Communication from the Commission concerning the implementation of Council Directive 96/29/Euratom of 13 May 1996 laying down basic safety standards for the protection of the health of the workers and the general public against the dangers arising from ionising radiation
Date: 1998-02-23
Institutions: European Commission
Subjects: health control, health legislation, ionising radiation, public health, radiation protection

COMMISSION OF THE EUROPEAN COMMUNITIES 

Brussels, 23.02.1998 
COM(1998) 87  final 

Communication from the Commission concerning the implementation of Council 

Directive 96/29/Euratom of 13 May 1996 laying down basic safety standards for the 

protection of the health of the workers and the general public against the dangers 

arising from ionising radiation 

iti 

m 

Communication from the Commission concerning the implementation of Council 

Directive 96/29/Euratom of 13 May 1996 laying down basic safety standards for the 

protection of the health of the workers and the general public against the dangers 

arising from ionising radiation 

For  the  purposes  of  implementing  Council  Directive  96/29/Euratom  of  13 May  1996  laying 
down  basic  safety  standards  for  the  protection  of  the  health  of  the  workers  and  the  general 
public  against  the dangers  arising from ionising  radiation1, the  Commission,  having  consulted 
the  group  of  scientific  experts  referred  to  in  Article  31  of  the  Euratom  Treaty,  wishes  to 
communicate the following  information: 

I.  General Remarks 

The purpose  of this communication  is to assist  the Member  States  in transposing  into  national 
law  Council  Directive  96/29/Euratom  of  13 May  1996 laying down  basic  safety  standards  for 
the protection  of the  health  of  the  workers  and  the  general  public  against  the  dangers  arising 
from  ionising radiation, hereinafter  called the Directive. The Directive repeals, with effect  from 
13 May 2000, the previously established Basic Safety Standards Directives2. 

It  should  be  regarded  as  a  reference  document  since  Member  States  are  bound  only  by  the 
provisions of the Directive. 

Exposure  to  ionising  radiation  can  lead  to  detrimental  health  effects  in  human  beings.  The 
Directive  sets  out requirements  designed  for  the protection  of  workers  and  the  general  public 
against  the  dangers  of  ionising  radiation  without  unduly  limiting  the  beneficial  uses  of  the 
practices giving rise to radiation exposure.  The Commission recognises that all those concerned 
with  radiation  protection  have  to  make  value  judgements  about  the  relative  importance  of 
different  kinds of risks and about the balancing of risks and benefits. 

The  European  Community  is  required  by  Article 30  of  the  Treaty  establishing  the  European 
Atomic Energy  Community  to lay down basic standards for the protection  of  workers and  the 
general  public against  the dangers of ionising radiation.  These standards  have  been  laid  down 
in the form of Council Directives. 

OJ No LI 59,29.6.1996, p. 1. 
Notably  Directive 80/836/Euratom (OJ No L 246,  17.9.1980, p.l.) as amended by 
Directive 84/467/Euratom (OJ No L 265, 5.10.1984, p.4.) 

1 

Those  Directives  have  always  made  use  of  the  recommendations  of  the  Internationa? 
Commission on Radiological Protection (ICRP) and the International Commission on Radiation 
Units and Measurements  (ÏCRU).  Those organisations  are internationally  recognised  for  their 
assessments of the state of the art in their respective fields. 

The  ICRP  publication  on  which  the  1996  Directive  is  based  is  ICRP  Publication  Nc  60  that 
contains  the  latest  general  recommendations  issued  by  the  ICRP  to  take  account  of 
the 
in  scientific  knowledge  and  administrative  experience.  This 
continuing  development 
development has been of an evolutionary nature and it did not fundamentally  change the system 
of protection recommended  by ICRP Publication N° 26 on which the  1980/1984 Directive was 
based. 

Until  1984  the  Basic  Safety  Standards  Directive  has  been  the  only  instrument  of  derived 
legislation based on Article 31 of the Euratom Treaty.  Since then, although it remained  together 
with  the  Euratom  Treaty  itself,  the  central  element  of  the  European  Community  radiation 
protection system, it has been supplemented by a number of specific  legal instruments3. 

The  Directive does not affect  genera! obligations  relating  to the protection  of  those  at  work  as 
given  for  example  in  Directive  89/391/EEC  on  the  introduction  of  measures  to  encourage 
improvements  in  the  safety  and  health  of  workers  at work4.  In the case  of  mutually  exclusive 
dispositions the Euratom Directive is given priority over EC Directives5 

-  Council Decision 87/600/Euratom  of  14 December  1987 on Community  arrangements 

for the early exchange of information  in the event of a radiological  emergency 
OJ  No L 371, 30.12.1987, p. 76 

-  Council Regulation (Euratom) No 3954/87 of 22 December  1987 laying down 
maximum permitted levels of radioactive contamination of foodstuffs  and of 
feedingstuffs  following  a nuclear accident or any other case of radiological  emergency 
OJ No L 371, 30.12.1987, p.  11.  Regulation as amended by Regulation  (Euratom) 
No 2218/89 (OJ No L 211, 22.7.1989, p. 19) 

-  Council Directive 89/618/Euratom of 27 November  1989 on informing  the general 
public about health protection measures to be applied and steps to be taken in the 
event of a radiological  emergency 
OJ No L 357, 7.12.1989, p. 31 

-  Council Directive 90/641/Euratom of 4 December  1990 on the operational  protection 
of outside workers exposed to the risk of ionizing radiation during their activities in 
controlled areas 
OJNoL349,  13.12.1990, p. 21 

-  Council Directive 92/3/Eurtom of 3 February  1992 on the supervision and control of 

shipments of radioactive waste between Member States and into and out of the 
Community 
OJ No L 35, 12.2.1992, p. 24 

-  Council Regulation  (Euratom) No  1493/93 of 8 June  1993 on shipments of 

radioactive substances between  Member States 
OJNoL  148, 19.6.1993, p.  1 

-  Council  Directive 97/43/Euratom  of 30 June  1997 on health protection of  individuals 

against the dangers of ionizing radiation  in relation to medical exposures, and 
repealing Directive  84/466/Euratom 
OJ No L 180, 9.7.1997, p. 22 

OJNoL  183,29.6.1989, p. 1. 
See Article 232 (2) EC Treaty. 

2 

One  of  the  major  new  features  of  the  Directive  is  the  distinction  between  practices  and 
interventions.  Practices  relate  to  those  human  activities  that  can  increase  radiation  exposure; 
interventions are those human activities that prevent or decrease radiation exposure. Other new 
features  are  the  increased  recognition  of  the  fact  that  some  exposures  due  to  work  activities 
involving  natural  radiation  sources  are significant  enough to warrant  attention, the use of dose 
constraints  in optimisation  of protection, the concepts  of clearance  and of potential  exposures. 
The development  of scientific  knowledge led to new concepts  and quantities  in dosimetry  and 
radiation protection.  It also  led to lower dose limits, to redefined  values  for  the application  of 
the  requirements  on  reporting  and  authorisation  of  practices  and  to  new  parameters  for  the 
estimation  of  doses  from  external  radiation,  notably  from  neutrons,  and  from  intakes  of 
radionuclides. 

II.  Comments on some Articles of the Directive6 

a)  TITLE I 

Definitions 

Article 1 

The definitions  relate to terms used in the Directive. Further definitions  are given in Annex II. 
Where  necessary,  guidance  on  their  interpretation  is  given  below  in  the  comments  on  the 
articles in question: 

i) 

'Accidental exposure' is no longer limited to exposures whereby one of the dose limits laid 
down for exposed workers is exceeded. 

ii) 

'Emergency exposure1 should  not  be  confused  with  'Specially authorised exposures', an 
emergency exposure is the exposure of a volunteer actively implementing urgent protective 
actions (Article 52).  A specially authorised exposure is the carefully  planned exposure of a 
category A  worker  who  should  be  a  volunteer  for  carrying  out  specific  operations  in 
exceptional circumstances (Article 12) 

iii)  'Equivalent  dose'  and  'Effective  dose'.  The  Directive  uses  the  protection  quantities 
recommended  by  ICRP  Publication  N° 60.  They  replace  the  previous  quantities  "Dose 
equivalent"  and  "Effective  dose (equivalent)".  It is noted  that the ICRP recommends that 
"it is appropriate to treat as additive the weighted quantities used by the ICRP but assessed 
at different  times, despite the use of different  values of weighting  factors.  The ICRP does 
not recommend  that any attempt be made to correct earlier values. It is also appropriate to 
add values of dose equivalent to equivalent dose and values of effective  dose equivalent to 
effective  dose without any  adjustment". 

iv)  The newly introduced concept of 'Health detriment' includes the probability of fatal  cancer, 

of severe hereditary effects, of non-fatal  cancer and the relative length of life lost. 

v) 

'Qualified expert'.  Advice on basic and additional training for qualified  experts is given in 
Annex I of this communication. 

6  Articles referred  to in this Communication are those of Council  Directive  96/29/Euratom 

of  13 May  1996. 

vi) ' Undertaking.  The  obligations  set  out  in  Title  VI  for  the  protection  of  exposed 
workers and related to requirements for working areas are linked to the undertaking  who 
has  the  legal  responsibility  for  the  practice.  In  a  given  working  area  more  than  one 
In  this  context  it 
practice  can  be  carried  out  by  various  undertakings  or  employers. 
should  be  noted  that  the  Directive  does  not  affect  employers'  obligations  required  by 
Council  Directive  89/391/EEC  of  12 June  1989  on  the  introduction  of  measures  to 
encourage improvements in the safety and health of workers at work7. 

b)  TITLE II 

Scope 

Article 2 

The Directive does not apply to radon in dwellings, for which a Commission  Recommendation 
exists8 nor to exposures to natural radiation sources essentially not controllable. 

c)  TITLE III 

Reporting and authorisation of practices 

Article 3 

Reporting means the submission of a document to notify  or inform the competent authorities of 
the intention to undertake a practice.  Article 3(2) and Annex I specify  the circumstances under 
which  competent  authorities  may  decide  that  reporting  is  not  required.  Member  States  are 
allowed  to  deviate from the  values  in  Table  A  of  Annex  I,  in  exceptional  circumstances  and 
subject to specified conditions. 

Article 4 

Prior  authorisation  is the  permission  granted  by the competent  authority  in  individual  written 
notification  or  in  a  legislative  act  that  is  individual  in  character,  to  carry  out  a  practice.  It 
implies the prior examination by the competent authorities of individual submitted cases. 

Member  States  need  not  require  such  prior  authorisation  in  the  case  of  certain  practices, 
exempted from the requirement to report as stated in Article 3(2) and in Article 4(3)(a), and in 
the case of practices, permitted according to conditions laid down in national legislation, where 
examination  of  individual  cases  is  not  considered  necessary  as  a  result  of  limited  risk  of 
exposure  of  human  beings  as  stated  in  Article 4(3)(b).  In  compliance  with  Article 3(1)  such 
latter practices are reported to the competent authorities. 

Authorisation  is needed under any circumstances for the practices referred  to in Article 4(1 )(b) 
and in Article 4(1 )(d) 

Article 6(5) identifies practices which are not permitted under any circumstances. 

7 OJN°L  183, 29.6.1989 pi 
8  Commission Recommendation (90/143/Euratom) of 21 February  1990 on the protec 
tion of the public against indoor exposure to radon (OJ No L 80, 27.3.1990,  p.26.). 
4 

Article 5 

This Article deals with the disposal, recycling or reuse of radioactive substances or materials. 

The disposal, recycling or reuse of materials containing radioactive substances which have been 
involved in practices subject to reporting or prior authorisation  is subject  to prior  authorisation. 
Such materials may  nevertheless  be released  from  the requirements  of the Directive  subject  to 
compliance with clearance levels established by national competent  authorities. Such clearance 
levels shall  be established  following  the basic criteria  in Annex  I. They  may  be  generic  or be 
established  in  individual  cases.  The  term  'clearance'  refers  to  material  previously  subject  to 
regulatory control as part of the operations that gave rise to this disposal, recycling or reuse. On 
the other hand exemption from reporting according to Article 3(2) refers to material which does 
not need to become subject to regulatory control. 

Article  3(2)(f)  ensures  that  human  activities  involving  materials  contaminated  as  a  result  of 
authorised releases need not be reported. 

In view of the internal market, a harmonised approach to the development of clearance levels is 
highly  desirable.  The  Commission  will  therefore  give  technical  guidance  for  national 
competent  authorities  on  the  establishment  of  clearance  levels.  The  Commission,  with  the 
support  of  the  group  of  scientific  experts  referred  to  in  Article  31  of  the  Euratom  Treaty,  is 
working on a revised version of the technical guide (1988) on clearance levels for the recycling 
of material  coming  from  the decommissioning  of nuclear  installations9. Other technical  guides 
will follow. 

d)  TITLE IV 

Justification, optimisation and dose limitation for practices 

Article 6 

This Article sets out the basic principles of radiation protection and thus requires Member States 
to  base  their  procedures  on  these  principles,  namely  justification,  optimisation  and  dose 
limitation. 

Determination  of  the justification  of  any  new  classes  or  types  of  practice  is  the  duty  of  the 
Member State. It should take place before the introduction of the class or type of practice and as 
early as possible to reduce the influence of the already incurred costs in balancing economic and 
social factors against health detriment. Compliance with this principle  can be safely  assumed in 
respect  of  a  new  class  or  type  of  practice  by  the  existence  or  laying  down  of  regulations 
specifically  concerning  the  class  or  type  of  practice.  Paragraph  5  gives  a  list  of  practices 
considered a priori as not justifiable under any circumstances.  The newly introduced proviso  of 
Article 6 (2) reflects that there might be the need to review the justification  of existing classes or 
types of practices.  If an existing practice should be considered  unjustified  a transitional period 
could still be tolerated on the basis of a carefully  weighted balance between economic, social or 
other benefits  and the health detriment. 

Radiation protection No 43:  Radiological protection criteria for the recycling of 
materials from  the dismantling of nuclear installations, Luxembourg  1988. 

5 

Optimisation  requires  that  exposures  from  practices  shall  be  kept  as  low  as  reasonably 
achievable  below the prescribed limits, economic  and social  factors  being  taken into account. 
The techniques  for judging the need for further reductions in exposure  in the  light  of what is 
reasonable are very diverse. They include  formal aids to decision-making  such as cost benefit 
analyses, but they are more usually based on professional judgement.  The principle should be 
applied  from  the  design  stage,  throughout  all  other  stages  to  eventual  decommissioning  or 
disposal of sources. 

The third principle requires that the sum of the doses to an individual from all relevant practices 
shall not exceed specified dose limits. The considerations which led to the establishment of the 
dose limits are presented in ICRP Publication N° 60. The dose limits are intended to protect the 
most highly exposed individuals which, in the case of members of the public, are defined as the 
"reference group of the population " (Article 1 ). 

Article 7 

The concept of dose constraint has been introduced in ICRP Publication 60 within the context 
of optimisation of protection.  Dose constraints should not be confused with dose limits.  They 
are essentially  a ceiling to the predicted values of individual  doses from a source, practice or 
task which could be determined to be acceptable in the process of optimisation of protection for 
that source, practice or task. 

Dose  constraints  may  be  established  and  used  by  undertakings  as  a  help  for  optimising 
protection in the design or in the planning stage.  They may also be established  by authorities, 
particularly  in the context of public exposure.  They may be matters  for discussions  between 
undertakings and authorities. 

A guide on the utilisation of the newly introduced concept is given in a report10 by a joint group 
of  experts  from  the  OECD  Nuclear  Energy  Agency  and  from  the  European  Commission, 
published by the OECD in 1996. 

Article 9 

The Directive has decreased the effective dose limit for exposed workers from 50 mSv in a year 
to  100 mSv in a consecutive five-year-period,  subject to a maximum effective  dose of 50 mSv 
in any single year. 

While  respecting  the  limit  of  100 mSv  in a consecutive five-year period  Member  States are 
entitled  to  decide  instead  an  annual  amount.  In this  case  the  effective  dose  limit  would  be 
20 mSv in a year. Member States  which wish to adopt stricter dose  limits shall  comply  with 
Article 54. 

The equivalent dose limits for the lens of the eye, the skin, the hands, forearms, feet and ankles 
remain unchanged.  Their purpose is to protect against deterministic effects, for which  scientific 
information indicates no need for change.  However, the limit for the skin  now applies to the 
dose  averaged  over any  1  cm2 of  skin, regardless of the area exposed.  Compliance  with the 
effective  dose  limit  alone  is  not  always  sufficient  to  prevent  the  occurrence  of  deterministic 
effects  on some organs or tissues.  It is therefore necessary to ensure compliance with both the 
effective dose limit and the quivalent dose limits. 

10  Considerations on the Concept of Dose constraint, Paris 1996. 

6 

Article 10 

Article 10  aims  at  protecting  the  suckling  child  or  the  child  to  be  born,  via  the  working 
conditions of the nursing or the pregnant woman. 

Article 22 (1) (b) identifies the additional information that women should be given. 

Article 12 

Specially  authorised  exposures  replace  the  planned  special  exposures  from  Directive 
80/836/Euratom.  Experience on the application of planned special exposure under the terms of 
the  1980 Directive  has  shown  that they have  been  applied  very  seldom  if at  all.  A specially 
authorised  exposure  would  involve  an  exposure  above  one  of  the  dose  limits  for  exposed 
workers established by national legislation in compliance with Article 9. 

The Directive requires  maximum exposure levels resulting from specially authorised exposures 
to be defined  for each particular case by the competent authorities.  No ceiling is given for such 
levels as it might be interpreted as a generally tolerable value. 

Article  12 (2)  should be read in conjunction  with Articles 35 and 36 on the special surveillance 
of exposed workers. 

Article 13 

The Directive has decreased the effective  dose limit for  members of the public from 5 mSv to 1 
mSv m a year; in special  circumstances, a higher effective' dose may  be authorised  in a single 
year, provided that the average over five consecutive years does not exceed  1  mSv per year. 

The equivalent dose limits for the lens of the eye and for the skin are unchanged.  Their purpose 
is to protect against deterministic effects,  for which scientific  information  indicates no need  for 
change.  However,  the limit  for  the skin  now applies to the dose averaged  over any  1 cm2 of 
skin, regardless  of the  area  exposed.  Equivalent  dose limits  for  the hands, forearms,  feet  and 
ankles are no  longer  seen as necessary.  Compliance with the effective  dose limit alone is not 
always sufficient  to prevent the occurrence of deterministic effects  on some organs or tissues.  It 
is therefore  necessary to ensure compliance with both the effective  dose limit and the quivalent 
dose limits. 

The dose limits apply to the sum of the doses to members of the public due to exposure to all 
relevant sources received in one year, through all exposure pathways. 

Article 14 

This Article requires optimisation of protection to be made not only with respect to individuals 
but also to the population as a whole. 

The second paragraph requires regular assessments of the total of contributions to the exposure 
of  the  population  from  practices.  The  objective  is  to  enable  competent  authorities  and 
undertakings to identify  trends in the pattern of exposures in particular where actions to reduce 
doses might be warranted. See also Article 45. 

7 

e)  TITLE V 

Estimation of effective dose 

Articles 15 and 16 

This  Title  refers  to  the  values  and  relationships  given  in  Annex II  and  the  dose  coefficients 
given  in  Annex III  to  be  used  for  the  estimation  of  effective  and  equivalent  doses.  The 
information  contained 
this 
Communication  are taken from  the most recent relevant work of  ICRU and  ICRP and  reflect 
the current status of scientific knowledge.  While competent authorities may authorise the use of 
equivalent  methods  (Article  15),  it  is  recommended  that  these  be  kept  in  line  with 
internationally recognised scientific guidance. 

these  annexes  and 

tables  annexed 

the  additional 

in 

to 

With  regard  to  the  estimation  of  effective  dose  for  internal  exposure,  Annex III  gives  dose 
coefficients  for  different  chemical  and physical  forms  that have  been  considered  for  the  listed 
radionuclides  and corresponding parameter values.  If specific  information  is not available, the 
indicated  default  parameters  may  be  used.  On  the  other  hand,  whenever  information  is 
available  which  permits  a  better  estimation  of  the  parameter  values  and  corresponding  dose 
coefficients,  competent  authorities  may  authorise  the  use  of  such  information  to  calculate 
effective  dose to workers and to members of the public. 

In the above context, the last paragraph of Part B of Annex III  relates to the choice of parameter 
values for  inhalation  dose  coefficients  for  members of the public.  The  international  scientific 
guidance referred to is now identified  in Table 1  in Annex II of this communication. 

In the first paragraph of Part B of Annex III it is stated that dose coefficients  for members of the 
public also  relate to apprentices and students aged between sixteen and eighteen years.  While 
this makes allowance for the age dependence of dose coefficients,  in some circumstances it may 
be  useful  to  look  into  whether  the  default  parameters  used  for  members  of  the  public  are 
suitable  for  the physical  and  chemical  forms  in which  radionuclides  occur  in the  workplace. 
Article  15 allows Member States to authorise the use of dose coefficients  for workers whenever 
these are more appropriate. 

f)  TITLE VI 

Fundamental principles governing operational protection 
of exposed workers, apprentices and students for practice 

Article 17 

Consistent with Council Directive 89/391/EEC of 12 June  1989 on the introduction of measures 
to encourage improvements in the safety  and health of workers at work",  Article  17(a) requires 
a prior evaluation  of the radiological  risk to exposed  workers.  This  should  be seen as the  first 
step in  identifying  the  protection  measures  required  including  the  classification  of  workplaces 
and workers. 

OJNoL  183,29.6.1989, p.l 

Article  17(b),  dealing  with  classification  of  workplaces  into  different  areas,  introduces  the 
concept of potential exposure, as defined  in Article 1. An example of potential exposures is that 
resulting from the failure  of the operation of an interlock  preventing access to the beam of an 
irradiation  facility.  Any  exposure  resulting  from  such  an  event  would  be  considered  as 
accidental.  Exposures  that  may  result  from  events  having  a  relatively  high  probability  of 
occurrence, and contributing only small increments to the doses inherent in the normal working 
conditions, can be considered as resulting from  the normal working conditions.  An example of 
such  exposures  are  those  resulting  from  the  spillage  of  a  radiopharmaceutical  in  a  nuclear 
medicine laboratory. 

Article 18-20 

These  articles  give  the  requirements  to  implement  Article  17.  Article  18 (2)  requires  a 
distinction to be made between controlled  and  supervised  areas. This distinction  is primarily a 
management  matter.  It  aims  at  facilitating  the  practical  organisation  of  radiation  protection 
commensurate  with  the  radiological  risk.  It  also  draws  the  attention  of  the  workers  to  the 
particular conditions of the workplace and makes them aware of their responsibilities as regards 
radiation protection. 

Controlled  areas  should  be  established  where  workers  are  required  to  follow  rules  specially 
related to radiological protection rather than simply on the basis of a defined fraction of the dose 
limit.  Special rules are required based on considerations of radiological risk, including expected 
dose to workers, possible spread of contamination and potential exposures. 

The Directive does not require  a controlled area  to be surrounded by a supervised area, neither 
does it require that supervised areas only exist at the border of controlled areas. 

Article 21 

The classification  of exposed workers in Category A and Category B workers is maintained.  It 
is intended to simplify  working arrangements and to ensure that workers are aware both of their 
own status and of the likely conditions in their place of work.  It also contributes to ensure that 
radiation protection arrangements for workers are appropriate to the risks linked with their work 
and working conditions. 

Article 28 

The Directive requires a record of the results of the individual monitoring to be retained only  for 
category  A workers. Member  States, however,  are free  to require  such  records to be kept  for 
other persons who are individually monitored. 

The individual dose record shall contain the estimated or measured doses separated into: 

- 

those received routinely (Article 25), 

- 

those received as specially authorised exposures (Article 12), 

- 

those due to accidents (Article 26), 

- 

those received as emergency exposures (Article 27) and,, 

- 

those received from natural radiation sources in a work activity declared  to be of concern 
(Article 41 ), when decided by Member States. 

The individual dose record shall also contain reports relating to the circumstances of an accident 
or emergency exposure and actions taken (Article 28(2)(b)). 

i 

A  separate  medical  record  shall  be  opened  for  each  Category  A  worker  as  specified  by 
Article 34. 

Article 29 

Article 29(2) requires Member States to determine the arrangements for conveying the results of 
individual  monitoring  following  their  national  regulations  concerning  confidentiality  and 
privacy. 

Articles 31-37 

One of the aims of medical  surveillance  of category A workers is to ensure that they  are and 
continue to be medically fit for  their duties. The approved medical practitioner conducting the 
surveillance must therefore have relevant information about these duties and the conditions in 
which they are carried out. 

The nature of the periodic reviews shall depend on the type of work that is undertaken and the 
state of health of the worker. 

For example special consideration may be needed in situations: 

-  where workers are required to use respiratory protective equipment, 

-  where  workers  with  skin  diseases  or  skin  damage  are  required  to  handle  radioactive 

substances which are not in the form of sealed sources, 

-  where workers are known to have psychological disorders. 

g)  TITLE VII 

Significant increase in exposure due to natural radiation sources 

Articles 40-42 

In some cases, the exposures of workers and members of the public to natural radiation  sources 
due to  work  activities  are  sufficiently  high  to  warrant  the  introduction  of  radiation  protection 
measures  to  monitor,  control  and  reduce  them  . Examples  are  radon  exposures  in  identified 
working  places  and  exposures  due  to  work  with  large  amounts  of  materials  with  activity 
concentrations significantly  above the normal levels of natural radionuclides in the earth's crust. 
Materials  with  elevated  activity  concentrations  might  include  phosphate  rock,  rare  earth 
materials,  scales  and  residues  from  oil  and  gas  industries.  The  potential  to  apply  protection 
measures  regarding these exposures may vary considerably  depending  for  example on working 
conditions  and  within  and  between  Member  States, therefore  the  Directive  leaves  significant 
discretion to the Member States as regards actions to be taken. 

10 

The Directive sets up a four step system to deal with exposures due to natural radiation sources: 

i) 

the use of surveys or  other appropriate means to identify  work activities which may lead to 
a significant  increase in the exposure of workers or members of the public; 

ii)  the  setting-up  of  appropriate  means  for  monitoring  exposures,  and  the  evaluation  of  the 

related doses in identified workplaces; 

iii)  the implementation, as necessary of corrective measures to reduce exposure , and 

iv)  the total  or partial  application,  as necessary,  of radiation protection  measures  for  practices 

(Title III, IV, V, VI and VIII). 

Advice  on the  implementation  of  Title VII  of the  Directive  concerning  significant  increase  in 
exposure  due to natural  radiation  sources, prepared  with the support  of the  group of  scientific 
experts referred to in Article 31 of the Euratom Treaty12 has been issued by the Commission. 

The advice covers protection of air crew. 

i)  TITLE IX 

Intervention 

Articles 48-53 

A  clear  distinction  between  practices  and  interventions  is  one  of  the  main  modifications 
introduced  by  the  Directive.  Therefore,  Title IX  includes  a  section  on the  various  phases  for 
intervention in cases of a radiological emergency: 

-  preventive consideration of possible radiological emergency; 

preventive preparation of the intervention; 

implementation of the intervention, should an emergency occur. 

Article 48(2)  sets out the radiation protection  principles for  interventions.  It makes clear that 
dose  limits  do  not  apply  to  interventions;  however,  they  should  normally  be  appropriate  for 
workers involved in interventions.  Intervention levels  established by the competent authorities 
constitute indications as to the situations in which intervention would be appropriate. 

Mainly  following  the  Chernobyl  accident  a  number  of  measures  in  relation  to  possible 
radiological emergencies have been adopted by the Community: 

12  Radiation Protection No 88:  Recommendations for the implementation of Title VII of 
the European Basic Safety  Standards Directive (BSS) Concerning significant  Increase 
in Exposure due to Natural  Radiation  Sources, Luxembourg  1997. 

11 

Regulations  laying  down  maximum  permitted  levels  of  radioactive  contamination  of 
foodstuffs  and feedingstuffs  following  a nuclear accident  or any  other  case of radiological 
emergency,  including  a  Council  Regulation  on  the  special  conditions  for  exporting 
foodstuffs  and feedingstuffs  following  a nuclear accident or any other case of  radiological 
emergency13; 

Council Decision on Community arrangements for the early exchange of information  in the 
event of a radiological emergency14; 

Council  Directive on informing  the general public about the health protection  measures to 
be applied and steps to be taken in the event of a radiological emergency15. 

Following  Council  Conclusions  of  27 November  1989 experts from the  Member  States  meet 
regularly  on  issues  of  cooperation  between  Member  States  in  the  event  of  a  radiological 
emergency. 

The  Commission,  with  the  support  of  the  Group  of  Experts  Referred  to  in  Article 31  of  the 
Euratom  Treaty,  issued  guidance  on  the  radiological  protection  principles  for  relocation  and 
return  of  people  in  the  event  of  accidental  releases  of  radioactive  material16  and  on  the 
radiological  protection  principles  for  emergency  countermeasures  to  protect  the  public  in  the 
event of accidental releases of radioactive material17 

Title IX also emphasises the importance, of international cooperation to ensure protection of the 
population  concerned  in  the  event  of  radiological  emergencies  and  sets  requirements  on  the 
Member States.  These measures complement the obligations stemming from two international 
conventions  adopted  in  1986 which  deal  respectively  with  the  early  notification  of  a  nuclear 
accident and mutual assistance in the event of a nuclear accident.  The two conventions have 
been signed by all Member States18. 

Article 49 deals with potential exposures. The concept is to be used essentially  in the preventive 
phase. 

Council Regulation (Euratom) No 3954/87 (OJ No L 371, 30.12.1987, p. 1 ), as 
amended by Council Regulation (Euratom) No 2218/89 (OJ No L 211, 22.7.1989,p. 1 ). 
Commission Regulation (Euratom) No 944/89 (OJNo L 101, 13.4.1989, p. 17), 
Council Regulation (EEC) No 2219/89 (OJ No L 211, 22.7.1989, p.4). 
Commission Regulation (Euratom) 770/90 (OJ No L 83, 30.3.1990, p.78). 
OJ No L 371, 30.12.1987, p;76. 
OJ No L 357, 7.12.1989, p.31.  See also Commission Communication on the 
implementation  of Council  Directive 89/619/Euratom of 27 November  1989 on 
informing  the general public about health protection measures to be applied and steps to 
be taken  in the event of a radiological emergency (OJ No C  103 of  19.4.1991, p. 12). 
Radiation  Protection No 64:  Radiological  Protection Principles for Relocation and 
Return of People in the Event of Accidental  Releases of Radioactive Material, 
Luxembourg  1993. 
Radiation Protection No 87:  Radiological  Protection Principles for  Emergency 
Countermeasures to Protect the Public in the Event of Accidental  Releases of 
Radioactive Material, Luxembourg  1997. 
With the exception of Luxembourg which did not sign, nor ratify  the Convention on 
Mutual Assistance. 

12 

Article 53 deals with lasting exposure situations resulting from the after-effects  of a radiological 
emergency or a past practice. 

j)  TITLE X 

Final provisions 

Article 54 

Under Article 33 (3) of the Euratom Treaty, the Member States  are required to communicate to 
the  Commission  any  draft  legislative,  regulatory  and  administrative  provision  intended  to 
ensure compliance with the basic safety standards19. 

As a result of Article  54 of the Directive, in the case a Member  State  is to adopt  stricter dose 
limits,  it  has  also  to  inform  the  other  Member  States.  The  Commission  would  normally  be 
notified under Article 33 of the Treaty. 

Annexes to the Directive 

Annex I to the Directive 

The exemption levels , which apply to practices, are  worked out using scenarios, pathways and 
formulae presented in a report published by the Commission20. 

Annex II to the Directive 

The values and relationships given in Annex II for external radiations are those required for the 
protection  quantities  defined  by  the  International  Commission  on  Radiological  Protection  in 
Publication  60  and  the  International  Commission  on  Radiation  Units  and  Measurement  in 
Report 51. 

During the preparation of the Directive some small changes were introduced by the ICRP in the 
composition  of  some  tissues  and  organs  used  to  work  out  the  effective  dose,  in  particular  as 
regards the colon and the remainder tissues and organs*.  Competent authorities may  authorise 
the use of the updated ICRP guidance, as an equivalent method under the terms of Article  15. 

The dose limits given  in the  Directive  are expressed  in terms of effective  dose and  equivalent 
dose. The need  for  measurable  quantities that can be related to these  protection  quantities  has 
led  to  the  development  of  the  operational  quantities.  The  operational  quantities  for  area 
monitoring  are  ambient  dose  equivalent  and  directional  dose  equivalent.  The  operational 
quantity for use in individual monitoring is the personal dose equivalent at a specified  depth. 

20 

See Commission Recommendation of 26 July  1991 on the application of the third and 
fourth paragraphs of Article 33 of the Euratom Treaty (OJ No L 238 of 27.8.1991, p.31). 
Radiation Protection No 65:  Principles and Methods for Establishing concentrations and 
Quantities (Exemption Values) Below which Reporting is not Required in the European 
Directive, Luxembourg  1993. 
ICRP Publication No 67 Age dependent doses to members of the public for intake of 
radionuclides:  Part 2.  Annuals of the ICRP Volume 23.  Part 3-4. 

13 

Annex III to the Directive 

The requirements on doses in the Directive apply to the sum of the relevant doses from external 
and internal radiation exposure.  In the case of internal exposure, the calculation is based on the 
use of dose coefficients  which are the committed effective  doses per unit intake of the relevant 
radionuclide.  Tables  in  Annex III  give  the  appropriate  dose  coefficients  for  workers  and 
members  of  the  public.  These  are  based  on  parameters  that  generally  apply.  The  Directive 
permits  competent  authorities  to  use  other  methods  that  are  equivalent.  For  example  where 
information  is available on the actual chemical, physical or biological behaviour of a particular 
form  of radionuclide the competent authorities may authorise the use of specially derived  dose 
coefficients. 

Annual  Limits  of  Intake  (ALI)  are no  longer  used  in the  Directive.  If  required,  they  can  be 
derived from the dose coefficients  and the relevant dose limits. 

Dose  coefficients  of  Annex  III  are  taken  from  ICRP  Publication  68  (for  workers)  and  ICRP 
Publication 72 (for members of the public). 

Inhalation  dose  coefficients  for  workers  are  given  both  for  1  micrometer  Activity  Median 
Aerodynamic  Diameter  (AMAD)  and  for  5  micrometers  AMAD.  The  advice  from  ICRP  is 
that the default value for the AMAD is 5 micrometers and this should be used in the absence of 
Inhalation  dose  coefficients  for  members  of  the  public  are  based  on 
specific  information. 
1 micrometer  AMAD.  For  inhalation  by  workers,  materials  categorised  as  lung  absorption 
classes D, W and  Y (days, weeks and years respectively,  indications of the residence  time) in 
ICRP  Publication  30 were  assigned  to  lung  absorption  types  F, M  and  S (fast,  moderate  and 
slow) in the model of ICRP Publication 66. 

Three tables, relevant for  the estimation of doses from  intakes or from exposure to inert  gases 
are given in Annex II to this Communication. 

Table  1  indicates  the  relevant  ICRP  publications  for  the  source  of  information  on  lung 
absorption types and biokinetics models for systematic activity used to calculate the  coefficients 
in Table B of Annex III of the Directive.  For a number of elements, lung absorption type G has 
also  been  retained,  which  refers  to  their  occurrence  in  specific  chemical  forms  as  soluble  or 
reactive  gases  and  vapours.  The  corresponding  dose  coefficients  for  soluble  or  reative  gases 
and  vapours  for  the  different  age  classes  are  given  in  Table 2.  The  values  for  adults  are 
appropriate for both workers and members of the public and thus the table complements the list 
of chemical forms for which dose coefficients  for workers are given in Table (C.2) of Annex III 
of the Directive. 

Table 3 gives effective  doses  for  exposure of adults to inert gases. For most  nuclides,  internal 
exposure  resulting  from  gases  absorbed  in body tissues or contained  in the lungs  is negligible 
compared  to  external  exposure  of  skin  and  other  organs  when  a  person  is  submerged  in  a 
radioactive  gas.  Hence  the  dose  coefficients,  which  apply  to  workers  and  members  of  the 
public, are expressed  per unit  integrated  air concentration.  Doses from the exposure  to radon 
(i.e. radon-222) and thoron (i.e. radon-220) arise principally  from  the  inhalation  of their short 
lived progeny, the data for  which are given in paragraph C of Annex III of the Directive.  Data 
for the parent radionuclides (radon and thoron) have therefore not been included in Table 3. 

Attachments:  Annex I and Annex II 

14 

ANNEX  I 

BASIC AND ADDITIONAL TRAINING FOR QUALIFIED EXPERTS 

1. 

INTRODUCTION 

The purpose  of this  annex is to provide advice  on the training  and  experience 

of the "qualified  expert" as defined  in Article  1 of the Directive and referred  to 

in Articles  12, 19, 20, 23, 38 and 47. 

Surveys carried  out by the Commission indicate a wide diversity in the current 

approaches  of  Member  States  to  the  training  and  qualifications  necessary  for 

recognition as a qualified  expert. 

It  is  therefore  concluded  that  it  is  not  possible  to  give  an  agreed  set  of 

harmonised  requirements for such experts. An alternative approach, adopted in 

this  annex,  is  to  propose  a  basic  syllabus  the  content  of  which  all  qualified 

experts should have received. Previous qualifications  and training may already 

have covered part or ail of this syllabus. 

The  depth  of  coverage  of  this  syllabus  should  depend  on  the  level  and 

complexity  of  advice  required  from 

the  qualified  expert,  which  is  generally 

linked to their level of involvement. ït is therefore  proposed  that certain  items 

should  be  covered  in  mors  detail  for  specific  applications.  Additional  topics 

have  also  hssn  identified  which  are recommended  for  five  specific  areas,  i.e. 

nuclear 

installations,  general 

industry,  research  and 

training,  medical 

application, accelerators. 

Training by  itself is not sufficient.  It needs to be supplemented  by  appropriate 

practical  experience,  the  duration  of which  will  depend  on  the  complexity  of 

the  field  of  work.  ït  is  not possible  to  recommend  any  specific  duration  for 

either the training  or the practical  experience needed,  as the  surveys  indicate a 

wide diversity of current practice in Member States. 

15 

2. 

BASIC SYLLABUS FOR TEE QUALIFIED EXPERT IN RADIATION 
PROTECTION 

'The depth to which topics of the syllabus shouiM be covered; should depend 
on the level of advice/napisÉ required from the qualified expert. 

( 

BASIC ATOMIC AND NUCLEAR PHYSICS 

BASIC BIOLOGY 

INTERACTION OF RADIATION WÎTK MATTER 

BIOLOGICAL EFFECTS OF RADIATION 

DETECTION AND MEASUREMENT METHODS 
(including uncertainties and limits of detection) 

QUANTITIES  AND  UNITS  (including  dosimetry  underlying  regulatory 
quantities) 

BASIS OF RADIATION PROTECTION STANDARDS 
(e.g.  epidemiology,  linear  hypothesis for- stochastic  effects,  deterministic 

t  effects) 

ICRP PRINCIPLES: 

- Justification 

-Optimisation 

- Dose limitation 

'  PRACTICES  AND INTERVENTIONS  (including  natural  radiation  especially 

radon) 

LEGAL AND REGULATORY BASIS: 

- International recommendations/conventions 

- European Union legislation 

- National legislation and regulations (including competent authorities) 

((* 

OPERATIONAL RADIATION PROTECTION: 

- Types of sources (sealed, unsealed sources, X-ray units and accelerators) 

- Hazard and risk assessment (including environmental impact) 

- Minimisation of  risk 

- Control of releases 

-Monitoring 

- area monitoring 

- personal dosimetry (external, real time and internal) 

- biological monitoring 

- Critical group concept/dose calculation for critical group 

- Ergonomics (e.g. user friendly design and layout of instrumentation) 

- Operating rules and contingency planning 

- Emergency procedures 

- Remedial action/decontamination 

- Analysis of past incidents including experience feedback 

ORGANISATION OF RADIATION PROTECTION: 

- Role of qualified experts 

- Safety culture (importance of human behaviour) 

- Communication skills (skills and ability to instil safety culture into others) 

- Record keeping (sources, doses, unusual occurrences...) 

- Permits to work and other authorisations 

- Designation of areas and classification of workers 

- Quality control/auditing 

- Dealing with contractors 

WASTE MANAGEMENT 

- Principles of management 

- Principles of disposal 

TRANSPORT 

PRACTICAL WORK/EXERCISES 
(e.g.  monitoring, laboratory techniques, handling of emergencies...) 

3. 

ADDITIONAL MATERIAL 

The  coverage  of  certain  items, selected  as  appropriate  from  the  following 
list, should be expanded to a greater depth according to the specific needs: 

SAFETY CULTURE 

OPTIMISATION TECHNIQUES 

HEALTH PHYSICS INSTRUMENTATEON 

- instrument calibration and testing 

- limitations of instruments and techniques 

EXTERNAL DOSIMETRY 

INTERNAL DOSIMETRY 

(including dosimetry for specific radionuclides, complex molecules...) 

MONITORING OF THE WORK PLACE 

SPECIAL DECONTAMINATION PROBLEMS 

CONTAINMENT/FILTRATION 

SPECIFIC PHYSIOLOGY OF INHALATION AND INGESTION 

PROTECTIVE MEASURES AGAINST INCORPORATION 

AREA DESIGNATION AND CONTROL 

DESIGN AND SHIELDING CALCULATIONS 

ENVIRONMENTAL  MONITORING 
(critical group and environmental impact of discharges) 

« 

POTENTIAL ACCIDENTS 

EMERGENCY PROCEDURES AND INTERVENTION 

WASTE MANAGEMENT 

DECOMMISSIONING 

TRANSPORT 

4. 

ADDITIONAL TOPICS RECOMMENDED FOR SPECIFIC AREAS 

4.1.  NUCLEAR INSTALLATIONS (including research installations) 

Basic additional training: 

- fission and fusion process and products 

- reactor engineering 

- neutrons (properties; detection) 

- criticality 

- handling spent  fuel 

Additional training specific to fuel  fabrication: 

- toxicity of and associated measurement problems for high Z elements 

Additional training specific to fuel processing and waste management: 

- chemistry of the process 

- remote handling 

- fuel storage and waste management special problems 

4.2.  GENERAL INDUSTRY 

a.  use of sealed  sources 

-  specific problems of: 

• controlling access, particularly in remote locations 
» transport (e.g. site radiography, mobile sources) 
• inadvertent exposure of non-radiation workers 
• safety  culture (e.g. proper handling) 

\°\ 

-  potential hazards of specific sealed sources 

-  practical examples of accidents/misuses that have occurred 

b.  use of unsealed sources 

-  hazards of isotopes production and use (including inadvertent use) 

-  special waste management aspects (including airborne and liquid 

discharges) 

-  specific hazards associated with natural radiation 

4.3.  RESEARCH AND TRAINING 

- potential hazards encountered by researchers and teachers 

- design of experiments (understanding of) 

- accelerators (special problems for research/training environment) 

- special problems with X-rays (e.g. crystallography) 

- hazards of isotopes production and use (including inadvertent use) 

4.4.  MEDICAL APPLICATIONS 

types and uses of different diagnostic and therapeutic procedures and 
equipments 

awareness of the patient protection, in particular relevant European Union 
legislation on radiation protection in relation to medical exposures, 
including requirements on potential exposures and equipment. 

specific problems of exposure control 
•  staff 
•  visitors/public 
hospital waste management 
design of special facilities (e.g.: rooms for special purposes) 

4.5.  ACCELERATORS 

special problems of radiation detection/measurement (response of 
instruments) 

control of access 

special design and shielding problems for accelerators 

X> 

ANNEX  II 

Table  1:  Lung  Absorption  Types(2l) 
Coefficients  for  Members  of  the Public 
Vapours 

used  for  the  Calculation  of  Inhalation  Dose 
Exposed  to Particulate  Aerosols  or to  Gases  and 

Element 

Absorption 
Type(s) 

ICRP Publication N° 
for details of 
Biokinetic Model and 
Absorption Type(s) 

Hydrogen 

Beryllium 

Carbon 

Fluorine 

Sodium 

Magnesium 

Aluminium 

Silicon 

Phosphorus 

Sulphur 

Chlorine 

Potassium 

Calcium 

Scandium 

Titanium 

Vanadium 

Chromium 

Manganese 

Iron 

Cobalt 

Nickel 

Copper 

Zinc 

F, M\  S, G  Publications 56, 67 and 71 

M, S 

Publication  30, Part 3 

F, M\ S, G  Publications 56, 67 and 71 

F, M, S 

Publication 30,  Part 2 

F 

Publication 30,  Part 2 

F, M 

F, M 

Publication 30,  Part 3 

Publication 30,  Part 3 

F, M, S 

Publication 30,  Part 3 

F, M 

Publication 30,  Part 1 

F, M\ S, G  Publications 67 and 71 

F, M 

Publication 30,  Part 2 

F 

Publication 30,  Part 2 

F, M, S 

Publication 71 

S 

Publication 30,  Part 3 

F,M,S 

Publication 30,  Part 3 

| 

F, M 

Publication 30,  Part 3 

F, M, S 

Publication 30,  Part 2 

F, M 

Publication 30,  Part 1 

F, M\ S 

Publications 69 and 71 

F, M*, S 

Publications 67 and 71 

F, M\ S, G  Publications 67 and 71 

F, M, S 

Publication 30,  Part 2 

F, M\ S 

Publications 67 and 71 

{21)  Particulates:  Fast, Moderate, Slow  (F, M, S), Gases and Vapours (G). 

Recommended default absorption Type for particulate aerosol when no specific information is available 

(see ÎCRP Publication  N° 71). 

-21-

. 

„ 

; 

Element 

Gallium 

Germanium 

Arsenic 

Selenium 

Bromine 

Rubidium 

Strontium 

Yttrium 

Zirconium 

Niobium 

Molybdenum 

Technetium 

Ruthenium 

Rhodium 

Palladium 

Silver 

Cadmium 

Indium 

Tin 

Antimony 

Tellurium 

Iodine 

Caesium 

Barium 

Lanthanum 

Cerium 

Praseodymium 

Neodymium 

Promethium 

Samarium 

Europium 

: 

.: 

Absorption 
Type(s) 

_ 

_ 

——} 

ICRP Publication N° 
for details of 
Biokinetic Model and 
Absorption Type(s) 

F, M 

F, M 

Publication 30,  Part 3 

Publication 30,  Part 3 

M 

Publication 30,  Part 3 

F\  M, S 

Publications 69 and 71 

F, M 

Publication 30,  Part 2 

F 

Publication 30,  Part 2 

F, M\  S 

Publications 67 and 71 

M, S 

Publication 30,  Part 2 

F, M\ S 

Publications 56, 67 and 71 

F, M\ S 

Publications 56, 67 and 71 

F, M*, S 

Publications 67 and 71 

F, M\ S 

Publications 67 and  71 

F, M\ S, G  Publications 56, 67 and 71 

F, M, S 

Publication 30,  Part 2 

. 

F, M, S 

Publication 30,  Part 3 

F, M\ S 

Publications 67 and 71 

F, M, S 

Publication 30,  Part 2 

F,M 

F, M 

Publication 30,  Part 2 

Publication 30,  Part 3 

F, M\ S 

Publications 69 and 71 

F, M\ S, G  Publications 67 and 71 

F\ M, S, G  Publications 56, 67 and 71 

F\  M, S 

Publications 56,67 and 71 

F, M\ S 

Publications 67 and 71 

F, M 

Publication 30,  Part 3 

F, M\ S 

Publications 56,67 and 71 

M, S 

M, S 

M, S 

M 

M 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

-22 

Gadolinium 

Terbium 

Dysprosium 

Holmium 

Erbium 

Thulium 

Ytterbium 

Lutetium 

Hafnium 

Tantalum 

Tungsten 

Rhenium 

-

Osmium 

Iridium 

Platinum 

Gold 

Mercury 

Thallium 

Lead 

Bismuth 

Polonium 

Astatine 

Francium 

Radium 

Actinium 

Thorium 

Protactinium 

Uranium 

Neptunium 

Plutonium 

Americium 

Element 

Absorption 
Type(s) 

ICRP Publication N° 
for details of 
Biokinetic Model and 
Absorption  Type(s) 

F, M 

Publication 30,  Part 3 

M 

M 

M 

M 

M 

M, S 

M, S 

F, M 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

Publication 30,  Part 3 

M, S 

Publication 30,  Part 3 

F 

Publication 30,  Part 3 

F,M 

Publication 30,  Part 2 

F,M,  S 

Publication 30,  Part 2 

F, M, S 

Publication  30,  Part 2 

. 

F 

Publication 30,  Part 3 

F,M, S 

Publication 30,  Part 2 

F,M, G 

Publication 30,  Part 2 

F 

Publication 30,  Part 3 

F,M*, S, G 

Publications 67 and 71 

F, M 

Publication 30,  Part 2 

F, M\  S, G 

Publications 67 and 71 

F, M 

Publication 30,  Part 3 

F 

Publication 30,  Part 3 

F, M\  S 

Publications 67 and 71 

F, M, S 

Publication  30,  Part 3 

F, M, S* 

Publications 69 and 71 

M, S 

Publication 30,  Part 3 

F, M\  S 

Publications 69 and 71 

F, M\  S 

Publications 67 and 71 

F, M\  S 

Publications 67 and 71 

F, M\  S 

Publications 67 and 71 

-23 

Element 

Absorption 
Type(s) 

ICRP Publication N° 
for details of 
Biokinetic Model and 
Absorption Type(s) 

Curium 

Berkelium 

Californium 

Einsteinium 

Fermtum 

Mendelevium 

F, M\  S 

Publication 71 

M 

M 

M 

M 

M 

Publication 30,  Part 4 

Publication 30,  Part 4 

Publication 30,  Part 4 

Publication 30,  Part 4 

Publication 30,  Part 4 

-24-

Table 2:  Committed Effective Dose p-ar Unit Intake via Inhalation  (Sv Bq"1) for soluble or reactive Gases and Vapours 

N u c l i de 

P h y s i c al 
r 
l a l f - l i fe 

A b s o r p 
t i on 

i 

d e p o s it 

fi 

h ( g) 

f or 

fi 
g  >  1  a 

h ( g) 

h ( g) 

h ( g) 

h ( g) 

h ( g )a 

Age  <  1  a 

Age 

l - 2a 

2 - 7a 

7 - 1 2a 

1 2 - 1 7a 

> 1 7a 

T r i t i a t ed  w a t er 

E l e m e n t al  h y d r o g en 

T r i t i a t ed  m e t h a ne 

1 2 .3  a 

1 2 .3  a 

1 2 .3  a 

O r g a n i c a l ly  bound 

t r i t i um 

1 2 .3  a 

C a r b o n - 11  v a p o ur 

C a r b o n - 11  d i o x i de 

C a r b o n - 11  monoxide 

0 . 3 40  h 

0 . 3 40  h 

0 . 3 40  h 

V1 

V 

V 

V 

V 

V 

V 

Carbon-14  v a p o ur 

5 . 73  1 03 

a  V 

Carbon-14  d i o x i de 

5 . 73  1 03 

a  V 

Carbon-14  monoxide 

5 . 73  1 03 

a  V 

Carbon  d i s u l p h i d e - 35 

S u l p h u r - 35  d i o x i de 

N i c k e l - 56  c a r b o n yl 

N i c k e l - 57  c a r b o n yl 

8 7 .4  d 

8 7 .4  d 

6 . 10  d 

1 . 50  d 

F 

F 

b2 

b2 

V: Very Fast absorption 

2  Refer to section 5.6 of ICRP Publication N° 71. 

100 

1 . 0 00 

6 .4  10"11 

1 . 0 00 

4 .8 

1 0 "n 

3 .1 

1 0_u 

2 .3  10"11 

1 .8  10"11 

1 .8 

1 0 'u 

0 . 01 

1 . 0 00 

6 .4  10"15 

1 . 0 00 

4 .8  1 0- 15 

3 .1  1 0 '15 

2 .3  10"15 

1 .8  10"15 

1 .8  10"15 

1 

100 

1 00 

100 

40 

1 00 

1 00 

40 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

6 .4  10"13 

1 . 0 00 

4 .8  1 0 "13 

3 .1  1 0- 13 

2 .3  1 0- 13 

1 .8  10"13 

1 .8  10"13 

1 .1  10"10 

1 . 0 00 

1 .1 

10"10 

7 .0 

1 0_u 

5 .5  10"11 

4 .1  1 0 "u 

4 .1  10"11 

2 .8  1 0 "11 

1 . 0 00 

1 .8 

1 0_ il 

9 .7 

1 0- 12 

6 .1  1 0- 12 

3 .8  10"12 

3 .2  10"12 

1 .8  10"11 

1 . 0 00 

1 .2  1 0 "11 

6 .5  10"12 

4 .1  10"12 

2 .5  1 0- 12 

2 .2  10"12 

1 .0 

1 0- 11 

1 . 0 00 

6 .7 

1 0- 12 

3 .5  1 0 '12 

2 .2  10"12 

1 .4  10"12 

1 .2  10"12 

1 .3 

10"9 

1 . 0 00 

1 .6 

1 0 "5 

9 .7  10"10 

7 .9  10"10 

5 .7  10"10 

5 .8  10"10 

1 .9 

1 0 "u 

1 . 0 00 

1 .3 

1 0 "11 

1 .1 

1 0- 11 

8 .9  10"12 

6 .3  1 0 '12 

6 .2  1 0- 12 

9 .1  1 0 '12 

1 . 0 00 

5 .7 

1 0- 12 

2 .8  10"12 

1 .7 

10"12 

• 9 .9  10"13 

8 .0  10"13 

1 00 

1 . 0 00 

6 .9  1 0-9 

0 . 8 00 

4 .8  10"5 

2 .4  10"9 

1.4  10"9 

8 .6  10"10 

7 .0  10_1C 

85 

1 00 

1 00 

1 . 0 00 

9 .4 

1 0- 10 

0 . 8 00 

6 .6  1 0 "i0 

3 .4 

1 0- 10 

2 .1  1 0- 10 

1 .3  10"10 

1 .1  10"1C 

1 . 0 00 

' 6 .8  10"9 

1 . 0 00 

5 .2 

l O '9 

3 .2  10"9 

2 .1  10"9 

1.4 

10"9 

1 .2 

1 0-9 

1 . 0 00 

3 .1  10"9 

1 . 0 00 

2 .3  1 0 "5 

1.4 

10"9 

9 .2  10"10 

6 .5  10"10 

5 .6  10_ 1( 

a applicable to both workers and adult member's- of the public" 

Table 2 :  Committed Effective Dose per Unit Intake via Inhalation  (Sv Bq"x) for soluble or reactive Gases and Vapours 

N u c l i de 

P h y s i c al 
h a l f - l i fe 

A b s o r p 
t i on 

% 
d e p o s it 

fi 

h ( g) 

f or 
fi 
g  >  1  a 

h ( g) 

h ( g) 

h ( g) 

h ( g) 

h ( g )a 

Age  <  1  a 

Age 

l - 2a 

2 - 7a 

7 - 1 2a 

1 2 - 1 7a 

> 1 7a 

N i c k e l -5  9  c a r b o n yl 

7 . 50  1 04  ; 

a  b: 

N i c k e l - 63 

c a r b o n yl 

N i c k e l - 65 

c a r b o n yl 

N i c k e l - 66 

c a r b o n yl 

9 6 .0  a 

2 . 52  h 

2 . 27  d 

R u t h e n i u m - 94 

t e t r o x i de 

0 . 8 63  h 

R u t h e n i u m - 9^ 

t e t r o x i de 

R u t h e n i u m - 1 03 

t e t r o x i de 

R u t h e n i u r r i - l C5 

t e t r o x i de 

R u t h e n i u n - 1 06 

t e t r o x i de 

T . e l l u r i u m - 1 16  v a p o ur 

T e l l u r i u m - 1 21  v a p o ur 

T e l l u r i u m - 1 2 1m  v a p o ur 

2 . 90  d 

3 9 .3  d 

4 . 44  h 

1 . 01  a 

2 . 49  h 

1 7 .0  d 

154  d 

b2 

b: 

b~ 

r 

TT 

F 

T e l l u r i u m - 1 23  v a p o ur 

1 . 00  1 0" 

a  F 

T e l l u r i u m - 1 2 3m  v a p o ur 

T e l l u r i u m - 1 2 5m  v a p o ur 

T e l l u r i u m - 1 27  v a p o ur 

T e l l u r i u r r - - 1 2 7m  v a p o ur 

120  d 

5 8 .0  d 

9 . 35  h 

109  d 

100 

1 00 

100 

100 

100 

1 00 

1 00 

100 

100 

100 

100 

100 

100 

100 

100 

100 

100 

1 . 0 00 

4 .0  1 0-9 

1 . C 00 

3 .3  10"9 

2 .0  10"9 

1 .3  10"9 

9 .1  10"10 

8 .3  10"10 

1 . 0 00 

9 .5  10"9 

1 . 0 00 

8 .0  10"9 

4 .8  10"9 

3 .0  1 0-9 

2 .2  10"9 

2 .0  10"9 

1 . 0 00 

1 . 0 00 

0 . 1 00 

0 . 1 00 

0 . 1 00 

2 .0  10"9 

1 . 0 00 

1 .4  10"9 

8 .1  10"10 

5 .6  10"10 

4 .0  10"10 

3 .6  10"10 

1 .0  10"6 

1 . C 00 

7 .1  10"5 

4 .0  10"9 

2 .7  10"9 

1 .8 

1 0-9 

1 .6  10"9 

5 .5  10"i0 

0 . 0 50 

3 .5  10"1C 

1 .8  10"10 

1 .1  10"10 

7 .0 

l O- 11 

5 .6  10"11 

8 .7  10"iC 

0 . C 50 

6 .2  10"10 

3 .4  10"10 

2 .2  10"10 

1 .4  10"10 

1 .2 

1 0- 10 

9 .0  1 0-9 

0 . C 50 

6 .2  1 0-5 

3 .3  1 0-9 

2 .1  10"9 

1 .3  10"9 

1 .1  10"9 

0 . 1 00 

1 .6  10"9 

0 . 0 50 

1 .0 

1 0_s 

5 .3  10"10 

3 .2  1 0- 10 

2 .2  10"10 

1 .8  10"10 

0 . 1 00 

0 . 6 00 

1 .6  10"7 

0 . C 50 

1 .1  10"7 

6 .1  10"8 

3 .7  10"8 

2 .2  10"8 

1 .8 

1 0 '8 

5 .9  10"10 

0 . 3 00 

4 .4  10"iC 

2 .5  10"10 

1 .6  10"10 

1 .1  10"10 

8 .7 

1 0- 11 

0 . 6 00 

3 .0  1 0-9 

0 . 3 00 

2 .4  1 0-9 

1 .4  10"9 

9 .6  10"10 

6 .7  10"10 

0 . 6 00 

3 .5  1 0-8 

0 . 3 00 

2 .7  1 0_e 

1 .6  10"8 

9 .8  10"9 

6 .6  1 0 '9 

0 . 6 00 

2 .8  10"5 

0 . 3 00 

2 .5  10"5 

1 .9  10"8 

1 .5  10"8 

1 .3  10"8 

0 . 6 00 

2 .5  10"5 

0 . 3 00 

1 .8  10"e 

1 .0  10"8 

5 .7  10"9 

3 .5  1 0 '9 

5 .1  10"10 

5 .5  10"9 

1 .2  10"8 

2 .9  1 0 '9 

0 . 6 00 

1 .5  1 0 "' 

0 . 3 0 0. 

1 .1  10"5 

5 .9  10"9 

3 .2  10"9 

1 .9  10"9 

1 .5  10"9 

0 . 6 00 

6 .1  10  'v' 

0 . 3 00 

4 .4  10"10 

2 .3  10"10 

1 .4  10"10 

0 . 6 00 

5 .3  10"-

0 . 3 :0 

3 .7  10"' 

1 .9  10"5 

1 .0  10"e 

9 .2  1 0 "n 

7 .7  10"11 

6 .1  10"9 

4 .6  10"9 

a applicable  to both workers  and ad-.; It members of the public 

Table 2:  Couaitted Effective Dos<*  ^r  Unit Intake via Inhalation  (Sv Bq"1) for soluble or reactive Gases and Vapours 

N u c l i de 

P h y s i c al 
h a l f - l i fe 

A b s o r p 
t i on 

% 
d e p o s it 

Age  <  1  a 

fi 

h ( g) 

f or 

fi 
g  >  1  a 

Age 

l - 2a 

2 - 7a 

7 - 1 2a 

1 2 - 1 7a 

> 1 7a 

h ( g) 

h ( g) 

h ( g) 

h ( g) 

h ( g )a 

T e l l u r i u m - 1 29  v a p o ur 

1.16  h 

T e l l u r i u m - 1 2 9m  v a p o ur 

3 3 .6  d 

T e l l u r i u m - 1 31  v a p o ur 

0 . 4 17  h 

T e i l u r i u m - 1 3 1m  v a p o ur 

1 . 25  d 

T e l l u r i u m - 1 32  v a p o ur 

3 . 26  d 

T e l l u r i u i t i - 1 33  v a p o ur 

0 . 2 07  h 

T e l l u r i u m - 1 3 3m  v a p o ur 

0 . 9 23  h 

T e l l u r i u m - 1 34  v a p o ur 

0 . 6 96  h 

E l e m e n t al 

i o d i n e - 1 20 

1 . 35  h 

E l e m e n t al 

i o d i n e - 1 2 0m 

0 . 8 83  h 

E l e m e n t al 

i o d i n e - 1 21 

2 . 12  h 

E l e m e n t al 

i o d i n e - 1 23 

1 3 .2  h 

E l e m e n t al 

i o d i n e - 1 24 

4 . 18  d 

E l e m e n t al 

i o d i n e - 1 25 

6 0 .1  d 

E l e m e n t al 

i o d i n e - 1 26 

1 3 .0  d 

E l e m e n t al 

i o d i n e - 1 28 

0 . 4 16  h 

F 

F 

F 

F 

F 

F 

F 

F 

V 

V 

V 

V 

V 

V 

y 

V 

E l e m e n t al 

i o d i n e - 12 9 

1 . 57  107  « 

i  y 

100 

1 00 

100 

1 00 

100 

1 00 

100 

100 

100 

100 

1 00 

1 00 

100 

1 00 

100 

100 

100 

0 . 6 00 

2 .5  10~10 

0 . 3 00 

1 .7 

lO"10 

9 .4  10"11 

6 .2 

1 0 "n 

4 .3  1 0 "u 

3 .7  10"11 

0 . 6 00 

4 .8  10"8 

0 . 3 00 

3 .2  10"8 

1 .6 

10"8 

8 .5  10"9 

5 .1  10"9 

3 .7  10"9 

0 . 6 00 

0 . 6 00 

5 .1  10"10 

0 . 3 00 

4 .5  10"iC 

2.6 

10"10 

1.4  10"10 

9 .5  10"11 

6 .8 

1 0- 11 

2 .1  10"8 

0 . 3 00 

1 .9 

10"s 

1 .1  10"8 

5 .6  10"9 

3 .7  10"9 

2 .4  10"9 

0 . 6 00 

5 .4  10"8 

0 . 3 00 

4 .5  10"8 

2 .4  10"8 

1 .2  10"8 

7 .6  10"9 

5 .1  1 0-9 

0 . 6 00 

. 

5 .5  10"10 

0 . 3 00 

4 ."  10"10 

2 .5  1 0 '10 

1 .2 

1 0- 10 

8 .1  10"11 

5 .6  1 0- 11 

0 . 6 00 

2 .3  10"9 

0 . 3 00 

2 .0  10"9 

1 .1  10"9 

5 .0 

I T10 

3 .3  10"1Q 

2 .2  10"10 

0 . 6 00 

6 .8  1 0 '10 

0 . 3 00 

5 .5  10"10 

3 .0  10"10 

1 .6  10"10 

1 .1  10"10 

8 .4 

1 0 ~n 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

3 .0  10"9 

1 . 0 00 

2 .4 

1 0 '5 

1 .3  10"9 

6 .4  10"10 

4 .3  10"10 

3 .0  10"10 

1 .5  10"9 

1 . 0 00 

1 .2 

10"5 

6 .4 

10"10 

3 .4 

I T10 

2 .3  10"10 

1 .8 

10"10 

5 .7  10"10 

1 . 0 00 

5 .1 

1 0 '10 

3 .0  10"10 

1 .7 

10"10 

1 .2 

I T10 

8 .6 

1 0 "n 

2 .1  10"9 

1 . 0 00 

1 .8 

10"9 

1 .0  10"9 

4 .7  1 0- 10 

3 .2  10"10 

2 .1  10"10 

1 .1  10"7 

1 . 0 00 

1 .0  10"7 

5 .8  10"8 

2 .8  10"8 

1 .8  10"8 

1 .2 

1 0-8 

4 .7  10"8 

1 . 0 00 

5 .2  10"% 

3 .7  10"8 

2 .8  10"8 

2 .0  10"8 

1.4  10"8 

1 .9  10"7 

1 . 0 00 

1 .9  10"7 

1 .1  10"7 

6 .2  10"8 

4 .1  10"8 

2 .6  10"8 

4 .2  10"10 

1 . 0 00 

2.c 

I T1'' 

1 .6  10"10 

1.0  10"10 

7 .5  10"11 

6 .5  1 0 '11 

1 . 0 00 

1.7 

10"7 

1 . 0 00 

2 .0 

I T7 

1 .6  10"7 

1.7  10"7 

1 .3 

1 0 '7 

9 .6  10"8 

a applicable  to both workers and adult menu: e r s o f~thT~fJu'bl" i c 

Table 2:  Committed Effective Dose per Unit Intake via Inhalation  (Sv Bq"1) for soluble or reactive Gas@s and Vapours 

N u c l i de 

P h y s i c al 
h a l f - l i fe 

A b s o r p 
t i on 

% 
d e p o s it 

( 

Age  <  1  a 

fi 

h ( g) 

fx  f or 
g  >  1  a 

Age 

l - 2a 

2 - 7a 

7 - 1 2a 

1 2 - 1 7a 

XL 7 a 

h ( g) 

h ( g) 

h ( g) 

h ( g) 

h ( g )a 

E l e m e n t al 

i o d i n e - 1 30 

1 2 .4  h 

E l e m e n t al 

i o d i n e - 1 31 

8 . 04  d 

E l e m e n t al 

i o d i n e - 1 32 

2 . 30  h 

E l e m e n t al 

i o d i n e - 1 3 2m 

1 . 39  h 

E l e m e n t al 

i c d i n e - 1 33 

2 0 .8  h 

E l e m e n t al 

i c d i n e - 1 34 

0 . 8 76  h 

E l e m e n t al 

i o d i n e - 1 35 

6 . 61  h 

M e t h yl 

i o d i d e - 1 20 

1 . 35  h 

M e t h yl 

i o d i d e - 1 2 0m 

0 . 8 83  h 

M e t h yl 

i o d i d e - 1 21 

M e t h yl 

i o d i d e ~ 1 23 

M e t h yl 

i o d i d e - 1 24 

M e t h yl 

i o d i d e - 1 25 

M e t h yl 

i o d i d e - 1 26 

2 . 12  h 

1 3 .2  h 

4 . 18  d 

6 0 .1  d 

1 3 .0  d 

M e t h yl 

i o d i d e - 1 28 

0 . 4 16  h 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

V 

M e t h yl 

i o d i d e - 1 29 

1 . 57  1 07  a 

t  V 

M e t h yl 

i o d i d e - 1 30 

1 2 .4  h 

V 

100 

100 

100 

100 

1 00 

1 00 

1 00 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 .9  10"8 

1 . 0 00 

1 .7 

I T8 

9 .2  10"9 

4 .3  10"9 

2 .8 

I T9 

1 .9  10"9 

1 .7 

I T7 

1 . 0 00 

1 .6  10"7 

9 .4  10"8 

4 .8 

I T8 

3 .1  10"8 

2 .0  10"8 

2 .8  10"9 

1 . 0 00 

2 .3  10"9 

1 .3 

I T9 

6 .4  10"10 

4 .3 

I T10 

3 .1 

I T10 

1 . 0 00 

2 .4  10"9 

1 . 0 00 

2 .1 

I T9 

1 .1  10"9 

5 .6  10"10 

3 .8  10"10 

2 .7 

I T10 

. 1 . 0 00 

4 .5 

I T8 

1 . 0 00 

4 .1  10"8 

2 .1  10"8 

9 .7  10~9 

6 .3  1 0 "9 

4 .0  10"9 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

8 .7  10"10 

1 . 0 00 

6 .9  10"10 

3 .9  10"10 

2 .2  10"10 

1 .6  1 0 "10 

1 .5 

I T10 

9 .7  1 0-9 

2 .3 

I T9 

1 .0  1 0-9 

1 . 0 00 

8 .5  10"9 

4 .5 

I T9 

2 .1  10"9 

1 .4  10~9 

9 .2  10"10 

1 . 0 00 

1 .9  1 0 "9 

1 .0  10"9 

4 .8  1 0- 10 

3 .1  10"10 

2 .0 

1 0 '10 

1 . 0 00 

8 .7 

1 0- 10 

4 .6 

I T10 

2 .2  1 0 "10 

1 .5  10"10 

1 .0 

i o ~10 

4 .2  10"10 

1 . 0 00 

3 .8 

I T10 

2 .2  10"10 

1 .2  10"10 

8 .3  1 0 "11 

5 .6  1 0 "11 

1 .6  10"9 

1 . 0 00 

1 .4  10"9 

7 .7  1 0 "10 

3 .6  10"10 

2 .4 

I T10 

1 .5  10"10 

8 .5 

I T8 

1 . 0 00 

8 .0 

10"8 

4 .5  10"8 

2 .2  10"8 

1 .4 

I T8 

9 .2  10"9 

3 .7  10"8 

1 . 0 00 

4 .0  10"° 

2 .9  10"8 

2 .2  10~8 

1 .6 

I T8 

1 .1  10"8 

1 . 0 00 

1 .5  10"7 

1 . 0 00 

1 .5  10"7 

9 .0  10"8 

4 .8  10"8 

3 .2  10"8 

2 .0  10"8 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 .5  10"10 

1 . 0 00 

1 .2  10"10 

6 .3 

1 0 "u 

3 .0  1 0 "1 1' 

1 .9  1 0 "n 

1 .3  10"11 

1 .3  10"7 

1 . 0 00 

1 .5  10"7 

1 .2  10"7 

1 .3  10"7 

9 .9 

I T8 

7 .4  10"8 

1 .5  10"* 

1 . 0 00 

1 .3  1 0 "' 

7 .2 

10"3 

3 .3 

I T9 

2 .2  10"9 

1 .4  10~9 

a applicable  to both workers and adult members  of the public 

Table 2:  Cosamittssd Effective Dose par Unit Intake via Inhalation  (Sv Bq"1) for soluble or reactive Gases and Vapours 

N u c l i de 

P h y s i c al 
h a l f - l i fe 

A b s o r p 
t i on 

% 
d e p o s it 

Age  <  1  a 

Age 

l - 2a 

2 - 7a 

7 - 1 2a 

1 2 - 1 7a 

> 1 7a 

fi 

h ( g) 

f or 

f: 
g  >  1  a 

h ( g) 

h ( g) 

h ( g) 

h ( g) 

h ( g )a 

M e t h yl 

i o d i d e - 1 31 

M e t h yl 

i o d i d e - 1 32 

M e t h yl 

i o d i d e - 1 3 2m 

M e t h yl 

. i o d i d e - 1 33 

8 . 04  d 

2 . 30  h 

1 . 39  h 

2 0 .8  h 

M e t h yl 

i o d i d e - 1 34 

0 . 8 76  h 

M e t h yl 

i o d i d e - 1 35 

M e r c u r y - 1 93  v a p o ur 

M e r c u r y - 1 9 3m  v a p o ur 

6 . 61  h 

3 . 50  h 

1 1 .1  h 

M e r c u r y - 1 94  v a p o ur 

2 . 60  1 C:  a 

M e r c u r y - 1 95  v a p o ur 

M e r c u r y - 1 9 5 ra  v a p o u r-

M e r c u r y - 1 97  v a p o ur 

M e r c u r y - 1 9 7m  v a p o ur 

9 . 90  h 

1 . 73  d 

2 . 67  d 

2 3 .8  h 

M e r c u r y - 1 9 9m  v a p o ur 

0 . 7 10  h 

V 

V 

V 

V 

V 

V 

b3 

b3 

b3 

b3 

b3 

b3 

b3 

M e r c u r y - 2 03  v a p o ur 

4 6 .6  d 

•.  "3 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

70 

1 . 0 00 

1 .3  10"7 

1 . 0 00 

1 .3  10"7 

7 .4  10"8 

3 .7  1 0-8 

2 .4  10"8 

1 .5  10"8 

1 . 0 00 

2 .0 

I T9 

1 . 0 00 

1 .8  1 0 "9 

9 .5  10"10 

4 .4  10"10 

2 .9  10"10 

1 .9 

I T10 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 . 0 00 

1 .8  10"9 

1 . 0 00 

1 .6  10"9 

8 .3  10"10 

3 .9 

I T10 

2 .5  10"10 

1 .6 

I T10 

3 .5  1 0_s 

1 . 0 00 

3 .2  10"8 

1 .7 

I T8 

7 .6 

I T9 

4 .9  1 0-9 

3 .1  10"9 

5 .1  10"10 

1 . 0 00 

4 .3 

I T10 

2 .3 

I T10 

1 .1  10"10 

7 .4 

1 0 "n 

5 .0  1 0- 11 

7 .5  10"9 

1 . 0 00 

6 .7  1 0-9 

3 .5 

I T9 

1 .6  10"9 

1 .1  10"9 

6 .8 

I T10 

1 . 0 00 

4 .2  1 0-9 

1 . 0 00 

3 .4  10"9 

2 .2  10"9 

1 .6  10"9 

1 .2  10"9 

1 .1  10"9 

1 . 0 00 

1 . 0 00 

1 .2 

I T3 

•i.  .  u uU 

9 .4  1 0 "9 

6 .1  10"9 

4 .5  10"9 

3 .4 

I T9 

3 .1  1 0-9 

9 .4  1 0 "5 

1  .  ;J J J 

8 .3  1 0 "8 

6 .2  10"8 

5 .0  10"8 

4 .3  1 0 '8 

4 .0  10"8 

1 . 0 00 

5 .3  1 0 "5 

1.CC0 

4 .3  1 0 "9 

2 .8  10"9 

2 .1  10"9 

1 .6  10"9 

1 .4  10"9 

1 . 0 00 

1 . 0 00 

3 .0  1 0 "8 

1 . 0 00 

2 .5  10"8 

1 .6 

I T8 

1 .2 

I T8 

8 .8  10"9 

8 .2  1 0-9 

1 .6  1 0-8 

1 . 0 00 

1 .3 

I T8 

8 .4 

I T9 

6 .3  10"9 

4 .7  10"9 

4 .4  1 0-9 

1 . 0 00 

2 .1 

I T8 

i..  u  \J  J 

1 .7 

I T8 

1 .1  10"8 

8 .2  1 0 "9 

6 .2  10"9 

5 .8  10"9 

1 . 0 00 

6 .5  10"1C 

1 . 0 00 

5 .3  10"10 

3 .4  1 0 "10 

2 .5  10_ 1C 

1 .9  10"10 

1 .8  10"10 

1 . 0 00 

3 .0  10"s 

r  *-  ^ 

2 .3 

I T8 

1 .5 

I T8 

1 .0  10"s 

7 .7  10"9 

7 .0  10"9 

3  Deposition 10% : 20% : 40% (bronchial: bronchioter. alveolar-interstitial),  1,7 day retention half-time (1CRP publication  68) 

a applicable  to both workers  and a';.It members of the public 

Table 3 

Effective Dose for Exposure of adults (workers or members of the 
public) to inert gases 

N u c l i de 

t l /2 

E f f e c t i ve  doao  p er  u n it 
a ir  c o n c e n t r a t i on  (Sv  d- 1/Bq  nf3) 

i n t e g r a t ed 

Argon 

A r - 37 
' A r - 39 
A r - 42 

Krypton 

Kr-74 
K r - 76 
K r - 77 
K r - 79 
K r - 81 
Kr-83m 
K r - 85 
Kr-85m 
K r - 87 
K r - 88 

Xenon 

Xe-120 
Xe-121 
Xe-122 
Xe-123 
Xe-125 
Xe-127 
Xe-129m 
Xe-131m 
Xe-133ra 
Xe-133 
Xe-135m 
X e - 1 35 
Xe-138 

3 5 .0  d 
269  a 
1 . 83  h 

1 1 .5  m 
1 4 .8  h 
7 4 .7  m 
1.46  d 
2 . 10  105  a 
1 . 83  h 
1 0 .7  a 
4 . 48  h 
1.27  h 
2 . 84  h 

4 0 .0  m 
4 0 .1  m 
2 0 .1  h 
2 . 08  h 
1 7 .0  h 
3 6 .4  d 
8 .0  d 
1 1 .9  d 
2 . 19  d 
5 . 24  d 
1 5 .3  m 
9 . 10  h 
1 4 .2  m 

4 .1  10"15 
1.1  10"11 
5 .3  10"9 

4 .5  10~9 
1.6  1 0" 
3 .9  10~9 
9 .7  1 0 '10 
2 .1  10"11 
2 .1  1 0 '13 
2 .2  1 0 "u 
5 .9  10_1° 
3 .4  10'9 
8.4  10-9 

1.5  10"9 
7 .5  10"9 
1.9  10"10 
2 .4  10-9 
9 .3  10~10 
9 .7  10"10 
8 .1  1 0 "" 
3 .2  10"11 
1.1  10- 10 
1.2  10"10 
1.6  10"9 
9 .6  10"10 
4 .7  10"9 

ISSN 0254-1475 

COM(98) 87  final 

DOCUMENTS 

EN 

12  14  05  04 

Catalogue  number  :  CB-CO-98-092-EN-C 

ISBN 92-78-31163-4 

Office  for Official  Publications of the European Communities 

L-2985 Luxembourg 

3(