3 × 10–11
5.6 × 10–11
3.3 × 10–11
6.6 × 10–11
6.9 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

354

2.40 h

27.0 d32.8 d163 d28.5 aCm‑240Cm‑241

Cm‑242

Cm‑2430.417 hPhysicalhalf-life

Cm‑238CuriumAm‑246m

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

F
M
S

Type

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005

f1

Age ≤ 1 a

1.3 × 10–10
1.9 × 10–10
2.0 × 10–10

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)7.7 × 10–9
2.1 × 10–8
2.2 × 10–8
8.3 × 10–6
1.2 × 10–5
1.3 × 10–5
1.1 × 10–7
1.3 × 10–7
1.4 × 10–7
2.7 × 10–5
2.2 × 10–5
2.4 × 10–5
1.6 × 10–4
6.7 × 10–5
4.6 × 10–5

f1 forg>1a5.4 × 10–9
1.5 × 10–8
1.6 × 10–8
6.3 × 10–6
9.1 × 10–6
9.9 × 10–6
8.9 × 10–8
1.0 × 10–7
1.1 × 10–7
2.1 × 10–5
1.8 × 10–5
1.9 × 10–5
1.5 × 10–4
6.1 × 10–5
4.0 × 10–5

8.9 × 10–11
1.3 × 10–10
1.4 × 10–10e(g)Age 1–2 a

2.6 × 10–9
7.9 × 10–9
8.6 × 10–9
3.2 × 10–6
5.8 × 10–6
6.4 × 10–6
4.9 × 10–8
6.6 × 10–8
6.9 × 10–8
1.0 × 10–5
1.1 × 10–5
1.2 × 10–5
9.5 × 10–5
4.2 × 10–5
2.6 × 10–5

4.2 × 10–11
6.1 × 10–11
6.4 × 10–11

e(g)

2–7 a

1.8 × 10–9
5.9 × 10–9
6.4 × 10–9
2.0 × 10–6
4.2 × 10–6
4.6 × 10–6
3.5 × 10–8
4.8 × 10–8
4.9 × 10–8
6.1 × 10–6
7.3 × 10–6
8.2 × 10–6
7.3 × 10–5
3.1 × 10–5
1.8 × 10–5

2.6 × 10–11
4.0 × 10–11
4.1 × 10–11

e(g)7–12 a9.2 × 10–10
5.6 × 10–9
6.1 × 10–9
1.5 × 10–6
3.8 × 10–6
4.3 × 10–6
2.8 × 10–8
4.4 × 10–8
4.5 × 10–8
4.0 × 10–6
6.4 × 10–6
7.3 × 10–6
6.5 × 10–5
3.0 × 10–5
1.6 × 10–5

1.6 × 10–11
2.6 × 10–11
2.7 × 10–11

e(g)12–17 a7.8 × 10–10
4.5 × 10–9
4.9 × 10–9
1.3 × 10–6
3.2 × 10–6
3.5 × 10–6
2.7 × 10–8
3.7 × 10–8
3.7 × 10–8
3.3 × 10–6
5.2 × 10–6
5.9 × 10– 6
6.9 × 10–5
3.1 × 10–5
1.5 × 10–5

1.4 × 10–11
2.2 × 10–11
2.3 × 10–11

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

355

18.1 a8.50 × 103 a4.73 × 103 a

1.56 × 107 a

3.39 × 105 a

1.07 h

6.90 × 103 a

Cm‑245

Cm‑246

Cm‑247

Cm‑248

Cm‑249Cm‑250Physicalhalf-life

Cm‑244

Radionuclidea

F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S
F
M
S

Type
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 af1 forg>1a
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

e(g)1.5 × 10–4
6.2 × 10–5
4.4 × 10–5
1.9 × 10–4
7.3 × 10–5
4.5 × 10–5
1.9 × 10–4
7.3 × 10–5
4.6 × 10–5
1.7 × 10–4
6.7 × 10–5
4.1 × 10–5
6.8 × 10–4
2.5 × 10–4
1.4 × 10–4
1.8 × 10–10
2.4 × 10–10
2.4 × 10–10
3.9 × 10–3
1.4 × 10–3
7.2 × 10–4

1.3 × 10–4
5.7 × 10–5
3.8 × 10–5
1.8 × 10–4
6.9 × 10–5
4.0 × 10–5
1.8 × 10–4
6.9 × 10–5
4.0 × 10–5
1.6 × 10–4
6.3 × 10–5
3.6 × 10–5
6.5 × 10–4
2.4 × 10–4
1.2 × 10–4
9.8 × 10–11
1.6 × 10–10
1.6 × 10–10
3.7 × 10–3
1.3 × 10–3
6.5 × 10–4

e(g)Age 1–2 a

8.3 × 10–5
3.7 × 10–5
2.5 × 10–5
1.2 × 10–4
5.1 × 10–5
2.7 × 10–5
1.2 × 10–4
5.1 × 10–5
2.7 × 10–5
1.1 × 10–4
4.7 × 10–5
2.4 × 10–5
4.5 × 10–4
1.8 × 10–4
8.2 × 10–5
5.9 × 10–11
8.2 × 10–11
7.8 × 10–11
2.6 × 10–3
9.9 × 10–4
4.4 × 10–4

e(g)

2–7 a

6.1 × 10–5
2.7 × 10–5
1.7 × 10–5
1.0 × 10–4
4.1 × 10–5
1.9 × 10–5
1.0 × 10–4
4.1 × 10–5
1.9 × 10–5
9.4 × 10–5
3.7 × 10–5
1.7 × 10–5
3.7 × 10–4
1.4 × 10–4
5.6 × 10–5
4.6 × 10–11
5.8 × 10–11
5.3 × 10–11
2.1 × 10–3
7.9 × 10–4
3.0 × 10–4

e(g)7–12 a5.3 × 10–5
2.6 × 10–5
1.5 × 10–5
9.4 × 10–5
4.1 × 10–5
1.7 × 10–5
9.4 × 10–5
4.1 × 10–5
1.7 × 10–5
8.6 × 10–5
3.7 × 10–5
1.5 × 10–5
3.4 × 10–4
1.4 × 10–4
5.0 × 10–5
4.0 × 10–11
3.7 × 10–11
3.9 × 10–11
2.0 × 10–3
7.9 × 10–4
2.7 × 10–4

e(g)12–17 a5.7 × 10–5
2.7 × 10–5
1.3 × 10–5
9.9 × 10–5
4.2 × 10–5
1.6 × 10–5
9.8 × 10–5
4.2 × 10–5
1.6 × 10–5
9.0 × 10–5
3.9 × 10–5
1.4 × 10–5
3.6 × 10–4
1.5 × 10–4
4.8 × 10–5
4.0 × 10–11
3.3 × 10–11
3.3 × 10–11
2.1 × 10–3
8.4 × 10–4
2.6 × 10–4

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

356

Es‑250Es‑251
Es‑253Einsteinium

Cf‑244
Cf‑246
Cf‑248
Cf‑249Cf‑250
Cf‑251
Cf‑252
Cf‑253
Cf‑254

Californium

Bk‑245
Bk‑246
Bk‑247
Bk‑249
Bk‑250Berkelium

Radionuclidea

2.10 h1.38 d20.5 d

0.323 h1.49 d334 d3.50 × 102 a
13.1 a8.98 × 102 a2.64 a17.8 d60.5 d

4.94 d1.83 d1.38 × 103 a
320 d3.22 hPhysicalhalf-life

M
M
M

M
M
M
M
M
M
M
M
M

M
M
M
M
M

Type

0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005
0.005

0.005
0.005
0.005
0.005
0.005

f1

Age ≤ 1 a

2.0 × 10–9
7.9 × 10–9
1.1 × 10–5

7.6 × 10–8
1.7 × 10–6
3.8 × 10–5
1.6 × 10–4
1.1 × 10–4
1.6 × 10–4
9.7 × 10–5
5.4 × 10–6
2.5 × 10–4

8.8 × 10–9
2.1 × 10–9
1.5 × 10–4
3.3 × 10–7
3.4 × 10–9e(g)5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

f1 forg>1a

1.8 × 10–9
6.0 × 10–9
8.0 × 10–6

5.4 × 10–8
1.3 × 10–6
3.2 × 10–5
1.5 × 10–4
9.8 × 10–5
1.5 × 10–4
8.7 × 10–5
4.2 × 10–6
1.9 × 10–4

6.6 × 10–9
1.7 × 10–9
1.5 × 10–4
3.3 × 10–7
3.1 × 10–9e(g)Age 1–2 a

1.2 × 10–9
3.9 × 10–9
5.1 × 10–6

2.8 × 10–8
8.3 × 10–7
2.1 × 10–5
1.1 × 10–4
6.6 × 10–5
1.1 × 10–4
5.6 × 10–5
2.6 × 10–6
1.1 × 10–4

4.0 × 10–9
9.3 × 10–10
1.1 × 10–4
2.4 × 10–7
2.0 × 10–9

e(g)

2–7 a

7.8 × 10–10
2.8 × 10–9
3.7 × 10–6

2.0 × 10–8
6.1 × 10–7
1.4 × 10–5
8.0 × 10–5
4.2 × 10–5
8.1 × 10–5
3.2 × 10–5
1.9 × 10–6
7.0 × 10–5

2.9 × 10–9
6.0 × 10–10
7.9 × 10–5
1.8 × 10–7
1.3 × 10–9e(g)7–12 a6.4 × 10–10
2.6 × 10–9
3.4 × 10–6

1.6 × 10–8
5.7 × 10–7
1.0 × 10–5
7.2 × 10–5
3.5 × 10–5
7.3 × 10–5
2.2 × 10–5
1.7 × 10–6
4.8 × 10–5

2.6 × 10–9
4.0 × 10–10
7.2 × 10–5
1.6 × 10–7
1.1 × 10–9e(g)12–17 a6.3 × 10–10
2.1 × 10–9
2.7 × 10–6

1.4 × 10–8
4.5 × 10–7
8.8 × 10–6
7.0 × 10–5
3.4 × 10–5
7.1 × 10–5
2.0 × 10–5
1.3 × 10–6
4.1 × 10–5

2.1 × 10–9
3.3 × 10–10
6.9 × 10–5
1.6 × 10–7
1.0 × 10–9

e(g)

>17 a

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

357

5.20 h
55.0 d22.7 h3.00 d3.24 h20.1 h101 d

276 d
1.64 dPhysicalhalf-life

M
M

M
M
M
M
M

M
M

Type

0.005
0.005

0.005
0.005
0.005
0.005
0.005

0.005
0.005

f1

Age ≤ 1 a

3.7 × 10–5
1.7 × 10–6

1.0 × 10–7
2.4 × 10–5

5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4
5.0 × 10–4

5.0 × 10–4
5.0 × 10–4

e(g)1.2 × 10–6
1.5 × 10–6
3.2 × 10–7
1.2 × 10–6
3.3 × 10–5

f1 forg>1a

8.2 × 10–8
1.9 × 10–5

9.0 × 10–7
1.2 × 10–6
2.3 × 10–7
7.3 × 10–7
2.6 × 10–5

3.1 × 10–5
1.3 × 10–6e(g)Age 1–2 a

5.1 × 10–8
1.2 × 10–5

5.8 × 10–7
7.3 × 10–7
1.3 × 10–7
4.7 × 10–7
1.6 × 10–5

2.0 × 10–5
8.4 × 10–7

e(g)

2–7 a

3.6 × 10–8
8.6 × 10–6

4.3 × 10–7
5.4 × 10–7
9.8 × 10–8
3.5 × 10–7
1.1 × 10–5

1.3 × 10–5
6.3 × 10–7

e(g)7–12 a3.1 × 10–8
7.3 × 10–6

4.0 × 10–7
5.0 × 10–7
7.6 × 10–8
3.4 × 10–7
8.8 × 10–6

1.0 × 10–5
5.9 × 10–7

e(g)12–17 a2.5 × 10–8
5.9 × 10–6

3.2 × 10–7
4.0 × 10–7
6.1 × 10–8
2.7 × 10–7
7.1 × 10–6

8.6 × 10–6
4.7 × 10–7

e(g)

>17 a

b

m and mʹ denote metastable states of the radionuclide. The metastable state mʹ is of higher energy than the metastable state m.
The f1 value for calcium for 1–15 year olds for Type F is 0.4.
c
The f1 value for iron for 1–15 year olds for Type F is 0.2.
d
The f1 value for cobalt for 1–15 year olds for Type F is 0.3.
e
The f1 value for strontium for 1–15 year olds for Type F is 0.4.
f
The f1 value for barium for 1–15 year olds for Type F is 0.3.
g
The f1 value for lead for 1–15 year olds for Type F is 0.4.
h
The f1 value for radium for 1–15 year olds for Type F is 0.3.
Note: Types F, M and S denote fast, moderate and slow absorption from the lung, respectively. f1: gut transfer factor; e(g): effective dose per unit
intake by age group.

a

Md‑257
Md‑258Mendelevium

Fm‑252
Fm‑253
Fm‑254
Fm‑255
Fm‑257

Fermium

Es‑254
Es‑254m

Radionuclidea

TABLE III.2E. MEMBERS OF THE PUBLIC: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) VIA
INHALATION (cont.)

TABLE III.2F. LUNG ABSORPTION TYPES USED TO CALCULATECOMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATIONFOR EXPOSURE DUE TO PARTICULATE AEROSOLS OR DUE TO GASESAND VAPOURS FOR MEMBERS OF THE PUBLIC (cont.)
Element

Absorption
type(s)a

ICRP Publication No. for details of biokinetic modeland absorption type(s)HydrogenF, Mb, S, G

Publications 56 [31], 67 [32] and 71 [33]Beryllium

M, S

Publication 30, Part 3 [34]

Carbonb

F, M , S, G

Publications 56 [31], 67 [32] and 71 [33]Fluorine

F, M, S

Publication 30, Part 2 [34]SodiumF

Publication 30, Part 2 [34]Magnesium

F, M

Publication 30, Part 3 [34]Aluminium

F, M

Publication 30, Part 3 [34]SiliconF, M, S

Publication 30, Part 3 [34]Phosphorus

F, M

Publication 30, Part 1 [34]Sulphurb

F, M , S, G

Publications 67 [32] and 71 [33]Chlorine

F, M

Publication 30, Part 2 [34]Potassium

F

Publication 30, Part 2 [34]Calcium

F, M, S

Publication 71 [33]ScandiumS

Publication 30, Part 3 [34]TitaniumF, M, S

Publication 30, Part 3 [34]

VanadiumF, M

Publication 30, Part 3 [34]ChromiumF, M, S

Publication 30, Part 2 [34]ManganeseF, M

Publication 30, Part 1 [34]IronF, Mb, S

Publications 69 [35] and 71 [33]bCobaltF, M , S

Publications 67 [32] and 71 [33]

Nickelb

F, M , S, G

Publications 67 [32] and 71 [33]CopperF, M, S

Publication 30, Part 2 [34]

Zinc

b

F, M , S

Publications 67 [32] and 71 [33]GalliumF, M

Publication 30, Part 3 [34]358TABLE III.2F. LUNG ABSORPTION TYPES USED TO CALCULATECOMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATIONFOR EXPOSURE DUE TO PARTICULATE AEROSOLS OR DUE TO GASESAND VAPOURS FOR MEMBERS OF THE PUBLIC (cont.)
Absorption
type(s)a

ICRP Publication No. for details of biokinetic modeland absorption type(s)F, M

Publication 30, Part 3 [34]M

Publication 30, Part 3 [34]Selenium

F , M, S

Publications 69 [35] and 71 [33]BromineF, M

Publication 30, Part 2 [34]

RubidiumF

Publication 30, Part 2 [34]Strontiumb

F, M , S

Publications 67 [32] and 71 [33]Yttrium

M, S

Publication 30, Part 2 [34]Zirconiumb

F, M , S

Publications 56 [31], 67 [32] and 71 [33]

NiobiumF, Mb, S

Publications 56 [31], 67 [32] and 71 [33]

Molybdenumb

F, M , S

Publications 67 [32] and 71 [33]Technetiumb

F, M , S

Publications 67 [32] and 71 [33]

Ruthenium

F, Mb, S, G

Publications 56 [31], 67 [32] and 71 [33]Rhodium

F, M, S

Publication 30, Part 2 [34]PalladiumF, M, S

Publication 30, Part 3 [34]Silverb

F, M , S

Publications 67 [32] and 71 [33]Cadmium

F, M, S

Publication 30, Part 2 [34]IndiumF, M

Publication 30, Part 2 [34]

Tin

F, M

Publication 30, Part 3 [34]AntimonyF, Mb, S

Publications 69 [35] and 71 [33]Telluriumb

Publications 67 [32] and 71 [33]IodineF , M, S, G

Publications 56 [31], 67 [32] and 71 [33]CaesiumFb, M, S

Publications 56 [31], 67 [32] and 71 [33]Bariumb

F, M , S

Publications 67 [32] and 71 [33]Lanthanum

F, M

Publication 30, Part 3 [34]Element
Germanium
Arsenicb

F, M , S, Gb

359

TABLE III.2F. LUNG ABSORPTION TYPES USED TO CALCULATECOMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATIONFOR EXPOSURE DUE TO PARTICULATE AEROSOLS OR DUE TO GASESAND VAPOURS FOR MEMBERS OF THE PUBLIC (cont.)
Element

Absorption
type(s)a

ICRP Publication No. for details of biokinetic modeland absorption type(s)CeriumF, Mb, S

Publications 56 [31], 67 [32] and 71 [33]Praseodymium

M, S

Publication 30, Part 3 [34]

Neodymium

M, S

Publication 30, Part 3 [34]Promethium

M, S

Publication 30, Part 3 [34]

Samarium

M

Publication 30, Part 3 [34]Europium

M

Publication 30, Part 3 [34]Gadolinium

F, M

Publication 30, Part 3 [34]Terbium

M

Publication 30, Part 3 [34]

Dysprosium

M

Publication 30, Part 3 [34]Holmium

M

Publication 30, Part 3 [34]ErbiumM

Publication 30, Part 3 [34]Thulium

M

Publication 30, Part 3 [34]Ytterbium

M, S

Publication 30, Part 3 [34]Lutetium

M, S

Publication 30, Part 3 [34]HafniumF, M

Publication 30, Part 3 [34]Tantalum

M, S

Publication 30, Part 3 [34]TungstenF

Publication 30, Part 3 [34]RheniumF, M

Publication 30, Part 2 [34]OsmiumF, M, S

Publication 30, Part 2 [34]Iridium

F, M, S

Publication 30, Part 2 [34]PlatinumF

Publication 30, Part 3 [34]Gold

F, M, S

Publication 30, Part 2 [34]Mercury

F, M, G

Publication 30, Part 2 [34]ThalliumF

Publication 30, Part 3 [34]360TABLE III.2F. LUNG ABSORPTION TYPES USED TO CALCULATECOMMITTED EFFECTIVE DOSE PER UNIT INTAKE VIA INHALATIONFOR EXPOSURE DUE TO PARTICULATE AEROSOLS OR DUE TO GASESAND VAPOURS FOR MEMBERS OF THE PUBLIC (cont.)
Element

Absorption
type(s)a

ICRP Publication No. for details of biokinetic modeland absorption type(s)LeadF, Mb, S, G

Publications 67 [32] and 71 [33]BismuthF, M

Publication 30, Part 2 [34]Poloniumb

F, M , S, G

Publications 67 [32] and 71 [33]Astatine

F, M

Publication 30, Part 3 [34]FranciumF

Publication 30, Part 3 [34]Radiumb

F, M , S

Publications 67 [32] and 71 [33]ActiniumF, M, S

Publication 30, Part 3 [34]Thorium

F, M, Sb

Protactinium

M, S

Publication 30, Part 3 [34]bF, M , S

Publications 69 [35] and 71 [33]Neptuniumb

F, M , S

Publications 67 [32] and 71 [33]Plutonium

F, Mb, S

Publications 67 [32] and 71 [33]Americiumb

F, M , S

Publications 67 [32] and 71 [33]CuriumF, Mb, S

Publication 71 [33]Berkelium

M

Publication 30, Part 4 [34]Californium

M

Publication 30, Part 4 [34]

Einsteinium

M

Publication 30, Part 4 [34]Fermium

M

Publication 30, Part 4 [34]Mendelevium

M

Publication 30, Part 4 [34]Uraniumab

Publications 69 [35] and 71 [33]For particulates: F: fast; M: moderate; S: slow; G: gases and vapours.
Recommended default absorption type for particulate aerosol when no specific information
is available (see ICRP Publication No. 71 [31]).

361

362
V
V
V
V

12.3 a12.3 a0.340 h0.340 h0.340 h5.73 × 103 a

5.73 × 103 a

5.73 × 103 a

87.4 dTritiated methane

Organicallybound tritium

Carbon‑11
vapourCarbon‑11
dioxideCarbon‑11monoxide

Carbon‑14 vapour

Carbon‑14
dioxideCarbon‑14monoxide

Carbondisulphide‑35

F

V

V

V

V

V

12.3 aElementalhydrogenV

Absorptiona

12.3 aPhysicalhalf-life

Tritiated water

Radionuclide

100

40

100

100

40

100

100

100

1

0.01

100

%
deposits

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

f1

1.000
1.000
1.000
1.000
1.000
1.000

6.4 × 10–11
6.4 × 10–15
6.4 × 10–13
1.1 × 10–10
2.8 × 10–11
1.8 × 10–11
1.0 × 10–11

1.000
0.800

6.9 × 10–9

1.000

9.1 × 10–12

1.9 × 10–11

1.000

1.000

e(g)

1.3 × 10–9

f1 forg>1a

Age ≤ 1 a

4.8 × 10–9

5.7 × 10–12

1.9 × 10–11

1.6 × 10–9

6.7 × 10–12

1.2 × 10–11

1.8 × 10–11

1.1 × 10–10

4.8 × 10–13

4.8 × 10–15

4.8 × 10–11e(g)Age ≤ 1 a

2.4 × 10–9

2.8 × 10–12

1.1 × 10–11

9.7 × 10–10

3.5 × 10–12

6.5 × 10–12

9.7 × 10–12

7.0 × 10–11

3.1 × 10–13

3.1 × 10–15

3.1 × 10–11

e(g)

2–7 a

1.4 × 10–9

1.7 × 10–12

8.9 × 10–12

7.9 × 10–10

2.2 × 10–12

4.1 × 10–12

6.1 × 10–12

5.5 × 10–11

2.3 × 10–13

2.3 × 10–15

2.3 × 10–11

e(g)7–12 a8.6 × 10–10

9.9 × 10–13

6.3 × 10–12

5.7 × 10–10

1.4 × 10–12

2.5 × 10–12

3.8 × 10–12

4.1 × 10–11

1.8 × 10–13

1.8 × 10–15

1.8 × 10–11

e(g)12–17 a7.0 × 10–10

8.0 × 10–13

6.2 × 10–12

5.8 × 10–10

1.2 × 10–12

2.2 × 10–12

3.2 × 10–12

4.1 × 10–11

1.8 × 10–13

1.8 × 10–15

1.8 × 10–11

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

363

100
100
100

c

c

c

96.0 a2.52 h2.27 d

0.863 h2.90 d39.3 dNickel‑63
carbonyl

Nickel‑65
carbonyl

Nickel‑66
carbonyl

Ruthenium‑94
tetroxide

Ruthenium‑97
tetroxide

Ruthenium‑103
tetroxide

F

F
100

100

100

100

c

7.50 × 104 a

Nickel‑59
carbonyl

F

100

c

1.50 dNickel‑57
carbonyl100c6.10 dNickel‑56
carbonyl%deposits
85

Absorptiona
F

87.4 dPhysicalhalf-life

Sulphur‑35
dioxideRadionuclide

0.100

0.100

0.100

1.000

1.000

1.000

1.000

1.000

1.000

1.000

f1
9.4 × 10–10

1.000
0.050
0.050
0.050

5.5 × 10–10
8.7 × 10–10
9.0 × 10–9

1.000

1.000

1.000

1.000

1.0 × 10–8

2.0 × 10–9

9.5 × 10–9

4.0 × 10–9

3.1 × 10–9

1.000

0.800

e(g)

6.8 × 10–9

f1 forg>1a

Age ≤ 1 a

6.2 × 10–9

6.2 × 10–10

3.5 × 10–10

7.1 × 10–9

1.4 × 10–9

8.0 × 10–9

3.3 × 10–9

2.3 × 10–9

5.2 × 10–9

6.6 × 10–10e(g)Age ≤ 1 a

3.3 × 10–9

3.4 × 10–10

1.8 × 10–10

4.0 × 10–9

8.1 × 10–10

4.8 × 10–9

2.0 × 10–9

1.4 × 10–9

3.2 × 10–9

3.4 × 10–10

e(g)

2–7 a

2.1 × 10–9

2.2 × 10–10

1.1 × 10–10

2.7 × 10–9

5.6 × 10–10

3.0 × 10–9

1.3 × 10–9

9.2 × 10–10

2.1 × 10–9

2.1 × 10–10

e(g)7–12 a1.3 × 10–9

1.4 × 10–10

7.0 × 10–11

1.8 × 10–9

4.0 × 10–10

2.2 × 10–9

9.1 × 10–10

6.5 × 10–10

1.4 × 10–9

1.3 × 10–10

e(g)12–17 a1.1 × 10–9

1.2 × 10–10

5.6 × 10–11

1.6 × 10–9

3.6 × 10–10

2.0 × 10–9

8.3 × 10–10

5.6 × 10–10

1.2 × 10–9

1.1 × 10–10

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

364
F
F

2.49 h

17.0 d154 d1.00 × 1013 a

120 d

58.0 d9.35 h109 dTellurium‑116
vapourTellurium‑121
vapourTellurium‑121m
vapourTellurium‑123
vapourTellurium‑123m
vapourTellurium‑125m
vapourTellurium‑127
vapourTellurium‑127m
vapour

F

F

F

F

F

F

F

1.01 aRuthenium‑106
tetroxideF

Absorptiona

4.44 hPhysicalhalf-life

Ruthenium‑105
tetroxide

Radionuclide

100

100

100

100

100

100

100

100

100

100

%
deposits

0.600

0.600

0.600

0.600

0.600

0.600

0.600

0.600

0.100

0.100

f1

0.300
0.300

6.1 × 10–10
5.3 × 10–8

3.5 × 10–8

0.300

0.300

3.0 × 10–9

1.5 × 10–8

0.300

5.9 × 10–10

0.300

0.300

1.6 × 10–7

2.5 × 10–8

0.050

1.6 × 10–9

0.300

0.050

e(g)

2.8 × 10–8

f1 forg>1a

Age ≤ 1 a

3.7 × 10–8

4.4 × 10–10

1.1 × 10–8

1.8 × 10–8

2.5 × 10–8

2.7 × 10–8

2.4 × 10–9

4.4 × 10–10

1.1 × 10–7

1.0 × 10–9e(g)Age ≤ 1 a

1.9 × 10–8

2.3 × 10–10

5.9 × 10–9

1.0 × 10–8

1.9 × 10–8

1.6 × 10–8

1.4 × 10–9

2.5 × 10–10

6.1 × 10–8

5.3 × 10–10

e(g)

2–7 a

1.0 × 10–8

1.4 × 10–10

3.2 × 10–9

5.7 × 10–9

1.5 × 10–8

9.8 × 10–9

9.6 × 10–10

1.6 × 10–10

3.7 × 10–8

3.2 × 10–10

e(g)7–12 a6.1 × 10–9

9.2 × 10–11

1.9 × 10–9

3.5 × 10–9

1.3 × 10–8

6.6 × 10–9

6.7 × 10–10

1.1 × 10–10

2.2 × 10–8

2.2 × 10–10

e(g)12–17 a4.6 × 10–9

7.7 × 10–11

1.5 × 10–9

2.9 × 10–9

1.2 × 10–8

5.5 × 10–9

5.1 × 10–10

8.7 × 10–11

1.8 × 10–8

1.8 × 10–10

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

365

1.16 h33.6 d

0.417 h1.25 d3.26 d

0.207 h0.923 h0.696 h1.35 h

0.883 hTellurium‑129m
vapourTellurium‑131
vapourTellurium‑131m
vapourTellurium‑132
vapourTellurium‑133
vapourTellurium‑133m
vapourTellurium‑134
vapourElemental
iodine‑120

Elemental
iodine‑120m

Physicalhalf-life

Tellurium‑129
vapourRadionuclide

V

V

F

F

F

F

F

F

F

F

Absorptiona

100

100

100

100

100

100

100

100

100

100

%
deposits

1.000

1.000

0.600

0.600

0.600

0.600

0.600

0.600

0.600

0.600

f1

f1 for
g>1a
0.300
0.300
0.300
0.300
0.300
0.300
0.300
0.300
1.000
1.000

e(g)
2.5 × 10–10
4.8 × 10–8
5.1 × 10–10
2.1 × 10–8
5.4 × 10–8
5.5 × 10–10
2.3 × 10–9
6.8 × 10–10
3.0 × 10–9
1.5 × 10–9

Age ≤ 1 a

1.2 × 10–9

2.4 × 10–9

5.5 × 10–10

2.0 × 10–9

4.7 × 10–10

4.5 × 10–8

1.9 × 10–8

4.5 × 10–10

3.2 × 10–8

1.7 × 10–10e(g)Age ≤ 1 a

6.4 × 10–10

1.3 × 10–9

3.0 × 10–10

1.1 × 10–9

2.5 × 10–10

2.4 × 10–8

1.1 × 10–8

2.6 × 10–10

1.6 × 10–8

9.4 × 10–11

e(g)

2–7 a

3.4 × 10–10

6.4 × 10–10

1.6 × 10–10

5.0 × 10–10

1.2 × 10–10

1.2 × 10–8

5.6 × 10–9

1.4 × 10–10

8.5 × 10–9

6.2 × 10–11

e(g)7–12 a2.3 × 10–10

4.3 × 10–10

1.1 × 10–10

3.3 × 10–10

8.1 × 10–11

7.6 × 10–9

3.7 × 10–9

9.5 × 10–11

5.1 × 10–9

4.3 × 10–11

e(g)12–17 a1.8 × 10–10

3.0 × 10–1

8.4 × 10–11

2.2 × 10–10

5.6 × 10–11

5.1 × 10–9

2.4 × 10–9

6.8 × 10–11

3.7 × 10–9

3.7 × 10–11

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

366
V
V

4.18 d60.1 d

13.0 d

0.416 h1.57 × 107 a

12.4 h8.04 d2.30 hElemental
iodine‑124

Elemental
iodine‑125

Elemental
iodine‑126

Elemental
iodine‑128

Elemental
iodine‑129

Elemental
iodine‑130

Elemental
iodine‑131

Elemental
iodine‑132

V

V

V

V

V

V

V

13.2 hElemental
iodine‑123

V

Absorptiona

2.12 hPhysicalhalf-life

Elemental
iodine‑121

Radionuclide

100

100

100

100

100

100

100

100

100

100

%
deposits

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

f1

1.000

4.2 × 10–10

2.8 × 10–9

1.000

1.9 × 10–7

1.000

1.000

4.7 × 10–8

1.7 × 10–7

1.000

1.1 × 10–7

1.000

1.000

2.1 × 10–9

1.9 × 10–8

1.000

5.7 × 10–10

1.000

1.000

e(g)

1.7 × 10–7

f1 forg>1a

Age ≤ 1 a

2.3 × 10–9

1.6 × 10–7

1.7 × 10–8

2.0 × 10–7

2.8 × 10–10

1.9 × 10–7

5.2 × 10–8

1.0 × 10–7

1.8 × 10–9

5.1 × 10–10e(g)Age ≤ 1 a

1.3 × 10–9

9.4 × 10–8

9.2 × 10–9

1.6 × 10–7

1.6 × 10–10

1.1 × 10–7

3.7 × 10–8

5.8 × 10–8

1.0 × 10–9

3.0 × 10–10

e(g)

2–7 a

6.4 × 10–10

4.8 × 10–8

4.3 × 10–9

1.7 × 10–7

1.0 × 10–10

6.2 × 10–8

2.8 × 10–8

2.8 × 10–8

4.7 × 10–10

1.7 × 10–10

e(g)7–12 a4.3 × 10–10

3.1 × 10–8

2.8 × 10–9

1.3 × 10–7

7.5 × 10–11

4.1 × 10–8

2.0 × 10–8

1.8 × 10–8

3.2 × 10–10

1.2 × 10–10

e(g)12–17 a3.1 × 10–10

2.0 × 10–8

1.9 × 10–9

9.6 × 10–8

6.5 × 10–11

2.6 × 10–8

1.4 × 10–8

1.2 × 10–8

2.1 × 10–10

8.6 × 10–11

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

367

V
V

0.876 h6.61 h

1.35 h

0.883 h2.12 h13.2 h

4.18 d60.1 d

13.0 d

0.416 h1.57 × 107 a

Elemental
iodine‑134

Elemental
iodine‑135

Methyl iodide‑120

Methyl iodide‑120m

Methyl iodide‑121

Methyl iodide‑123

Methyl iodide‑124

Methyl iodide‑125

Methyl iodide‑126

Methyl iodide‑128

Methyl iodide‑129

V

V

V

V

V

V

V

V

V

V

20.8 hElemental
iodine‑133

V

Absorptiona

1.39 hPhysicalhalf-life

Elemental
iodine‑132m

Radionuclide

70

70

70

70

70

70

70

70

70

100

100

100

100

%
deposits

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

f1

1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000
1.000

2.4 × 10–9
4.5 × 10–8
8.7 × 10–10
9.7 × 10–9
2.3 × 10–9
1.0 × 10–9
4.2 × 10–10
1.6 × 10–9
8.5 × 10–8
3.7 × 10–8
1.5 × 10–7
1.5 × 10–10

1.000

1.000

e(g)

1.3 × 10–7

f1 forg>1a

Age ≤ 1 a

1.5 × 10–7

1.2 × 10–10

1.5 × 10–7

4.0 × 10–8

8.0 × 10–8

1.4 × 10–9

3.8 × 10–10

8.7 × 10–10

1.9 × 10–9

8.5 × 10–9

6.9 × 10–10

4.1 × 10–8

2.1 × 10–9e(g)Age ≤ 1 a

1.2 × 10–7

6.3 × 10–11

9.0 × 10–8

2.9 × 10–8

4.5 × 10–8

7.7 × 10–10

2.2 × 10–10

4.6 × 10–10

1.0 × 10–9

4.5 × 10–9

3.9 × 10–10

2.1 × 10–8

1.1 × 10–9

e(g)

2–7 a

1.3 × 10–7

3.0 × 10–11

4.8 × 10–8

2.2 × 10–8

2.2 × 10–8

3.6 × 10–10

1.2 × 10–10

2.2 × 10–10

4.8 × 10–10

2.1 × 10–9

2.2 × 10–10

9.7 × 10–9

5.6 × 10–10

e(g)7–12 a9.9 × 10–8

1.9 × 10–11

3.2 × 10–8

1.6 × 10–8

1.4 × 10–8

2.4 × 10–10

8.3 × 10–11

1.5 × 10–10

3.1 × 10–10

1.4 × 10–9

1.6 × 10–10

6.3 × 10–9

3.8 × 10–10

e(g)12–17 a7.4 × 10–8

1.3 × 10–11

2.0 × 10–8

1.1 × 10–8

9.2 × 10–9

1.5 × 10–10

5.6 × 10–11

1.0 × 10–10

2.0 × 10–10

9.2 × 10–10

1.5 × 10–10

4.0 × 10–9

2.7 × 10–10

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

368
70
70
70

d

d

d

2.60 × 102 a9.90 h1.73 dMercury‑195
vapour

Mercury‑195m
vapour

Mercury‑193m
vapour

Mercury‑194
vapour3.50 hMercury‑193
vapour70

70

6.61 hMethyl iodide‑135

V

70

d

0.876 hMethyl iodide‑134V70

11.1 h20.8 hMethyl iodide‑133

V

70

70

1.39 hMethyl iodide‑132m

V

70

d

2.30 hMethyl iodide‑132

V

70

%
deposits

70

8.04 dMethyl iodide‑131

V

Absorptiona

V

12.4 hPhysicalhalf-life

Methyl iodide‑130

Radionuclide

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

1.000

f1

1.000
1.000
1.000
1.000
1.000
1.000

1.5 × 10–8
1.3 × 10–7
2.0 × 10–9
1.8 × 10–9
3.5 × 10–8
5.1 × 10–10
7.5 × 10–9

3.0 × 10–8

5.3 × 10–9

9.4 × 10–8

1.2 × 10–8

1.000

1.000

1.000

1.000

1.000

1.000

e(g)

4.2 × 10–9

f1 forg>1a

Age ≤ 1 a

2.5 × 10–8

4.3 × 10–9

8.3 × 10–8

9.4 × 10–9

3.4 × 10–9

6.7 × 10–9

4.3 × 10–10

3.2 × 10–8

1.6 × 10–9

1.8 × 10–9

1.3 × 10–7

1.3 × 10–8e(g)Age ≤ 1 a

1.6 × 10–8

2.8 × 10–9

6.2 × 10–8

6.1 × 10–9

2.2 × 10–9

3.5 × 10–9

2.3 × 10–10

1.7 × 10–8

8.3 × 10–10

9.5 × 10–10

7.4 × 10–8

7.2 × 10–9

e(g)

2–7 a

1.2 × 10–8

2.1 × 10–9

5.0 × 10–8

4.5 × 10–9

1.6 × 10–9

1.6 × 10–9

1.1 × 10–10

7.6 × 10–9

3.9 × 10–10

4.4 × 10–10

3.7 × 10–8

3.3 × 10–9e(g)7–12 a8.8 × 10–9

1.6 × 10–9

4.3 × 10–8

3.4 × 10–9

1.2 × 10–9

1.1 × 10–9

7.4 × 10–11

4.9 × 10–9

2.5 × 10–10

2.9 × 10–10

2.4 × 10–8

2.2 × 10–9e(g)12–17 a8.2 × 10–9

1.4 × 10–9

4.0 × 10–8

3.1 × 10–9

1.1 × 10–9

6.8 × 10–10

5.0 × 10–11

3.1 × 10–9

1.6 × 10–10

1.9 × 10–10

1.5 × 10–8

1.4 × 10–9

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

369

0.710 h46.6 dMercury‑199m
vapour

Mercury‑203
vapourdcb%deposits
70
70
70
70

Absorptiona
d

d

d

d

1.000

1.000

1.000

1.000

f1

3.0 × 10–8

6.5 × 10–10

2.1 × 10–8

1.6 × 10–8e(g)Age ≤ 1 a

1.000

1.000

1.000

1.000

f1 forg>1a2.3 × 10–8

5.3 × 10–10

1.7 × 10–8

1.3 × 10–8e(g)Age ≤ 1 a

1.5 × 10–8

3.4 × 10–10

1.1 × 10–8

8.4 × 10–9

e(g)

2–7 a

1.0 × 10–8

2.5 × 10–10

8.2 × 10–9

6.3 × 10–9e(g)7–12 a7.7 × 10–9

1.9 × 10–10

6.2 × 10–9

4.7 × 10–9e(g)12–17 a

F: fast; V: material is taken to be completely and instantaneously transferred to body fluids.
Applicable to both workers and adult members of the public.
Deposition: 30%:10%:20%:40% (extrathoracic:bronchial:bronchiolar:alveolar-interstitial; 0.1 d retention half-time (see Ref. [36]).
Deposition: 10%:20%:40% (bronchial:bronchiolar:alvelar-interstitial); 1.7 d retention half-time (see Ref. [36]).

23.8 hMercury‑197m
vapoura2.67 dPhysicalhalf-life

Mercury‑197
vapourRadionuclide

7.0 × 10–9

1.8 × 10–10

5.8 × 10–9

4.4 × 10–9

e(g)b

>17 a

TABLE III.2G. INHALATION: COMMITTED EFFECTIVE DOSE PER UNIT INTAKE e(g) (Sv/Bq) FOR SOLUBLE OR
REACTIVE GASES AND VAPOURS (cont.)

TABLE III.2H. EFFECTIVE DOSE RATE FOR EXPOSURE DUE TO INERTGASES FOR ADULTSa
Radionuclide

Physical half-life

Effective dose rate per unit integrated air concentration(Sv · d–1/Bq · m–3)a

Argon
Ar-37
Ar-39
Ar-41

35.0 d269 a1.83 h

4.1 × 10–15
1.1 × 10–11
5.3 × 10–9

0.192 h14.8 h
1.245 h1.46 d
2.10 × 105 a
1.83 h10.7 a4.48 h1.27 h2.84 h

4.5 × 10–9
1.6 × 10–9
3.9 × 10–9
9.7 × 10–10
2.1 × 10–11
2.1 × 10–13
2.2 × 10–11
5.9 × 10–10
3.4 × 10–9
8.4 × 10–9

0.667 h0.668 h20.1 h2.08 h
17.0 h36.4 d8.0 d11.9 d5.24 d
2.19 d9.10 h
0.255 h0.237 h1.5 × 10–9
7.5 × 10–9
1.9 × 10–10
2.4 × 10–9
9.3 × 10–10
9.7 × 10–10
8.1 × 10–11
3.2 × 10–11
1.2 × 10–10
1.1 × 10–10
9.6 × 10–10
1.6 × 10–9
4.7 × 10–9

Krypton
Kr-74
Kr-76
Kr-77
Kr-79
Kr-81
Kr-83m
Kr-85
Kr-85m
Kr-87
Kr-88
Xenon
Xe-120
Xe-121
Xe-122
Xe-123
Xe-125
Xe-127
Xe-129m
Xe-131m
Xe-133
Xe-133m
Xe-135
Xe-135m
Xe-138aApplicable to both workers and adult members of the public.

370

Schedule IV
CRITERIA FOR USE IN EMERGENCY PREPAREDNESSAND RESPONSE
IV.1. Table IV.1 gives generic criteria for doses received within a short period oftime for which protective actions and other response actions are expected to beundertaken under any circumstances to avoid or to minimize severe deterministic
effects.
IV.2. Table IV.2 gives guidance values for restricting exposure of emergency
workers.

371

TABLE IV.1. GENERIC CRITERIA FOR DOSES RECEIVED WITHIN ASHORT PERIOD OF TIME FOR WHICH PROTECTIVE ACTIONS AND
OTHER RESPONSE ACTIONS ARE EXPECTED TO BE UNDERTAKEN
UNDER ANY CIRCUMSTANCES TO AVOID OR TO MINIMIZE SEVERE
DETERMINISTIC EFFECTS
Acute external exposure (<10 h)
ADred marrowa

1 Gy

ADfetus

0.1 GyADtissueb

25 Gy at 0.5 cmcADskin10 Gy to 100 cm2

If the dose is projected:——Take precautionary urgent protective
actions immediately (even underdifficult conditions) to keep doses
below the generic criteria——Provide public information andwarnings——Carry out urgent decontamination

Acute internal exposure due to an
intake (Δ = 30 d)d
AD(Δ)red marrow

0.2 Gy for radionuclides
with atomic number Z ≥ 90e
2 Gy for radionuclides
with an atomic number Z ≤ 89e

AD(Δ)thyroid

2 Gy

AD(Δ)lungg

30 Gy

AD(Δ)colon

20 Gy

AD(Δ′)fetush

0.1 Gy

a

b

c

d

e

If the dose has been received:——Perform immediate medical
examination, consultation and indicatedmedical treatment——Carry out contamination control——Carry out immediate decorporationf(if applicable)——Carry out registration for longer term
medical follow-up——Provide comprehensive psychologicalcounselling

ADred marrow represents the average relative biological effectiveness (RBE) weighted absorbed
dose to internal tissues or organs (e.g. red marrow, lung, small intestine, gonads, thyroid)
and to the lens of the eye from exposure in a uniform field of strongly penetrating radiation.
Dose delivered to 100 cm2 at a depth of 0.5 cm under the body surface in tissue due to close
contact with a radioactive source (e.g. source carried in the hand or pocket).
The dose is to the 100 cm2 dermis (skin structures at a depth of 40 mg/cm2 (or 0.4 mm)
below the surface).
AD(Δ) is the RBE weighted absorbed dose delivered over a period of time Δ by the intake(I05) that will result in a severe deterministic effect in 5% of exposed individuals. This doseis calculated as described in appendix I of Ref. [29].
Different generic criteria are used to take account of the significant difference in RBE
weighted absorbed dose from exposure at the intake threshold values specific for these twogroups of radionuclides.

372

f

g

h

Decorporation is the action of the biological processes, facilitated by chemical or biologicalagents, by means of which incorporated radionuclides are removed from the human body.
The generic criterion for decorporation is based on the projected dose without decorporation.
For the purposes of these generic criteria, ‘lung’ means the alveolar-interstitial region of therespiratory tract.
For this particular case, ‘Δ′’ means the period of in utero development of the embryo andfetus.

TABLE IV.2. GUIDANCE VALUES FOR RESTRICTING EXPOSURE OF
EMERGENCY WORKERS
Tasks

Guidance valuea
Hp(10)b < 500 mSv

Life saving actions

This value may be exceeded undercircumstances in which the expected
benefits to others clearly outweigh the
emergency worker’s own health risks,
and the emergency worker volunteers totake the action and understands and accepts
these health risks

Actions to prevent severe deterministic effects
and actions to prevent the development ofcatastrophic conditions that could significantly
affect people and the environment

Hp(10) < 500 mSv

Actions to avert a large collective dose

Hp(10) < 100 mSv

ab

These values apply only for the dose from external exposure to strongly penetratingradiation. Doses from external exposure to weakly penetrating radiation and from intake
or skin contamination need to be prevented by all possible means. If this is not feasible, theeffective dose and the equivalent dose to a tissue or organ that are received have to be limited
to minimize the health risk to the individual in line with the risk associated with the guidancevalues given here.
Hp(10) is the personal dose equivalent Hp(d) where d = 10 mm.

373

REFERENCES
References are to editions that are current as of the time of publicationof these Standards. New editions that supersede these editions may be
adopted under national legislation. In the event that the publications
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See also: http://www-ns.iaea.org/standards/
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WORLD HEALTH ORGANIZATION, WHO Handbook on Indoor Radon: A Public
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INTERNATIONAL ATOMIC ENERGY AGENCY, Decommissioning of Facilities,
IAEA Safety Standards Series No. GSR Part 6, IAEA, Vienna (2014).
INTERNATIONAL ATOMIC ENERGY AGENCY, Predisposal Management ofRadioactive Waste, IAEA Safety Standards Series No. GSR Part 5, IAEA, Vienna (2009).
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for Facilities and Activities, IAEA Safety Standards Series No. GS-R-3, IAEA,
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AMERICAN HEALTH ORGANIZATION, UNITED NATIONS OFFICE FOR
THE CO-ORDINATION OF HUMANITARIAN AFFAIRS, WORLD HEALTHORGANIZATION, Preparedness and Response for a Nuclear or Radiological
Emergency, IAEA Safety Standards Series No. GS-R-2, IAEA, Vienna (2002).
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INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Ionizing-radiation
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for the Protection of Health of Workers and the General Public against the Dangers
Arising from Ionizing Radiation, Official Journal of the European Communities
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Research Involving Human Subjects, CIOMS, Geneva (2002).
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Radiological Protection in Biomedical Research, ICRP Publication 62, Pergamon Press,
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EUROPEAN COMMISSION, Principles and Methods for Establishing Concentrations
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INTERNATIONAL ATOMIC ENERGY AGENCY, Derivation of Activity
Concentration Values for Exclusion, Exemption and Clearance, Safety Reports Series
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INTERNATIONAL ATOMIC ENERGY AGENCY, Categorization of Radioactive
Sources, IAEA Safety Standards Series No. RS-G-1.9, IAEA, Vienna (2005).
INTERNATIONAL ATOMIC ENERGY AGENCY, Dangerous Quantities
of Radioactive Material (D-values), Emergency Preparedness and Response,
EPR-D-VALUES 2006, IAEA, Vienna (2006).
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Conversion Coefficients for Use in Radiological Protection against External Radiation,
ICRP Publication 74, Pergamon Press, Oxford and New York (1997).
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Age-dependent Doses to Members of the Public from Intake of Radionuclides — Part 1,
Publication 56, Pergamon Press, Oxford and New York (1990).
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Ingestion Dose Coefficients, Publication 67, Pergamon Press, Oxford and New York
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377

Annex
GENERIC CRITERIA FOR PROTECTIVE ACTIONS AND
OTHER RESPONSE ACTIONSTO REDUCE THE RISK OF STOCHASTIC EFFECTS
A–1. Table A–1 provides a set of generic criteria (expressed in terms ofprojected dose and dose that has been received) for use in the protection strategy
that are compatible with reference levels (expressed in terms of residual dose)
within a range of 20–100 mSv, and provides details of specific protective actions
and other response actions in different time frames.
A–2. For the thyroid, iodine thyroid blocking is an urgent protective action thatis prescribed: (i) if exposure due to radioactive iodine is involved, (ii) before or
shortly after a release of radioactive iodine and (iii) within a short period after anintake of radioactive iodine.
A–3. In the absence of national guidance, the generic criteria could be used
as a basis for the development of criteria at the national level. In exceptionalsituations, the use of higher values for the generic criteria may be necessary, suchas when no replacement food or water is available.

379

TABLE A–1. GENERIC CRITERIA FOR PROTECTIVE ACTIONS AND
OTHER RESPONSE ACTIONS IN AN EMERGENCY TO REDUCE THE
RISK OF STOCHASTIC EFFECTS
Generic criteria

Examples of protective actions andother response actions

Projected dose that exceeds the following generic criteria: Take urgent protective actions
and other response actions
Hthyroid

50 mSv in the first 7 days

Iodine thyroid blocking

E

100 mSv in the first 7 days

Hfetus

100 mSv in the first 7 days

Sheltering; evacuation; decontamination;
restrictions on food, milk and drinking water;
contamination control; reassurance of the public

Projected dose that exceeds the following generic criteria: Take early protective actions
and other response actions
E

100 mSv in the first year

Hfetus

100 mSv for the full period
of in utero development

Temporary relocation; decontamination; restrictions
on food, milk and drinking water; reassurance of the
public

Dose that has been received and that exceeds the following generic criteria: Take longer
term medical actions to detect and to effectively treat radiation induced health effects
E

100 mSv in a month

Health screening based on equivalent doses tospecific radiosensitive organs (as a basis for medical
follow-up); counselling

Hfetus

100 mSv for the full period
of in utero development

Counselling to allow informed decisions to be madein individual circumstances

380

DEFINITIONS
The following definitions apply for the purposes of these Standards.
Further definitions are provided in the IAEA Safety Glossary:
Terminology Used in Nuclear Safety and Radiation Protection (2007 Edition),
IAEA, Vienna (2007): http://www-ns.iaea.org/standards/safety-glossary.asp
The symbol ‘i’ denotes an information note.
The symbol ‘!’ denotes a cautionary note.
Notes do not constitute part of the definition.
absorbed dose, D
The fundamental dosimetric quantity D, defined as:

D=

d
dm

where d ε is the mean energy imparted by ionizing radiation to matter in a volume
element and dm is the mass of matter in the volume element.
i The SI unit for absorbed dose is joule per kilogram (J/kg), termed the gray(Gy).
i The energy can be averaged over any defined volume, the average dose being
equal to the total energy imparted in the volume divided by the mass in thevolume.
i Absorbed dose is defined at a point; the mean absorbed dose in a specified
tissue or organ of the human body is termed the organ dose.

accident
Any unintended event, including operating errors, equipment failures andother mishaps, the consequences or potential consequences of which are notnegligible from the point of view of protection and safety.
activation
The process of inducing radioactivity in matter by irradiation of that matter.

381

activity
1. The quantity A for an amount of radionuclide in a given energy state at agiven time, defined as:

A(t ) =

dN
dt

where dN is the expectation value of the number of spontaneous nuclear
transformations from the given energy state in the time interval dt.
i The SI unit for activity is reciprocal second (s–1), termed the becquerel (Bq).

2. See facilities and activities.
ambient dose equivalent, H*(d)The dose equivalent that would be produced by the corresponding aligned
and expanded field in the International Commission on Radiation Units andMeasurements ICRU sphere at a depth d on the radius vector opposing thedirection of the aligned field.
i Parameter defined at a point in a radiation field. Used as a directly measurable
proxy (i.e. substitute) for effective dose for use in monitoring of external
exposure.
i The recommended value of d for strongly penetrating radiation is 10 mm.

annual dose
The dose from external exposure in a year plus the committed dose fromintakes of radionuclides in that year.
approval
The granting of consent by a regulatory body.
area monitoring
A form of workplace monitoring in which an area is monitored by taking
measurements at different points in that area.
i As opposed to measurements by a static monitor.

382

assessment
The process, and the result, of analysing systematically and evaluating thehazards associated with sources and practices, and associated protection andsafety measures.
authorization
The granting by a regulatory body or other governmental body of written
permission for a person or organization (the operator) to conduct specified
activities.
bioassayAny procedure used to determine the nature, activity, location or retentionof radionuclides in the body by direct (in vivo) measurement or by in vitro
analysis of material excreted or otherwise removed from the body.
carers and comforters
Persons who willingly and voluntarily help (other than in their occupation)in the care, support and comfort of patients undergoing radiological procedures
for medical diagnosis or medical treatment.
clearance
The removal of regulatory control by the regulatory body from radioactive
material or radioactive objects within notified or authorized practices.
i Removal of regulatory control in this context refers to regulatory control
applied for radiation protection purposes.

clearance level
A value, established by a regulatory body and expressed in terms of activity
concentration, at or below which regulatory control may be removed from asource of radiation within a notified or authorized practice.
committed dose
The lifetime dose expected to result from an intake.

383

committed effective dose, E(τ)
The quantity E(τ), defined as:E( ) =

∑ w ⋅ H ( )T

TT

where HT(τ) is the committed equivalent dose to tissue or organ T over the
integration time τ elapsed after an intake of radioactive substances and wT is thetissue weighting factor for tissue or organ T. When τ is not specified, it will betaken to be 50 years for adults and the time to age 70 years for intakes by children.
committed equivalent dose, HT(τ)
The quantity HT(τ), defined as:
H T ( ) =∫t 0 +
t0

H T (t ) dt

where t0 is the time of intake, H T (t ) is the equivalent dose rate at time t in tissueor organ T and τ is the integration time elapsed after an intake of radioactive
substances. When τ is not specified, it will be taken to be 50 years for adults andthe time to age 70 years for intakes by children.
confinement
Prevention or control of releases of radioactive material to the environmentin operation or in accidents.
constraint
A prospective and source related value of individual dose (dose constraint)
or of individual risk (risk constraint) that is used in planned exposure situations
as a parameter for the optimization of protection and safety for the source, andthat serves as a boundary in defining the range of options in optimization.
i For occupational exposure, a constraint on individual dose to workers
established and used by registrants and licensees to set the range of options in
optimizing protection and safety for the source.

384

i For public exposure, the dose constraint is a source related value established orapproved by the government or the regulatory body, with account taken of thedoses from planned operations of all sources under control.
i The dose constraint for each particular source is intended, among other things,
to ensure that the sum of doses from planned operations for all sources undercontrol remains within the dose limit.
i For medical exposure, the dose constraint is a source related value used in
optimizing the protection of carers and comforters of patients undergoingradiological procedures, and the protection of volunteers subject to exposure
as part of a programme of biomedical research.
i The risk constraint is a source related value that provides a basic level ofprotection for the individuals most at risk from a source. This risk is a functionof the probability of an unintended event causing a dose and the probabilityof the detriment due to such a dose. Risk constraints correspond to dose
constraints but apply to potential exposure.

consumer productA device or manufactured item into which radionuclides have deliberately
been incorporated or produced by activation, or which generates ionizing
radiation, and which can be sold or made available to members of the public
without special surveillance or regulatory control after sale.
i This includes items such as smoke detectors and luminous dials into whichradionuclides have deliberately been incorporated and ion generating tubes.
It does not include building materials, ceramic tiles, spa waters, minerals andfoodstuffs, and it excludes products and appliances installed in public places(e.g. exit signs).

containment
Methods or physical structures designed to prevent or control the releaseand the dispersion of radioactive substances.
contamination
Radioactive substances on surfaces, or within solids, liquids or gases(including the human body), where their presence is unintended or undesirable,or the process giving rise to their presence in such places.
i Contamination does not include residual radioactive material remaining at asite after the completion of decommissioning.

385

i The term ‘contamination’ may have a connotation that is not intended. The
term ‘contamination’ refers only to the presence of radioactivity, and gives no
indication of the magnitude of the hazard involved.

control
The function or power or (usually as controls) means of directing, regulatingor restraining.
i It should be noted that the usual meaning of the English word ‘control’ in safety
related contexts is somewhat ‘stronger’ (more active) than that of its usualtranslations and other similar words in some other languages. For example,‘control’ typically implies not only checking or monitoring something but also
ensuring that corrective or enforcement measures are taken if the results of thechecking or monitoring indicate such a need. This is in contrast, for example,
to the more limited usage of the equivalent word in French and Spanish.

regulatory control. Any form of control or regulation applied to facilities
and activities by a regulatory body for reasons relating to nuclear safety andradiation protection or to nuclear security.
controlled area
A defined area in which specific protection measures and safety provisions
are or could be required for controlling exposures or preventing the spread ofcontamination in normal working conditions, and preventing or limiting theextent of potential exposures.
decontamination
The complete or partial removal of contamination by a deliberate physical,
chemical or biological process.
i This definition is intended to include a wide range of processes for removing
contamination from people, equipment and buildings, but to exclude theremoval of radionuclides from within the human body or the removal ofradionuclides by natural weathering or migration processes, which are notconsidered to be decontamination.

decorporation
The biological processes, facilitated by a chemical or biological agent, bywhich incorporated radionuclides are removed from the human body.

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deterministic effectA radiation induced health effect for which generally a threshold level ofdose exists above which the severity of the effect is greater for a higher dose.
severe deterministic effect. A deterministic effect that is fatal or life
threatening or results in a permanent injury that reduces quality of life.
i The level of the threshold dose is characteristic of the particular health effectbut may also depend, to a limited extent, on the exposed individual. Examples
of deterministic effects include erythema and acute radiation syndrome(radiation sickness).
i Deterministic effects are also referred to as ‘harmful tissue reactions’.

diagnostic reference level
A level used in medical imaging to indicate whether, in routine conditions,the dose to the patient or the amount of radiopharmaceuticals administered ina specified radiological procedure for medical imaging is unusually high or
unusually low for that procedure.
directional dose equivalent, H΄(d,Ω)
The dose equivalent that would be produced by the corresponding expanded
field in the International Commission on Radiation Units and Measurements
ICRU sphere at a depth d on a radius in a specified direction Ω.
i Parameter defined at a point in a radiation field. Used as a directly measurable
proxy (i.e. substitute) for equivalent dose in the skin for use in monitoring of
external exposure.
i The recommended value of d for weakly penetrating radiation is 0.07 mm.

disposal
Emplacement of waste in an appropriate facility without the intention of
retrieval.
dose
1. A measure of the energy deposited by radiation in a target.
2. Absorbed dose, committed equivalent dose, committed effective dose,
effective dose, equivalent dose or organ dose, as indicated by the context.
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committed dose. committed equivalent dose or committed effective dose.
dose assessment
Assessment of the dose(s) to an individual or group of people.
dose constraint
See constraint.
dose limit
The value of the effective dose or the equivalent dose to individuals inplanned exposure situations that is not to be exceeded.
effective dose, E
The quantity E, defined as a summation of the tissue or organ equivalentdoses, each multiplied by the appropriate tissue weighting factor:E=∑w ⋅ H
T

T

T

where HT is the equivalent dose in tissue or organ T and wT is the tissue weighting
factor for tissue or organ T. From the definition of equivalent dose, it follows that:E=∑w ⋅ ∑w ⋅ D
T

T

R

T,R

R

where wR is the radiation weighting factor for radiation type R and DT,R is theaverage absorbed dose in the tissue or organ T delivered by radiation type R.
i The SI unit for effective dose is joule per kilogram (J/kg), termed thesievert (Sv). An explanation of the quantity is given in Annex B of International
Commission on Radiological Protection Publication 1031.

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INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
The 2007 Recommendations of the International Commission on Radiological Protection,
Publication 103, Elsevier (2007).

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i Effective dose is a measure of dose designed to reflect the amount of radiation
detriment likely to result from the dose.
i Effective dose cannot be used to quantify higher doses or to make decisions on
the need for any medical treatment relating to deterministic effects.
i Values of effective dose from exposure for any type(s) of radiation and anymode(s) of exposure can be compared directly.

emergency
A non-routine situation that necessitates prompt action, primarily to
mitigate a hazard or adverse consequences for human health and safety, qualityof life, property or the environment. This includes nuclear or radiologicalemergencies and conventional emergencies such as fires, release of hazardous
chemicals, storms or earthquakes. It includes situations for which prompt action
is warranted to mitigate the effects of a perceived hazard.
nuclear or radiological emergency. An emergency in which there is, or isperceived to be, a hazard due to:(a)(b)

The energy resulting from a nuclear chain reaction or from the decayof the products of a chain reaction; orRadiation exposure.

emergency action level (EAL)
A specific, predetermined, observable criterion used to detect, recognize
and determine the emergency class.
emergency arrangements
The integrated set of infrastructural elements necessary to provide thecapability for performing a specified function or task required in response toa nuclear or radiological emergency. These elements may include authorities
and responsibilities, organization, coordination, personnel, plans, procedures,
facilities, equipment or training.

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emergency class
A set of conditions that warrant a similar immediate emergency response.
i This is the term used for communicating to the response organizations andto the public the level of response needed. The events that belong to a given
emergency class are defined by criteria specific to the installation, source orpractice, which, if exceeded, indicate classification at the prescribed level.
For each emergency class, the initial actions of the response organizations arepredefined.

emergency exposure situation
A situation of exposure that arises as a result of an accident, a malicious act
or other unexpected event, and requires prompt action in order to avoid or reduce
adverse consequences.
i Emergency exposures can be reduced only by protective actions and other
response actions.

emergency planA description of the objectives, policy and concept of operations for the
response to an emergency and of the structure, authorities and responsibilities fora systematic, coordinated and effective response. The emergency plan serves as
the basis for the development of other plans, procedures and checklists.
emergency preparedness
The capability to take actions that will effectively mitigate the consequencesof an emergency for human health and safety, quality of life, property and theenvironment.
emergency procedures
A set of instructions describing in detail the actions to be taken by response
personnel in an emergency.
emergency response
The performance of actions to mitigate the consequences of an emergency
for human health and safety, quality of life, property and the environment. It may
also provide a basis for the resumption of normal social and economic activity.
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emergency worker
A person having specified duties as a worker in response to an emergency.
i Emergency workers may include workers employed by registrants andlicensees, as well as personnel of response organizations, such as police
officers, firefighters, medical personnel, and drivers and crews of evacuation
vehicles.
i An emergency worker may or may not be designated as such in advance ofan emergency. An emergency worker not designated as such in advance of an
emergency is not necessarily a worker prior to the emergency.

employer
A person or organization with recognized responsibilities, commitments
and duties towards a worker in the employment of the person or organization by
virtue of a mutually agreed relationship.
!

A self-employed person is regarded as being both an employer and a worker.

environment
The conditions under which people, animals and plants live or develop andwhich sustain all life and development; especially such conditions as affected byhuman activities.
i Protection of the environment includes the protection and conservationof: non-human species, both animal and plant, and their biodiversity;
environmental goods and services, such as the production of food and feed;
resources used in agriculture, forestry, fisheries and tourism; amenities used in
spiritual, cultural and recreational activities; media, such as soil, water and air;and natural processes, such as carbon, nitrogen and water cycles.

environmental monitoring
The measurement of external dose rates due to sources in the environmentor of radionuclide concentrations in environmental media.
i Contrasted with source monitoring.

equilibrium equivalent concentration (EEC)
The activity concentration of 222Rn or 220Rn in radioactive equilibriumwith its short lived progeny that would have the same potential alpha energy
concentration as the actual (non-equilibrium) mixture.
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i The equilibrium equivalent concentration of 222Rn is given by:
EEC 222Rn = (0.104 × C(218Po)) + (0.514 × C(214Pb)) + (0.382 × C(214Bi))
where C(x) is the activity concentration of nuclide x in air.
1 Bq/m3 EEC 222Rn corresponds to 5.56 × 10–6 mJ/m3.
i The equilibrium equivalent concentration of 220Rn is given by:
EEC 220Rn = (0.913 × C(212Pb)) + (0.087 × C(212Bi))
where C(x) is the activity concentration of nuclide x in air.
1 Bq/m3 EEC 220Rn corresponds to 7.57 × 10–5 mJ/m3.

equilibrium factor
The ratio of the equilibrium equivalent activity concentration of 222Rn to
the actual 222Rn activity concentration.
equivalent dose, HT
The quantity HT,R, defined as:
H T,R = w R ⋅ DT,R

where DT,R is the absorbed dose delivered by radiation type R averaged over atissue or organ T and wR is the radiation weighting factor for radiation type R.
When the radiation field is composed of different radiation types with different
values of wR, the equivalent dose is:HT =∑w ⋅ DR

T,R

R

i The SI unit for equivalent dose is joule per kilogram (J/kg), termed thesievert (Sv). An explanation of the quantity is given in Annex B of International
Commission on Radiological Protection Publication 1032.
i Equivalent dose is a measure of the dose to a tissue or organ designed to reflect
the amount of harm caused.
i Equivalent dose cannot be used to quantify higher doses or to make decisions
on the need for any medical treatment relating to deterministic effects.
i Values of equivalent dose to a specified tissue or organ from any type(s) ofradiation can be compared directly.

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INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
The 2007 Recommendations of the International Commission on Radiological Protection,
Publication 103, Elsevier (2007).

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eventIn the context of the reporting and analysis of events, an event is any
occurrence unintended by the operator, including operating error, equipment
failure or other mishap, and deliberate action on the part of others, theconsequences or potential consequences of which are not negligible from thepoint of view of protection and safety.
exemption
The determination by a regulatory body that a source or practice need not be
subject to some or all aspects of regulatory control on the basis that the exposureand the potential exposure due to the source or practice are too small to warrant
the application of those aspects or that this is the optimum option for protection
irrespective of the actual level of the doses or risks.
exemption level
A value, established by a regulatory body and expressed in terms of activity
concentration, total activity, dose rate or radiation energy, at or below whicha source of radiation need not be subject to some or all aspects of regulatory
control.
existing exposure situation
A situation of exposure that already exists when a decision on the need forcontrol needs to be taken.
i Existing exposure situations include exposure to natural background radiationthat is amenable to control; exposure due to residual radioactive material
that derives from past practices that were never subject to regulatory control
or exposure due to residual radioactive material deriving from a nuclear orradiological emergency after an emergency has been declared to be ended.

exposure
The state or condition of being subject to irradiation.
external exposure. Exposure to radiation from a source outside the body.
internal exposure. Exposure to radiation from a source within the body.

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exposure pathway
A route by which radiation or radionuclides can reach humans and cause
exposure.
facilities and activities3
A general term encompassing nuclear facilities, uses of all sources ofionizing radiation, all radioactive waste management activities, transport ofradioactive material and any other practice or circumstances in which people may
be subject to exposure to radiation from naturally occurring or artificial sources.
i ‘Facilities’ includes: nuclear facilities; irradiation installations; some mining
and raw material processing facilities such as uranium mines; radioactive
waste management facilities; and any other places where radioactive material
is produced, processed, used, handled, stored or disposed of — or whereradiation generators are installed — on such a scale that consideration ofprotection and safety is required.
i ‘Activities’ includes: the production, use, import and export of radiation
sources for industrial, research and medical purposes; the transport ofradioactive material; the decommissioning of facilities; radioactive waste
management activities such as the discharge of effluents; and some aspects of
the remediation of sites affected by residues from past activities.
i This term is intended to provide an alternative to the terminology of sources
and practices (or intervention) to refer to general categories of situations. For
example, a practice may involve many different facilities and/or activities,
whereas the general definition (1) of ‘source’ is too broad in some cases: afacility or activity might constitute a source, or might involve the use of manysources, depending upon the interpretation used.
i The term ‘facilities and activities’ is very general, and includes those forwhich little or no regulatory control may be necessary or achievable: the more
specific terms ‘authorized facility’ and ‘authorized activity’ should be used to
distinguish those facilities and activities for which any form of authorization
has been given.

3

A small number of ‘catch-all’ terms — e.g. ‘facilities and activities’; ‘protection andsafety’; ‘radiation risks’; and ‘structures, systems and components’ — are defined in the IAEA
Safety Glossary. These terms may be used in exactly the form listed to describe a whole groupof things without cumbersome repetition, or slight variations of the terms may be used to referto particular subgroups. Although the definitions include an indication of the meanings of theseparate elements of the terms, these are not intended to be applied rigidly: if precise referenceis needed to particular items covered by the ‘catch-all’ term, more precise terms should be used.

394

i In the Fundamental Safety Principles (Safety Fundamentals), the term
‘facilities and activities — existing and new — utilized for peaceful purposes’
is abbreviated for convenience to ‘facilities and activities’ as a general term
encompassing any human activity that may cause people to be exposed toradiation risks arising from naturally occurring or artificial sources (seepara. 1.9 of IAEA Safety Standards Series No. SF-14).

feed
Any single material or multiple materials, whether processed,
semi-processed or raw, that is or are intended to be fed directly to food producing
animals.
fluencei A measure of the strength of a radiation field. Commonly used without
qualification to mean particle fluence.

energy fluence, Ψ. A measure of the energy density of a radiation field,
defined as:

Ψ=

dR
da

where dR is the radiation energy incident on a sphere of cross-sectional
area da.
i See International Commission on Radiological Protection Publication 745.

4EUROPEAN ATOMIC ENERGY COMMUNITY, FOOD AND AGRICULTURE
ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGYAGENCY, INTERNATIONAL LABOUR ORGANIZATION, INTERNATIONALMARITIME ORGANIZATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICANHEALTH ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME,WORLD HEALTH ORGANIZATION, Fundamental Safety Principles, IAEA Safety Standards
Series No. SF-1, IAEA, Vienna (2006).
5
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Conversion Coefficients for Use in Radiological Protection against External Radiation, ICRP
Publication 74, Pergamon Press, Oxford and New York (1997).

395

particle fluence, Φ. A measure of the density of particles in a radiation
field, defined as:

Φ=

dN
da

where dN is the number of particles incident on a sphere of cross-sectional
area da.
i See International Commission on Radiological Protection Publication 745.

food
Any substance, whether processed, semi-processed or raw, that is intended
for human consumption.
i This includes drink (other than fresh water), chewing gum and substances usedin the preparation or processing of food; it does not include cosmetics, tobacco
or drugs. Consumption in this context refers to ingestion.

graded approach
For a system of control, such as a regulatory system or a safety system, aprocess or method in which the stringency of the control measures and conditions
to be applied is commensurate, to the extent practicable, with the likelihood andpossible consequences of, and the level of risk associated with, a loss of control.
hazard assessment
Assessment of hazards associated with facilities, activities or sources
within or beyond the borders of a State in order to identify:
(a)
(b)

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Those events and the associated areas for which protective actions may berequired within the State;
The actions that would be effective in mitigating the consequences of such
events.

health authority
A governmental authority (at the national, regional or local level) that is
responsible for policies and interventions, including the development of standards
and the provision of guidance, for maintaining or improving human health, andthat has the legal power of enforcing such policies and interventions.
health professional
An individual who has been formally recognized through appropriate
national procedures to practise a profession related to health (e.g. medicine,
dentistry, chiropractic, podiatry, nursing, medical physics, medical radiation
technology, radiopharmacy, occupational health).
health screening programme
A programme in which health tests or medical examinations are performed
for the purpose of early detection of disease.
health surveillance
See workers’ health surveillance.
hereditary effectA radiation induced health effect that occurs in a descendant of the exposed
person.
i Hereditary effects are usually stochastic effects.
i Contrasting term: somatic effect.

ICRU sphereA sphere of 30 cm diameter made of tissue equivalent material with adensity of 1 g/cm3 and a mass composition of 76.2% oxygen, 11.1% carbon,
10.1% hydrogen and 2.6% nitrogen.
i The International Commission on Radiation Units and Measurements ICRU
sphere is used as a reference phantom in defining dose equivalent quantities.6

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COMMISSIONONRADIATIONUNITSANDMEASUREMENTS, Radiation Quantities and Units, Rep. 33, ICRU, Bethesda, MD (1980).

397

incident
Any unintended event, including operating errors, equipment failures,
initiating events, accident precursors, near misses or other mishaps, orunauthorized act, malicious or non-malicious, the consequences or potential
consequences of which are not negligible from the point of view of protection
and safety.
individual monitoring
Monitoring using measurements by equipment worn by individuals, ormeasurements of quantities of radioactive substances in or on, or taken into, thebodies of individuals, or measurements of quantities of radioactive substances
excreted from the body by individuals.
i Usually contrasted with workplace monitoring.

inspection imaging device
An imaging device designed specifically for imaging persons or cargoconveyances for the purpose of detecting concealed objects on or within thehuman body or within cargo or a vehicle.
i In some types of inspection imaging device, ionizing radiation is used to
produce images by backscatter, transmission or both. Other types of inspection
imaging device utilize imaging by means of electrical and magnetic fields,
ultrasound and sonar waves, nuclear magnetic resonance, microwaves,terahertz rays, millimetre waves, infrared radiation or visible light.

intake1. The act or process of taking radionuclides into the body by inhalation oringestion or through the skin.
i Other intake pathways are injection (important in nuclear medicine) and intake
via a wound, as distinguished from intake through (intact) skin.

2. The activity of a radionuclide taken into the body in a given time period
or as a result of a given event.
interested party
A person, company, etc., with a concern or interest in the activities andperformance of an organization, business, system, etc.
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i The term ‘interested party’ is used in a broad sense to mean a person or grouphaving an interest in the performance of an organization. Those who can
influence events may effectively become interested parties — whether their‘interest’ is regarded as ‘genuine’ or not — in the sense that their views need
to be considered. Interested parties have typically included the following:
customers, owners, operators, employees, suppliers, partners, trade unions; theregulated industry or professionals; scientific bodies; governmental agencies
or regulatory bodies (national, regional and local) whose responsibilities may
cover nuclear energy; the media; the public (individuals, community groups
and interest groups); and other States, especially neighbouring States that haveentered into agreements providing for an exchange of information concerning
possible transboundary impacts, or States involved in the import or export ofcertain technologies or materials.

investigation level
The value of a quantity such as effective dose, intake or contamination perunit area or volume at or above which an investigation would be conducted.
ionizing radiation
See radiation.
justification
1. The process of determining for a planned exposure situation whether apractice is, overall, beneficial; i.e. whether the expected benefits to individuals
and to society from introducing or continuing the practice outweigh the harm(including radiation detriment) resulting from the practice.
2. The process of determining for an emergency exposure situation or an
existing exposure situation whether a proposed protective action or remedialaction is likely, overall, to be beneficial; i.e. whether the expected benefits toindividuals and to society (including the reduction in radiation detriment) fromintroducing or continuing the protective action or remedial action outweigh thecost of such action and any harm or damage caused by the action.

399

kerma, K
The quantity K, defined as:
K=

dE tr
dm

where dEtr is the sum of the initial kinetic energies of all charged ionizing
particles liberated by uncharged ionizing particles in a material of mass dm.
i The SI unit for kerma is joule per kilogram (J/kg), termed the gray (Gy).

air kerma. The kerma value for air.
i Under charged particle equilibrium conditions, the air kerma (in grays) isnumerically approximately equal to the absorbed dose in air (in grays).

reference air kerma rate. The kerma rate to air, in air, at a reference
distance of 1 m, corrected for air attenuation and scattering.
i This quantity is expressed in μGy/h at 1 m.

licence
A legal document issued by the regulatory body granting authorization to
perform specified activities relating to a facility or activity.
i A licence is a product of the authorization process and a practice with a current
licence is an authorized practice.
i Authorization may take other forms, such as registration.
i The licensee is the person or organization having overall responsibility for a
facility or activity.

licensee
The holder of a current licence.
limit
The value of a quantity used in certain specified activities or circumstancesthat must not be exceeded.
authorized limit. A limit on a measurable quantity, established or formally
accepted by a regulatory body.
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operational limits and conditions. A set of rules setting forth parameter
limits, the functional capability and the performance levels of equipment
and personnel approved by the regulatory body for safe operation of an
authorized facility.
linear–no threshold (LNT) hypothesis
The hypothesis that the risk of stochastic effects is directly proportional
to the dose for all levels of dose and dose rate below those levels at which
deterministic effects occur.
i This means that any non-zero dose implies a non-zero risk of stochastic
effects.
i This is the working hypothesis on which the IAEA’s safety standards are based.
It is not proven — indeed it is probably not provable — for low doses and dose
rates, but it is considered the most radiobiologically defensible assumption onwhich to base safety standards.

lung absorption typeA classification used to distinguish between the different rates at which
inhaled radionuclides are transferred from the respiratory tract to the blood.
i International Commission on Radiological Protection Publication 717
classifies materials into four lung absorption types:(a) Type V (very fast) are materials that, for dosimetric purposes, are assumed to
be instantaneously absorbed into the blood;(b) Type F (fast) are materials that are readily absorbed into the blood;(c) Type M (moderate) are materials that have intermediate rates of absorption
into the blood;(d) Type S (slow) are materials that are relatively insoluble and are only slowly
absorbed into the blood.

i See also gut transfer factor, a similar concept for ingested radionuclides in thegastrointestinal tract.

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INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Age-dependent Doses to Members of the Public from Intakes of Radionuclides: Part 4 Inhalation
Dose Coefficients, Publication 71, Pergamon Press, Oxford and New York (1995).

401

management system
A set of interrelated or interacting elements (system) for establishingpolicies and objectives and enabling the objectives to be achieved in an efficientand effective manner.
i The component parts of the management system include the organizational
structure, resources and organizational processes. Management is defined (inISO 9000) as coordinated activities to direct and control an organization.
i The management system integrates all elements of an organization into one
coherent system to enable all of the organization’s objectives to be achieved.
These elements include the organizational structure, resources and processes.
Personnel, equipment and organizational culture as well as the documented
policies and processes are parts of the management system. The organization’s
processes have to address the totality of the requirements on the organization
as established in, for example, IAEA safety standards and other international
codes and standards.

medical exposure
Exposure incurred by patients for the purposes of medical or dental
diagnosis or treatment; by carers and comforters; and by volunteers subject toexposure as part of a programme of biomedical research.
i A patient is an individual who is a recipient of services of health care
professionals and/or their agents that are directed at (a) promotion of health;(b) prevention of illness and injury; (c) monitoring of health; (d) maintaining
health; and (e) medical treatment of diseases, disorders and injuries in orderto achieve a cure or, failing that, optimum comfort and function. Some
asymptomatic individuals are included. For the purpose of the requirements on
medical exposure in the IAEA safety standards, the term ‘patient’ refers only
to those individuals undergoing radiological procedures.

medical physicist
A health professional with specialist education and training in the concepts
and techniques of applying physics in medicine and competent to practise
independently in one or more of the subfields (specialties) of medical physics.
i Competence of persons is normally assessed by the State by having a formal
mechanism for registration, accreditation or certification of medical physicists
in the various specialties (e.g. diagnostic radiology, radiation therapy, nuclear
medicine). States that have yet to develop such a mechanism would need toassess the education, training and competence of any individual proposed by
the licensee to act as a medical physicist and to decide, on the basis of either

402

international accreditation standards or standards of a State where such an
accreditation system exists, whether such an individual could undertake thefunctions of a medical physicist, within the required specialty.

medical radiation facility
A medical facility in which radiological procedures are performed.
medical radiation technologist
A health professional, with specialist education and training in medical
radiation technology, competent to perform radiological procedures, ondelegation from the radiological medical practitioner, in one or more of thespecialties of medical radiation technology.
i Competence of persons is normally assessed by the State by having a formal
mechanism for registration, accreditation or certification of medical radiation
technologists in the various specialties (e.g. diagnostic radiology, radiation
therapy, nuclear medicine). States that have yet to develop such a mechanism
would need to assess the education, training and competence of any individual
proposed by the licensee to act as a medical radiation technologist and to
decide, on the basis of either international standards or standards of a State
where such a system exists, whether such an individual could undertake thefunctions of a medical radiation technologist, within the required specialty.

medical radiological equipment
Radiological equipment used in medical radiation facilities to perform
radiological procedures that either delivers an exposure of an individual or
directly controls or influences the extent of such exposure. The term applies toradiation generators, such as X ray machines or medical linear accelerators; todevices containing sealed sources, such as 60Co teletherapy units; to devices
used in medical imaging to capture images, such as gamma cameras, image
intensifiers or flat panel detectors, and to hybrid systems such as positronemission tomography–computed tomography scanners.
member of the public
For purposes of protection and safety, in a general sense, any individualin the population except when subject to occupational exposure or medical
exposure. For the purpose of verifying compliance with the annual dose limit for
public exposure, this is the representative person.

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monitoring
The measurement of dose, dose rate or activity for reasons relating to theassessment or control of exposure to radiation or exposure due to radioactive
substances, and the interpretation of the results.
i ‘Measurement’ is used somewhat loosely here. The ‘measurement’ of dose
often means the measurement of a dose equivalent quantity as a proxy (i.e.
substitute) for a dose quantity that cannot be measured directly. Also, sampling
may be involved as a preliminary step to measurement.
i Measurements may actually be made of radiation levels, airborne activity
concentrations, levels of contamination, quantities of radioactive material, or
individual doses. The results of these measurements may be used to assessradiological hazards or doses resulting or potentially resulting from exposure.
i Monitoring may be subdivided in two different ways: according to where themeasurements are made, into individual monitoring, workplace monitoring,source monitoring and environmental monitoring; and, according to the
purpose of the monitoring, into routine monitoring, task related monitoringand special monitoring.

natural backgroundThe doses, dose rates or activity concentrations associated with natural
sources, or any other sources in the environment that are not amenable to control.
i This is normally considered to include doses, dose rates or activity
concentrations associated with natural sources, global fallout (but not local
fallout) from atmospheric nuclear weapon tests and the Chernobyl accident.

notification
A document submitted to the regulatory body by a person or organization to
notify an intention to carry out a practice or other use of a source.
nuclear fuel cycle
All operations associated with the production of nuclear energy.
i These include:
(a)
(b)
(c)
(d)
(e)

404

Mining and processing of uranium ores or thorium ores;
Enrichment of uranium;
Manufacture of nuclear fuel;Operation of nuclear reactors (including research reactors);
Reprocessing of spent fuel;(f) All waste management activities (including decommissioning) relating tooperations associated with the production of nuclear energy;(g) Any related research and development activities.

nuclear installation
Any nuclear facility subject to authorization that is part of the nuclear fuelcycle, except facilities for the mining or processing of uranium ores or thorium
ores and radioactive waste disposal facilities.
i This definition thus includes: nuclear power plants; research reactors(including subcritical and critical assemblies) and any adjoining radioisotope
production facilities; spent fuel storage facilities; facilities for the enrichmentof uranium; nuclear fuel fabrication facilities; conversion facilities; facilities
for the reprocessing of spent fuel; facilities for the predisposal managementof radioactive waste arising from nuclear fuel cycle facilities; and nuclear fuelcycle related research and development facilities.

nuclear or radiological emergency
See emergency.
(nuclear) safety
The achievement of proper operating conditions, prevention of accidents
or mitigation of accident consequences, resulting in protection of workers, thepublic and the environment from undue radiation hazards.
See also protection and safety, safety.
(nuclear) security
The prevention of, detection of, and response to, criminal or intentional
unauthorized acts involving or directed at nuclear material, other radioactive
material, associated facilities, or associated activities.

405

i There is not an exact distinction between the general terms ‘safety’ and‘security’. In general, ‘security’ is concerned with criminal acts or intentional
unauthorized acts by humans that could cause or threaten harm to otherhumans; ‘safety’ is concerned with the broader issue of harm to humans (or to
the environment) from radiation, whatever the cause. The precise interaction
between security and safety depends on the context. Security of nuclear
material for reasons relating to non-proliferation is outside the scope of the
IAEA safety standards.

occupancy factor
A typical fraction of the time for which a location is occupied by anindividual or group.
occupational exposure
Exposure of workers incurred in the course of their work.
operational intervention level (OIL)
A set level of a measurable quantity that corresponds to a generic criterion.
i Operational intervention levels are typically expressed in terms of dose rates
or of activity of radioactive material released, time integrated air activity
concentrations, ground or surface concentrations, or activity concentrationsof radionuclides in environmental, food or water samples. An operational
intervention level is used immediately and directly (without further
assessment) to determine the appropriate protective actions on the basis of anenvironmental measurement.

optimization of protection and safety
The process of determining what level of protection and safety would resultin the magnitude of individual doses, the number of individuals (workers andmembers of the public) subject to exposure and the likelihood of exposure being“as low as reasonably achievable, economic and social factors being taken into
account” (ALARA).
For medical exposures of patients, the optimization of protection and safety
is the management of the radiation dose to the patient commensurate with the
medical purpose.

406

i “Protection and safety is optimized” means that optimization of protection andsafety has been applied and the result of that process has been implemented.

personal dose equivalent, Hp(d)The dose equivalent in soft tissue below a specified point on the body at an
appropriate depth d.
i Parameter used as a directly measurable proxy (i.e. substitute) for equivalentdose in tissues or organs or (with d = 10 mm) for effective dose, in individual
monitoring of external exposure.
i The recommended values of d are 10 mm for strongly penetrating radiationand 0.07 mm for weakly penetrating radiation for whole body monitoring.
i Hp(0.07) is used for monitoring for hands and feet for all radiation types.
i Hp(3) is used for monitoring exposure of the lens of the eye.
i ‘Soft tissue’ is commonly interpreted as the International Commission on
Radiation Units and Measurements ICRU sphere.

planned exposure situation
The situation of exposure that arises from the planned operation of a sourceor from a planned activity that results in an exposure due to a source.
i Since provision for protection and safety can be made before embarking on theactivity concerned, associated exposures and their probabilities of occurrence
can be restricted from the outset. The primary means of controlling exposurein planned exposure situations is by good design of installations, equipment
and operating procedures. In planned exposure situations, a certain level of
exposure is expected to occur.

planning target volume
A geometrical concept used in radiation therapy for planning medical
treatment with consideration of the net effect of movements of the patient andof the tissues to be irradiated, variations in size and shape of the tissues, andvariations in beam geometry such as beam size and beam direction.
potential exposure
Prospectively considered exposure that is not expected to be delivered
with certainty but that may result from an anticipated operational occurrence or
accident at a source or owing to an event or sequence of events of a probabilistic
nature, including equipment failures and operating errors.
407

i Potential exposure includes prospectively considered (hypothetical) exposuresdue to a source in an event or sequence of events of a probabilistic nature,including exposures resulting from an accident, equipment failures, operating
errors, natural phenomena (such as hurricanes, earthquakes and floods) andinadvertent human intrusion (such as an intrusion into a near surface waste
disposal facility after institutional control is removed).

practice
Any human activity that introduces additional sources of exposure or
additional exposure pathways, or modifies the network of exposure pathways
from existing sources, so as to increase the exposure or the likelihood of exposureof people or the number of people exposed.
!

Radioactive waste is generated as a result of practices that involve somebeneficial effect, such as the generation of electricity by nuclear means or
the diagnostic application of radioisotopes. The management of this waste istherefore only one part of the overall practice.

projected dose
The dose that would be expected to be received if planned protective
actions were not taken.
protection (against radiation)
radiation protection (also radiological protection). The protection ofpeople from harmful effects of exposure to ionizing radiation, and themeans for achieving this.
protection and safety
The protection of people against exposure to ionizing radiation or exposuredue to radioactive material and the safety of sources, including the means forachieving this, and the means for preventing accidents and for mitigating theconsequences of accidents if they do occur.
i For the purposes of the IAEA safety standards, ‘protection and safety’ includes
the protection of people against ionizing radiation and safety; it does notinclude non-radiation-related aspects of safety. ‘Protection and safety’ isconcerned with both radiation risks under normal circumstances and radiation
risks as a consequence of incidents, as well as with other possible directconsequences of a loss of control over a nuclear reactor core, nuclear chain408

reaction, radioactive source or any other source of radiation. Safety measures
include actions to prevent incidents and arrangements put in place to mitigate
their consequences if they were to occur.

protection of the environment
See environment.
protective action
An action for the purposes of avoiding or reducing doses that mightotherwise be received in an emergency exposure situation or an existing exposure
situation.
public exposure
Exposure incurred by members of the public due to sources in planned
exposure situations, emergency exposure situations and existing exposure
situations, excluding any occupational exposure or medical exposure.
qualified expert
An individual who, by virtue of certification by appropriate boards orsocieties, professional licence or academic qualifications and experience, is duly
recognized as having expertise in a relevant field of specialization, e.g. medical
physics, radiation protection, occupational health, fire safety, quality management
or any relevant engineering or safety specialty.
quality assurance
The function of a management system that provides confidence thatspecified requirements will be fulfilled.
i Planned and systematic actions are necessary to provide adequate confidence
that an item, process or service will satisfy given requirements for quality;
for example, those specified in the licence. This statement has been slightly
modified from that in the International Organization for Standardization’s
publication ISO 921:19978 to ‘an item, process or service’ instead of ‘a productor service’ and to add the example. A more general definition of quality
assurance (all those planned and systematic actions necessary to provide

8

INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Nuclear Energy:
Vocabulary (Second Edition), ISO 921:1997, ISO, Geneva (1997).

409

confidence that a structure, system or component will perform satisfactorily
in service) and definitions of related terms can be found in the International
Organization for Standardization’s publication ISO 8402:19949.

radiation!

When used in IAEA publications, the term ‘radiation’ refers only to ionizing
radiation unless otherwise stated. The IAEA has no statutory responsibilities inrelation to non-ionizing radiation.

ionizing radiation. For the purposes of radiation protection, radiation
capable of producing ion pairs in biological material(s).
i For most practical purposes, it may be assumed that strongly penetratingradiation includes photons of energy above about 12 keV, electrons of energy
more than about 2 MeV, and neutrons.
i For most practical purposes, it may be assumed that weakly penetratingradiation includes photons of energy below about 12 keV, electrons of energy
less than about 2 MeV, and massive charged particles such as protons andalpha particles.

radiation detriment
The total harm that would eventually be incurred by a group that is subject
to exposure and by its descendants as a result of the group’s exposure to radiationfrom a source.
radiation generator
See source (1).
radiation protection
See protection.
radiation protection officer
A person technically competent in radiation protection matters relevant fora given type of practice who is designated by the registrant, licensee or employer
to oversee the application of regulatory requirements.

9

INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Quality
Management and Quality Assurance — Vocabulary, ISO 8024:1994, ISO, Geneva (1994).

410

radiation risks
Detrimental health effects of exposure to radiation (including the likelihoodof such effects occurring), and any other safety related risks (including those to
the environment) that might arise as a direct consequence of:
(a)
(b)
(c)

Exposure to radiation;
The presence of radioactive material (including radioactive waste) or
its release to the environment;
A loss of control over a nuclear reactor core, nuclear chain reaction,
radioactive source or any other source of radiation.

radiation weighting factor, wR
A number by which the absorbed dose in a tissue or organ is multiplied toreflect the relative biological effectiveness of the radiation in inducing stochastic
effects at low doses, the result being the equivalent dose.
i Values are selected to be representative of the relevant relative biologicaleffectiveness and are broadly compatible with the values previously
recommended for quality factors in the definition of dose equivalent. The
radiation weighting factor values10 are:
Type of radiation

wR

Photons

1

Electrons and muons

1

Protons and charged pions

2

Alpha particles, fission fragments,
heavy ions20

Neutrons

A continuous function of neutron energy:

Note: All values relate to radiation incident on the body or, for internal radiation sources,
radiation emitted from the incorporated radionuclide(s).

10INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
The 2007 Recommendations of the International Commission on Radiological Protection,
Publication 103, Elsevier (2007).

411

radioactive (adjective)
1. Exhibiting radioactivity; emitting or relating to the emission of ionizing
radiation or particles.
i This is the ‘scientific’ definition, and should not be confused with the‘regulatory’ definition (2).

2. Designated in national law or by a regulatory body as being subject toregulatory control because of its radioactivity.
i This is the ‘regulatory’ definition, and should not be confused with the‘scientific’ definition (1).

radioactive material
Material designated in national law or by a regulatory body as being subject
to regulatory control because of its radioactivity.
i This is the ‘regulatory’ meaning of radioactive (2), and should not be confusedwith the ‘scientific’ meaning of radioactive (1): ‘exhibiting radioactivity;
emitting or relating to the emission of ionizing radiation or particles’. The‘scientific’ meaning of radioactive — as in radioactive substance — refers
only to the presence of radioactivity, and gives no indication of the magnitudeof the hazard involved.

radioactive source
A source containing radioactive material that is used as a source of radiation.
radioactive substancei This is the ‘scientific’ meaning of radioactive (1), and should not be confusedwith the ‘regulatory’ meaning of radioactive (2): ‘Designated in nationallaw or by a regulatory body as being subject to regulatory control becauseof its radioactivity.’ The ‘scientific’ meaning of radioactive refers only to thepresence of radioactivity, and gives no indication of the magnitude of thehazard involved.

radioactive waste
For legal and regulatory purposes, material for which no further use
is foreseen that contains, or is contaminated with, radionuclides at activity
concentrations greater than clearance levels as established by the regulatory body.
412!

It should be recognized that this definition is purely for regulatory purposes,
and that material with activity concentrations equal to or less than clearance
levels is radioactive from a physical viewpoint, although the associatedradiological hazards are considered negligible.

radioactive waste management
All administrative and operational activities involved in the handling,
pretreatment, treatment, conditioning, transport, storage and disposal ofradioactive waste.
predisposal management of radioactive waste. Any waste management
steps carried out prior to disposal, such as pretreatment, treatment,
conditioning, storage and transport activities.
i Predisposal management is used as a contraction of ‘pre-disposal managementof radioactive waste’; ‘predisposal’ is not a form of disposal.

processing. Any operation that changes the characteristics of waste,
including pretreatment, treatment and conditioning.
radioactive waste management facility
Facility specifically designed to handle, treat, condition, store orpermanently dispose of radioactive waste.
radiological medical practitioner
A health professional with specialist education and training in the medical
uses of radiation, who is competent to perform independently or to oversee
radiological procedures in a given specialty.
i Competence of persons is normally assessed by the State by having a formal
mechanism for registration, accreditation or certification of radiological
medical practitioners in the given specialty (e.g. radiology, radiation therapy,
nuclear medicine, dentistry, cardiology). States that have yet to develop sucha mechanism need to assess the education, training and competence of any
individual proposed by the licensee to act as a radiological medical practitioner
and to decide, on the basis of either international standards or standards of aState where such a system exists, whether such an individual could undertakethe functions of a radiological medical practitioner, within the required
specialty.

413

radiological procedure
A medical imaging procedure or therapeutic procedure that involves ionizing
radiation — such as a procedure in diagnostic radiology, nuclear medicine orradiation therapy, or a planning procedure, image guided interventional procedureor other interventional procedure involving radiation — delivered by a radiation
generator, a device containing a sealed source or an unsealed source, or by meansof a radiopharmaceutical administered to a patient.
radionuclides of natural origin
Radionuclides that occur naturally on Earth in significant quantities.

i The term is usually used to refer to the primordial radionuclides 40K, 235U,
238
U, 232Th and their radioactive decay products.
i Contrasted with radionuclides of artificial origin; also artificial radionuclides,
anthropogenic radionuclides and human-made radionuclides.

radiopharmacist
A health professional, with specialist education and training inradiopharmacy, who is competent to prepare and dispense radiopharmaceuticals
used for the purposes of medical diagnosis and radionuclide therapy.
i Competence of persons is normally assessed by the State by having a formal
mechanism for registration, accreditation or certification of radiopharmacists.
States that have yet to develop such a mechanism need to assess the education,
training and competence of any individual proposed by the licensee to act asa radiopharmacist and to decide, on the basis of either international standards
or standards of a State where such a system exists, whether such an individual
could undertake the functions of a radiopharmacist.

radon
Any combination of isotopes of the element radon.

i For the purposes of these Standards, radon refers to 220Rn and 222Rn.

radon progeny
The short lived radioactive decay products of 220Rn and of 222Rn.

414

i For 222Rn, this includes the decay chain up to but not including 210Pb, namely
218
Po, 214Pb, 214Bi and 214Po, plus traces of 218At, 210Tl and 209Pb. 210Pb, which
has a half-life of 22.3 a, and its radioactive progeny — 210Bi and 210Po, plus
traces of 206Hg and 206Tl — are, strictly, progeny of 222Rn, but they are notincluded in this listing because they will not normally be present in significant
amounts in airborne form. For 220Rn, this includes 216Po, 212Pb, 212Bi, 212Po and208
Tl.

reference level
For an emergency exposure situation or an existing exposure situation, thelevel of dose, risk or activity concentration above which it is not appropriate toplan to allow exposures to occur and below which optimization of protection andsafety would continue to be implemented.
i The value chosen for a reference level will depend upon the prevailingcircumstances for the exposure under consideration.

referring medical practitioner
A health professional who, in accordance with national requirements, may
refer individuals to a radiological medical practitioner for medical exposure.
registrant
The holder of a current registration.
i Other derivative terms should not be needed; a registration is a product of theauthorization process, and a practice with a current registration is an authorizedpractice.

registration
A form of authorization for practices of low or moderate risks whereby
the person or organization responsible for the practice has, as appropriate,
prepared and submitted a safety assessment of the facilities and equipment to theregulatory body. The practice or use is authorized with conditions or limitations
as appropriate.
i The requirements for safety assessment and the conditions or limitations
applied to the practice would be less severe for registration than those forlicensing.

415

i Typical practices that are amenable to registration are those for which:(a) safety can largely be ensured by the design of the facilities and equipment;(b) the operating procedures are simple to follow; (c) the safety training
requirements are minimal; and (d) there is a history of few problems withsafety in operations. Registration is best suited to those practices for which
operations do not vary significantly.

regulatory body
An authority or a system of authorities designated by the government of aState as having legal authority for conducting the regulatory process, including
issuing authorizations, and thereby regulating nuclear, radiation, radioactive
waste and transport safety.
i The national competent authority for the regulation of radioactive materialtransport safety (see IAEA Safety Standards Series No. SSR-611) is included inthis description, as is the regulatory body for protection and safety.

regulatory control
See control.
relative biological effectiveness (RBE)
A relative measure of the effectiveness of different radiation types at
inducing a specified health effect, expressed as the inverse ratio of the absorbed
doses of two different radiation types that would produce the same degree of adefined biological end point.
i Values of relative biological effectiveness in inducing stochastic effects are
represented by the radiation weighting factor wR.
i Values of relative biological effectiveness in inducing deterministic effects
are selected to be representative of the severe deterministic effects that are
significant to emergency preparedness and response. The tissue or organ
specific and radiation specific values of RBET,R for the development of
selected severe deterministic effects are as shown in the table.

11

INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe
Transport of Radioactive Material, 2012 Edition, IAEA Safety Standards Series No. SSR-6,
IAEA, Vienna (2012).

416

Health effectHaematopoietic
syndrome

Pneumonitis

Gastrointestinal
syndrome

Critical tissue or organ

Red marrow

Lungb

Colon

Necrosis

Tissued

Moist desquamation

Skine

Hypothyroidism

Thyroid

a

b
c

d
e
f

Exposurea

RBET,R

External and internal γ

1External and internal n

3Internal β

1Internal α2External and internal γ

1External and internal n

3Internal β

1Internal α

7External and internal γ

1External and internal n

3Internal β

1Internal α0cExternal β, γ1External n3

External β, γ1External n

3Intake of iodine isotopesf

0.2

Other thyroid seekers

1External β, γ exposure includes exposure to bremsstrahlung produced within the material of
the source.
Tissue of the alveolar–interstitial region of the respiratory tract.
For alpha emitters uniformly distributed in the contents of the colon, it is assumed that
irradiation of the walls of the intestine is negligible.
Tissue at a depth of 5 mm below the skin surface over an area of more than 100 cm2.
Tissue at a depth of 0.4 mm below the skin surface over an area of more than 100 cm2.
Uniform irradiation of the tissue of the thyroid gland is considered to be five times more
likely to produce deterministic effects than internal exposure due to low energy beta emitting
isotopes of iodine such as 131I, 129I, 125I, 124I and 123I. Thyroid seeking radionuclides have aheterogeneous distribution in thyroid tissue. The isotope 131I emits low energy beta particles,
which leads to a reduced effectiveness of irradiation of critical thyroid tissue owing to thedissipation of the energy of the particles within other tissues.

417

relative biological effectiveness (RBE) weighted absorbed dose, ADT
The quantity ADT,R, defined as:
AD T,R = DT,R × RBE T,R

where DT,R is the absorbed dose delivered by radiation of type R averaged over atissue or organ T and RBET,R is the relative biological effectiveness for radiationof type R in the production of severe deterministic effects in a tissue or organ T.
When the radiation field is composed of different radiation types with different
values of RBET,R, the RBE weighted absorbed dose is given by:
AD T =∑D

T,R × RBE T,R

R

i The SI unit for RBE weighted absorbed dose is joule per kilogram (J/kg),
termed the gray (Gy).
i RBE weighted absorbed dose is a measure of the dose to a tissue or organ,
intended to reflect the risk of development of severe deterministic effects.
i Values of RBE weighted absorbed dose to a specified tissue or organ from anytype(s) of radiation can be compared directly.

remedial action
The removal of a source or the reduction of its magnitude (in terms ofactivity or amount) for the purposes of preventing or reducing exposures thatmight otherwise occur in an existing exposure situation.
i Remedial actions could also be termed longer term protective action, but
longer term protective actions are not necessarily remedial actions.

remediation
Any measures that may be carried out to reduce the radiation exposuredue to existing contamination of land areas through actions applied to thecontamination itself (the source) or to the exposure pathways to humans.
i Complete removal of the contamination is not implied.

See decontamination.

418

representative person
An individual receiving a dose that is representative of the doses to themore highly exposed individuals in the population.

i The International Commission on Radiological Protection’s Publication 10112
indicates that the dose to the representative person “is the equivalent of, andreplaces, the mean dose in the ‘critical group’”, and provides guidance on
assessing doses to the representative person. The concept of critical groupremains valid.

See member of the public.
residual dose
The dose expected to be incurred after protective actions have been
terminated (or after a decision has been taken not to take protective actions).
i This applies for an existing exposure situation or an emergency exposure
situation.

response organization
An organization designated or otherwise recognized by a State as being
responsible for managing or implementing any aspect of an emergency response.
risk
A multiattribute quantity expressing hazard, danger or chance of harmful or
injurious consequences associated with exposures or potential exposure. It relates
to quantities such as the probability that specific deleterious consequences may
arise and the magnitude and character of such consequences.
See radiation risks.
risk constraint
See constraint.

12

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION,
Assessing Dose of the Representative Person for the Purpose of Radiation Protection of
the Public and the Optimisation of Radiological Protection: Broadening the Process, ICRP
Publication 101, Elsevier (2006).

419

safetySee (nuclear) safety, protection and safety.

i In the Fundamental Safety Principles (Safety Fundamentals)13, the generalized
usage in this particular text of the term ‘safety’ (i.e. to mean protection andsafety) is explained as follows (in paras 3.1 and 3.2):“3.1. For the purposes of this publication, ‘safety’ means the protectionof people and the environment against radiation risks, and the safety offacilities and activities that give rise to radiation risks. ‘Safety’ as used here
and in the IAEA safety standards includes the safety of nuclear installations,radiation safety, the safety of radioactive waste management and safety
in the transport of radioactive material; it does not include non-radiationrelated aspects of safety.
“3.2. Safety is concerned with both radiation risks under normal
circumstances and radiation risks as a consequence of incidents, as well aswith other possible direct consequences of a loss of control over a nuclear
reactor core, nuclear chain reaction, radioactive source or any other sourceof radiation. Safety measures include actions to prevent incidents andarrangements put in place to mitigate their consequences if they were tooccur.”
safety assessment
Assessment of all aspects of a practice that are relevant to protection andsafety; for an authorized facility, this includes siting, design and operation of the
facility.

13

EUROPEAN ATOMIC ENERGY COMMUNITY, INTERNATIONAL ATOMICENERGY AGENCY, FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED
NATIONS, INTERNATIONAL LABOUR ORGANIZATION, INTERNATIONALMARITIME ORGANIZATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICANHEALTH ORGANIZATION, UNITED NATIONS ENVIRONMENT PROGRAMME,WORLD HEALTH ORGANIZATION, Safety Fundamentals: Fundamental Safety Principles,
IAEA Safety Standards Series No. SF-1, IAEA, Vienna (2006).

420

safety culture
The assembly of characteristics and attitudes in organizations andindividuals which establishes that, as an overriding priority, protection and safetyissues receive the attention warranted by their significance.
safety measure
Any action that might be taken, condition that might be applied or procedurethat might be followed to fulfil the requirements of Safety Requirements.
safety standards
Standards issued pursuant to Article III(A)(6)14 of the Statute of the IAEA15.
i IAEA publications issued since 1997 in the IAEA Safety Standards Series aredesignated as Safety Fundamentals, Safety Requirements or Safety Guides.

scenario
A postulated or assumed set of conditions and/or events.
i Most commonly used in analysis or assessment to represent possible future
conditions and/or events to be modelled, such as possible accidents at a nuclear
facility, or the possible future evolution of a repository and its surroundings.
A scenario may represent the conditions at a single point in time or a single
event, or a time history of conditions and/or events (including processes).
i See event.

securitySee (nuclear) security.
somatic effectA radiation induced health effect that occurs in the exposed person.

14“[The Agency is authorized…] To establish or adopt, in consultation and, whereappropriate, in collaboration with the competent organs of the United Nations and with thespecialized agencies concerned, standards of safety for protection of health and minimizationof danger to life and property (including such standards for labour conditions)…”
15
Statute of the International Atomic Energy Agency, IAEA, Vienna (1990).

421

i This includes effects occurring after birth that are attributable to exposure inutero.
i Deterministic effects are normally also somatic effects; stochastic effects may
be somatic effects or hereditary effects.
i Contrasting term: hereditary effect.

source1. Anything that may cause radiation exposure — such as by emitting
ionizing radiation or by releasing radioactive substances or radioactive material— and can be treated as a single entity for purposes of protection and safety.
i For example, materials emitting radon are sources in the environment; asterilization gamma irradiation unit is a source for the practice of irradiation
preservation of food and sterilization of other products; an X ray unit may be
a source for the practice of radiodiagnosis; a nuclear power plant is part of thepractice of generating electricity by nuclear fission, and may be regarded as asource (e.g. with respect to discharges to the environment) or as a collectionof sources (e.g. for occupational radiation protection purposes). A complex
or multiple installation situated at one location or site may, as appropriate,
be considered a single source for the purposes of application of the safety
standards.

natural source. A naturally occurring source of radiation, such as the
sun and stars (sources of cosmic radiation) and rocks and soil (terrestrial
sources of radiation), or any other material whose radioactivity is for all
intents and purposes due only to radionuclides of natural origin, suchas products or residues from the processing of minerals; but excluding
radioactive material for use in a nuclear installation and radioactive waste
generated in a nuclear installation.
radiation generator. A device capable of generating ionizing radiation,such as X rays, neutrons, electrons or other charged particles, that may be
used for scientific, industrial or medical purposes.
2. Radioactive material used as a source of radiation.
i Such as those sources used for medical applications or in industrial
instruments. These are, of course, sources as defined in (1), but this usage in(2) is less general.

dangerous source. A source that could, if not under control, give rise toexposure sufficient to cause severe deterministic effects. This categorization422

is used for determining the need for emergency arrangements and is not tobe confused with categorizations of sources for other purposes.
i The term ‘dangerous source’ relates to dangerous quantities (D values) as
recommended in Dangerous Quantities of Radioactive Material (D-Values),
Emergency Preparedness and Response, EPR-D-VALUES 200616.

radioactive source. A source containing radioactive material that is used asa source of radiation.
sealed source. A radioactive source in which the radioactive material is(a) permanently sealed in a capsule, or (b) closely bonded and in a solid
form.
spent source. A source that is no longer suitable for its intended purpose asa result of radioactive decay.
!

Note that a spent source may still represent a radiological hazard.

unsealed source. A radioactive source in which the radioactive material isneither (a) permanently sealed in a capsule nor (b) closely bonded and in asolid form.
source monitoring
The measurement of activity in radioactive material being released to theenvironment or of external dose rates due to sources within a facility or activity.
i Contrasted with environmental monitoring.

spent fuelNuclear fuel removed from a reactor following irradiation that is no longer
usable in its present form because of depletion of fissile material, poison buildup
or radiation damage.

16

INTERNATIONAL ATOMIC ENERGY AGENCY, Dangerous Quantities ofRadioactive Material (D-Values), Emergency Preparedness and Response, EPR-D-VALUES,
IAEA, Vienna (2006).

423

i The adjective ‘spent’ suggests that spent fuel cannot be used as fuel in its
present form (e.g. as in spent source). In practice, however, spent fuel iscommonly used to refer to fuel that has been used as fuel but will no longer
be used, whether or not it could be used (and that might more accurately betermed ‘disused fuel’).

standards dosimetry laboratory
A laboratory, designated by the relevant national authority, that possesses
certification or accreditation necessary for the purpose of developing, maintaining
or improving primary or secondary standards for radiation dosimetry.
stochastic effectA radiation induced health effect, the probability of occurrence of whichis greater for a higher radiation dose and the severity of which (if it occurs) is
independent of dose.
i Stochastic effects may be somatic effects or hereditary effects, and generally
occur without a threshold level of dose. Examples include solid cancers andleukaemia.
i Contrasting term: deterministic effect.

storage
The holding of radioactive sources, radioactive material, spent fuel orradioactive waste in a facility that provides for their/its containment, with theintention of retrieval.
structures, systems and components
A general term encompassing all of the elements (items) of a facility or
activity that contribute to protection and safety, except human factors.
i Structures are the passive elements: buildings, vessels, shielding, etc. A
system comprises several components, assembled in such a way as to performa specific (active) function. A component is a discrete element of a system.
Examples of components are wires, transistors, integrated circuits, motors,
relays, solenoids, pipes, fittings, pumps, tanks and valves.
i Human factors may be reflected in structures, systems and components inso far as ergonomics — the study of people’s efficiency in their working
environment — is an element in their design.

424supervised area
A defined area not designated as a controlled area but for which
occupational exposure conditions are kept under review, even though specificprotection measures or safety provisions are not normally needed.
supplier (of a source)
Any person or organization to whom a registrant or licensee assigns
duties, totally or partially, in relation to the design, manufacture, production orconstruction of a source.
i The term ‘supplier’ of a source includes designers, manufacturers, producers,
constructors, assemblers, installers, distributors, sellers, importers andexporters of a source.

tissue weighting factor, wT
Multiplier of the equivalent dose to a tissue or organ used for purposes ofradiation protection to account for the different sensitivities of different tissues ororgans to the induction of stochastic effects of radiation.
i Tissue weighting factors used for calculating effective dose are as follows.

Tissue or organwT∑w

Bone marrow (red), colon, lung, stomach, breast, remainder tissuesa

0.12

0.72

Gonads0.08

0.08

Bladder, oesophagus, liver, thyroid

0.04

0.16

Bone surface, brain, salivary glands, skin

0.01

0.04

Total

1.00

a

T

The wT for remainder tissues (0.12) applies to the arithmetic mean dose to these 13 tissues
and organs for each sex: adrenals, extrathoracic region, gall bladder, heart, kidneys,
lymphatic nodes, muscle, oral mucosa, pancreas, prostate (male), small intestine, spleen,
thymus, uterus/cervix (female).

425transboundary exposure
Exposure of members of the public in one State due to radioactive material
released via accidents, discharges or waste disposal in another State.
transport
The deliberate physical movement of radioactive material (other than that
forming part of the means of propulsion) from one place to another.
urgent protective action
See protective action.
workerAny person who works, whether full time, part time or temporarily, for an
employer and who has recognized rights and duties in relation to occupationalradiation protection.
i A self-employed person is regarded as having the duties of both an employer
and a worker.

workers’ health surveillance
Medical supervision intended to ensure the initial and continuing fitness ofworkers for their intended tasks.
workplace monitoring
Monitoring using measurements made in the working environment.
i Usually contrasted with individual monitoring.

426

CONTRIBUTORS TO DRAFTING AND REVIEW
Abu-Eid, R.

Nuclear Regulatory Commission,
United States of America

Ahier, B.

OECD Nuclear Energy Agency

Akhadi, M.

National Nuclear Energy Agency, Indonesia

Al-Arfaj, A.

Institute of Atomic Energy Research, Saudi Arabia

Ali, H.

Atomic Licensing Board, Malaysia

Ali, M.

Pakistan Nuclear Regulatory Authority, Pakistan

Amaral, E.

International Atomic Energy Agency

Amor Calvo, I.

Nuclear Safety Council, Spain

Ampuero Flores, C.

Peruvian Institute of Nuclear Energy, Peru

Andersen, R.

World Nuclear Association

Arvela, H.

Radiation and Nuclear Safety Authority, Finland

Awatsuji, Y.

Ministry of Education, Culture, Sports, Science andTechnology, JapanBåckström, T.

Swedish Radiation Protection Authority, Sweden

Badulin, V.

Ministry of Health, Bulgaria

Baeklandt, L.

Federal Agency for Nuclear Control, Belgium

Basurto Cázares, J.

National Commission for Nuclear Safety and
Safeguards, Mexico

Berkovskyy, V.

International Atomic Energy Agency

Boal, T.

International Atomic Energy Agency

Bochichhio, F.

Higher Institute of Health, Italy

Bologna, L.

APAT, Italy

Borras, C.

Consultant, Radiological Physics and Health Services,
United States of America

427

Böttger, A.

Federal Ministry for the Environment, Nature
Conservation and Nuclear Safety, Germany

Bourguignon, M.

World Health Organization

Brewer, S.

Atomic Energy of Canada Limited, Canada

Buglova, E.

International Atomic Energy Agency

Bundy, K.

Canadian Nuclear Safety Commission, Canada

Burns, P.

Australian Radiation Protection and Nuclear Safety
Agency, Australia

Byron, D.

Food and Agriculture Organization of
the United Nations

Cabral Molina, W.

Ministry of Industry, Energy and Mining, Uruguay

Calamosca, M.

Institute for Radiation Protection, Italy

Cancio, D.

Unidad de Protección Radiológica, Spain

Canoba, A.

Nuclear Regulatory Authority, Argentina

Carboneras Martinez, P.

National Company for Radioactive Waste, Spain

Carr, Z.

World Health Organization

Cernohlavek, N.

Austrian Agency for Health and Food Safety, Austria

Chambers, D.

SENES Consultants Limited, Canada

Charette, M.

International Source Suppliers and Producers
Association

Cherf, A.

International Atomic Energy Agency

Cheung, K.

International Organization for Medical Physics

Chi, C.

China Institute for Radiation Protection, China

Cho, K.

Korea Institute of Nuclear Safety, Republic of Korea

Christofides, S.

International Organization for Medical Physics

Clement, C.

International Commission on Radiological Protection

Colgan, T.

International Atomic Energy Agency

Cool, D.

Nuclear Regulatory Commission,
United States of America

Cooper, J.

Health Protection Agency, United Kingdom

Coppee, G.

International Labour Organization

Crick, M.

United Nations Scientific Committee on the Effects ofAtomic Radiation

Cripwell, B.

International Labour Organization

Cruz-Suarez, R.

International Atomic Energy Agency

Currivan, L.

Radiological Protection Institute of Ireland, Ireland

Czarwinski, R.

International Atomic Energy Agency

de la Fuenta Puch, A.

National Nuclear Safety Centre, Cuba

Deboodt, P.

International Atomic Energy Agency

Delattre, D.

International Atomic Energy Agency

Delves, D.

International Atomic Energy Agency

Dimitriou, P.

Greek Atomic Energy Commission, Greece

Ditto, M.

Federal Ministry for Health and Women, Austria

Ebdon-Jackson, S.

Health Protection Agency, United Kingdom

Fenton, D.

Radiological Protection Institute of Ireland, IrelandFischer, H.

Federal Ministry of Agriculture, Forestry,
Environment and Water Management, Austria

Frullani, S.

Higher Institute of Health, Italy

Fujii, K.

Ministry of Education, Culture, Sports, Science andTechnology, Japan

Fundarek, P.

Canadian Nuclear Safety Commission, Canada

Garcia-Talavera, M.

Nuclear Safety Council, Spain

Garcier, Y.

World Nuclear Association

429

Gaunt, M.

International Labour Organization, International
Organization of Employers

Ghovanlou, A.

Health and Physics Safety, United States of America

Gilley, N.

Florida Department of Health Bureau of Radiation
Control, United States of America

Gomaa, M.

Atomic Energy Authority, Egypt

Gonzalez, A.

Nuclear Regulatory Authority, Argentina

Griebel, J.

Federal Office for Radiation Protection, Germany

Groth, S.

World Health Organization

Gruson, M.

Federal Office of Public Health, Switzerland

Guven, M.

Turkish Atomic Energy Authority, Turkey

Hamani, W.

National Centre for Nuclear Science andTechnology, Tunisia

Hammer, J.

Swiss Federal Nuclear Safety Inspectorate,
Switzerland

Hanninen, R.

Radiation and Nuclear Safety Authority, Finland

Hattori, T.

Central Research Institute of Electric Power Industry,Japan

Havukainen, R.

Radiation and Nuclear Safety Authority, Finland

Hedemann, P.

Danish Decommissioning, Denmark

Helming, M.

Federal Ministry for the Environment, Nature
Conservation and Nuclear Safety, Germany

Hesse, J.

World Nuclear Association

Hoffmann, B.

Federal Office for Radiation Protection, Germany

Homma, T.

Japan Atomic Energy Agency, Japan

Huffman, D.

AREVA Resources Canada Inc., Canada

Hugron, R.

National Defence Headquarters, Canada

430

Hulka, J.

SÚRO National Radiation Protection Institute,
Czech Republic

Hunt, J.

International Atomic Energy Agency

Iimoto, T.

University of Tokyo, Japan

Inokuchi, T.

Nuclear Safety Commission, Japan

Ishikawa, N.

Nuclear Safety Commission, Japan

Ito, K.

Japan Atomic Energy Agency, Japan

Janssens, A.

European Commission

Janzekovic, H.

Slovenian Nuclear Safety Administration, Slovenia

Jensen, L.

National Institute of Radiation Protection, Denmark

Jerachanchai, S.

Office of Atoms for Peace, Thailand

Jimenez, P.

Pan American Health Organization

Jones, G.

International Atomic Energy Agency

Jung, T.

Federal Office for Radiation Protection, Germany

Jurina, V.

Public Health Authority, Slovakia

Kamenopoulou, V.

Greek Atomic Energy Commission, Greece

Kardan, M.

Atomic Energy Organization of Iran,
Islamic Republic of Iran

Kelly, N.

Consultant, United Kingdom

Kenigsberg, J.

National Commission of Radiation Protection, Belarus

Kirchner, G.

Federal Office for Radiation Protection, Germany

Koblinger, L.

Hungarian Atomic Energy Authority, Hungary

Koc, J.

Temelin Nuclear Power Plant, Czech RepublicKoch, J.

Soreq Nuclear Research Center, Israel

Kolovou, M.

Greek Atomic Energy Commission, Greece

Kralik, I.

State Office for Radiation Protection, Croatia

431

Krca, S.

State Office for Radiation Protection, Croatia

Kuhlen, J.

Federal Ministry for the Environment, Nature
Conservation and Nuclear Safety, Germany

Kulich, V.

Dukovany Nuclear Power Plant, Czech Republic

Kutkov, V.

Russian Research Centre “Kurchatov Institute”,
Russian Federation

Landfermann, H.

Federal Ministry for the Environment, Nature
Conservation and Nuclear Safety, Germany

Larsson, C.

Swedish Radiation Protection Authority, Sweden

Lazo, E.

OECD Nuclear Energy Agency

Le Guen, B.

World Nuclear Association

Le Heron, J.

International Atomic Energy Agency

Lecomte, J.-F.

Institute for Radiological Protection and Nuclear
Safety, France

Lindvall, C.

Barsebäck Kraft AB, Sweden

Lipsztein, J.

Institute of Radiation Protection and Dosimetry, Brazil

Long, K.

Food and Agriculture Organization of
the United Nations

Long, W.

Center for Radon and Air Toxics,
United States of America

Lopes Gonzalez, F.

Universidad Nacional Autonoma de Nicaragua,
Nicaragua

Lorenz, B.

World Nuclear Association

Louvat, D.

International Atomic Energy Agency

Lund, I.

Swedish Radiation Protection Authority, Sweden

Magnusson, S.

Icelandic Radiation Protection Institute, Iceland

Makarovska, O.

State Nuclear Regulatory Committee, Ukraine

Mansoux, H.

International Atomic Energy Agency

432

Marechal, N.

Commissão Nacional de Energia Nuclear, Brazil

Marengo, M.

World Federation of Nuclear Medicine and Biology

Maringer, F.

Low-level Counting Laboratory Arsenal, Austria

Markkanen, M.

Radiation and Nuclear Safety Authority, Finland

Martin Calvarro, J.

Nuclear Safety Council, Spain

Martincic, R.

International Atomic Energy Agency

Mason, C.

International Atomic Energy Agency

Massera, G.

Nuclear Regulatory Authority, Argentina

Mayya, Y.

Bhabha Atomic Research Centre, India

McClelland, V.

Department of Energy, United States of America

McKenna, T.

International Atomic Energy Agency

McLaughlin, J.

University College Dublin, Ireland

Meghzifene, A.

International Atomic Energy Agency

Merta, A.

National Atomic Energy Agency, Poland

Metcalf, P.

International Atomic Energy Agency

Mirsaidov, U.

Nuclear and Radiation Safety Agency, Tajikistan

Miyazaki, S.

Kansai Electric Power Co. Inc., Japan

Mizumachi, W.

Japan Nuclear Energy Safety Organization, Japan

Mokrani, Z.

Nuclear Research Centre, Algeria

Mrabit, K.

International Atomic Energy Agency

Mundigl, S.

European Commission

Naegele, J.

European Commission

Nandakumar, A.

International Atomic Energy Agency

Niu, S.

International Labour Organization

Owen, D.

International Labour Organization

433

Parkes, R.

Health and Safety Executive, United Kingdom

Pather, T.

National Nuclear Regulator, South Africa

Paynter, R.

Health Protection Agency, United Kingdom

Peñalosa, A.

International Organization of Employers

Perez, M.

World Health Organization

Perrin, M.

French Nuclear Safety Authority, France

Petrova, K.

State Office for Nuclear Safety, Czech Republic

Philpott, L.

Health and Safety Executive, United Kingdom

Pinak, M.

OECD Nuclear Energy Agency

Poffijn, A.

Federal Agency for Nuclear Control, Belgium

Purvis, C.

Canadian Nuclear Safety Commission, Canada

Radolic, V.

University Josip Juraj Strossmayer, Croatia

Rannou, A.

Institute for Radiological Protection and Nuclear
Safety, France

Rehani, M.

International Atomic Energy Agency

Ringertz, H.

International Society of Radiology

Robinson, I.

Health and Safety Executive, United Kingdom

Rochedo, E.

Institute of Radiation Protection and Dosimetry, Brazil

Rotaru, I.

National Commission for Nuclear Activities Control,
Romania

Rudjord, A.

Norwegian Radiation Protection Authority, Norway

Runova, J.

Scientific and Engineering Centre for Nuclear andRadiation Safety, Russian Federation

Ryder, G.

International Trade Union Confederation, Belgium

Saint-Pierre, S.

World Nuclear Association, United Kingdom

Sallit, G.

Department for Transport, United Kingdom434

Salomon, S.

Australian Radiation Protection and Nuclear Safety
Agency, Australia

Sanz Alduan, M.

Nuclear Safety Council, Spain

Schmitt-Hannig, A.

Federal Office for Radiation Protection, Germany

Sefzig, R.

Federal Ministry for the Environment, Nature
Conservation and Nuclear Safety, Germany

Shannoun, F.

World Health Organization

Simeonov, G.

European Commission

Sinaga, M.

Nuclear Energy Regulatory Agency, Indonesia

Stasiunaitiene, R.

Ministry of Health, Lithuania

Stephen, P.

Nuclear Directorate, United Kingdom

Stern, W.

International Atomic Energy Agency

Storrie, R.

International Source Suppliers and Producers
Association

Sugier, A.

Institute for Radiological Protection and Nuclear
Safety, France

Suman, H.

International Atomic Energy Agency

Sutej, T.

Ministry of Health, Romania

Svensson, H.

International Organization for Medical Physics

Syahrir, S.

National Nuclear Energy Agency, Indonesia

Telleria, D.

International Atomic Energy Agency

Thomas, G.

Health and Safety Executive, United Kingdom

Tirmarche, M.

Institute for Radiological Protection and Nuclear
Safety, France

Todorov, N.

Bulgarian Nuclear Regulatory Agency, Bulgaria

Tokonami, S.

National Institute of Radiological Sciences, Japan

435

Tomasek, L.

SÚRO National Radiation Protection Institute,
Czech Republic

Tonhauser, W.

International Atomic Energy Agency

Ugleveit, F.

Norwegian Radiation Protection Authority, Norway

Valentin, J.

International Commission on Radiological Protection

Van der Steen, J.

Nuclear Research & Consultancy Group, Netherlands

Viktorsson, C.

International Atomic Energy Agency

Wambersie, A.

International Commission on Radiation Units,
Belgium

Wangler, M.

International Atomic Energy Agency

Weiss, W.

Federal Office for Radiation Protection, Germany

Wheatley, J.

International Atomic Energy Agency

Wiklund, A.

European Commission

Wirth, E.

Federal Office for Radiation Protection, Germany

Wood, P.

International Society of Radiographers andRadiological Technologists

Wrixon, A.

International Atomic Energy Agency

Wymer, D.

International Atomic Energy Agency

Xiao, X.

China Institute of Atomic Energy, China

Yonehara, H.

National Institute of Radiological Sciences, Japan

Zafmanjato, J.

Ministère de l’éducation national et de la recherche
scientifique, Madagascar

Zeeb, H.

World Health Organization

Zodiates, T.

International Labour Organization, International Trade
Union Confederation

Zuur, C.

Ministry of Housing, Spatial Planning andEnvironment, Netherlands

436

@

No. 23ORDERING LOCALLY
In the following countries, IAEA priced publications may be purchased from the sources listed below orfrom major local booksellers.
Orders for unpriced publications should be made directly to the IAEA. The contact details are given at
the end of this list.
AUSTRALIADA Information Services
648 Whitehorse Road, Mitcham, VIC 3132, AUSTRALIA
Telephone: +61 3 9210 7777 y Fax: +61 3 9210 7788
Email: books@dadirect.com.au y Web site: http://www.dadirect.com.au

BELGIUM

Jean de Lannoy
Avenue du Roi 202, 1190 Brussels, BELGIUM
Telephone: +32 2 5384 308 y Fax: +32 2 5380 841
Email: jean.de.lannoy@euronet.be y Web site: http://www.jean-de-lannoy.be

CANADA

Renouf Publishing Co. Ltd.
5369 Canotek Road, Ottawa, ON K1J 9J3, CANADA
Telephone: +1 613 745 2665 y Fax: +1 643 745 7660
Email: order@renoufbooks.com y Web site: http://www.renoufbooks.com
Bernan Associates
4501 Forbes Blvd., Suite 200, Lanham, MD 20706-4391, USA
Telephone: +1 800 865 3457 y Fax: +1 800 865 3450
Email: orders@bernan.com y Web site: http://www.bernan.com

CZECH REPUBLIC

Suweco CZ, spol. S.r.o.
Klecakova 347, 180 21 Prague 9, CZECH REPUBLIC
Telephone: +420 242 459 202 y Fax: +420 242 459 203
Email: nakup@suweco.cz y Web site: http://www.suweco.cz

FINLAND

Akateeminen Kirjakauppa
PO Box 128 (Keskuskatu 1), 00101 Helsinki, FINLAND
Telephone: +358 9 121 41 y Fax: +358 9 121 4450
Email: akatilaus@akateeminen.com y Web site: http://www.akateeminen.com

FRANCE

Form-Edit
5 rue Janssen, PO Box 25, 75921 Paris CEDEX, FRANCE
Telephone: +33 1 42 01 49 49 y Fax: +33 1 42 01 90 90
Email: fabien.boucard@formedit.fr y Web site: http://www.formedit.fr
Lavoisier SAS
14 rue de Provigny, 94236 Cachan CEDEX, FRANCE
Telephone: +33 1 47 40 67 00 y Fax: +33 1 47 40 67 02
Email: livres@lavoisier.fr y Web site: http://www.lavoisier.fr
L’Appel du livre
99 rue de Charonne, 75011 Paris, FRANCE
Telephone: +33 1 43 07 50 80 y Fax: +33 1 43 07 50 80
Email: livres@appeldulivre.fr y Web site: http://www.appeldulivre.fr

GERMANY

Goethe Buchhandlung Teubig GmbH
Schweitzer Fachinformationen
Willstätterstrasse 15, 40549 Düsseldorf, GERMANY
Telephone: +49 (0) 211 49 8740 y Fax: +49 (0) 211 49 87428
Email: s.dehaan@schweitzer-online.de y Web site: http://www.goethebuch.de

HUNGARY

Librotade Ltd., Book Import
PF 126, 1656 Budapest, HUNGARY
Telephone: +36 1 257 7777 y Fax: +36 1 257 7472
Email: books@librotade.hu y Web site: http://www.librotade.hu

INDIA

Allied Publishers
1st Floor, Dubash House, 15, J.N. Heredi Marg, Ballard Estate, Mumbai 400001, INDIA
Telephone: +91 22 2261 7926/27 y Fax: +91 22 2261 7928
Email: alliedpl@vsnl.com y Web site: http://www.alliedpublishers.com
Bookwell
3/79 Nirankari, Delhi 110009, INDIA
Telephone: +91 11 2760 1283/4536
Email: bkwell@nde.vsnl.net.in y Web site: http://www.bookwellindia.com

ITALY

Libreria Scientifica “AEIOU”
Via Vincenzo Maria Coronelli 6, 20146 Milan, ITALY
Telephone: +39 02 48 95 45 52 y Fax: +39 02 48 95 45 48
Email: info@libreriaaeiou.eu y Web site: http://www.libreriaaeiou.eu

JAPANMaruzen Co., Ltd.
1-9-18 Kaigan, Minato-ku, Tokyo 105-0022, JAPAN
Telephone: +81 3 6367 6047 y Fax: +81 3 6367 6160
Email: journal@maruzen.co.jp y Web site: http://maruzen.co.jp

NETHERLANDS

Martinus Nijhoff International
Koraalrood 50, Postbus 1853, 2700 CZ Zoetermeer, NETHERLANDS
Telephone: +31 793 684 400 y Fax: +31 793 615 698
Email: info@nijhoff.nl y Web site: http://www.nijhoff.nl
Swets Information Services Ltd.
PO Box 26, 2300 AA Leiden
Dellaertweg 9b, 2316 WZ Leiden, NETHERLANDS
Telephone: +31 88 4679 387 y Fax: +31 88 4679 388
Email: tbeysens@nl.swets.com y Web site: http://www.swets.com

SLOVENIA

Cankarjeva Zalozba dd
Kopitarjeva 2, 1515 Ljubljana, SLOVENIA
Telephone: +386 1 432 31 44 y Fax: +386 1 230 14 35
Email: import.books@cankarjeva-z.si y Web site: http://www.mladinska.com/cankarjeva_zalozba

SPAIN

Diaz de Santos, S.A.
Librerias Bookshop y Departamento de pedidos
Calle Albasanz 2, esquina Hermanos Garcia Noblejas 21, 28037 Madrid, SPAIN
Telephone: +34 917 43 48 90 y Fax: +34 917 43 4023
Email: compras@diazdesantos.es y Web site: http://www.diazdesantos.es

UNITED KINGDOMThe Stationery Office Ltd. (TSO)
PO Box 29, Norwich, Norfolk, NR3 1PD, UNITED KINGDOM
Telephone: +44 870 600 5552
Email (orders): books.orders@tso.co.uk y (enquiries): book.enquiries@tso.co.uk y Web site: http://www.tso.co.uk

UNITED STATES OF AMERICA

Bernan Associates
4501 Forbes Blvd., Suite 200, Lanham, MD 20706-4391, USA
Telephone: +1 800 865 3457 y Fax: +1 800 865 3450
Email: orders@bernan.com y Web site: http://www.bernan.com
Renouf Publishing Co. Ltd.
812 Proctor Avenue, Ogdensburg, NY 13669, USA
Telephone: +1 888 551 7470 y Fax: +1 888 551 7471
Email: orders@renoufbooks.com y Web site: http://www.renoufbooks.com

United Nations

300 East 42nd Street, IN-919J, New York, NY 1001, USA
Telephone: +1 212 963 8302 y Fax: 1 212 963 3489
Email: publications@un.org y Web site: http://www.unp.un.org

Orders for both priced and unpriced publications may be addressed directly to:
IAEA Publishing Section, Marketing and Sales Unit, International Atomic Energy Agency
Vienna International Centre, PO Box 100, 1400 Vienna, Austria
Telephone: +43 1 2600 22529 or 22488 • Fax: +43 1 2600 29302
Email: sales.publications@iaea.org • Web site: http://www.iaea.org/books

12-45001

Safety through international standards

Yukiya Amano
Director General

INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA
ISBN 978–92–0–135310–8
ISSN 1020–525X

Untitled-1 4
12-45001_PUB1578_cover.indd 1-3

2014-07-22 14:18:34

IAEA Safety Standards Series No. GSR Part 3“Governments, regulatory bodies and operators everywhere mustensure that nuclear material and radiation sources are usedbeneficially, safely and ethically. The IAEA safety standards aredesigned to facilitate this, and I encourage all Member States tomake use of them.”