1. ------IND- 2016 0477 CZ - EN- ------ 20161012 --- --- PROJET 
I. 
DRAFT  
 
IMPLEMENTING DECREE  
of … 2016  
on Radiation Protection and Security of a Radioactive Source  
The State Office for Nuclear Safety provides, pursuant to §  236 of Act No  263/2016, the 
Atom ic Act, the implementation of §  9(2)(c) and (j), §  17(3)(a) and (b), §  24(7), §  25(2)(a) 
through (d), §  60(4), §  61(6), §  63(6), §  66(6), §  67(4), §  68(2)(a) through (i), §  69(2), 
§ 70(2)(b) and (c), §  71(2), §  72(5), §  73(3), §  74(4)(a) through (c), §  75(5)(a), §  76(6), 
§ 77(2), §  78(3), §  81(3), §  83(7), §  84(6), §  85(4), §  86(3), §  87(5), §  88(6), §  89(2), §  93(4), 
§ 95(6), §  96(3), §  98(4), §  99(5), §  100(3), §  101(4), §  104(9) and §  164(2):  
PART ONE  
INTRODUCTORY PROVISI ONS  
§ 1 
Subje ct matter  
This implementing decree implements the respective Euratom1) regulations and provides 
requirements for the provision of radiation protection in exposure situations and a method for 
the security of radioactive sources, including radioactive source s of security levels 1 to 3.  
Definitions  
§ 2 
For the purposes of this implementing decree, the following definitions apply  
a) absorbed dose refers to the quotient of the mean energy imparted by ionising radiation to 
the matter in a volume element and the weight of the matter in this volume element;  
b) activity refers to the quotient of the expected number of nuclear transitions from the 
energy state and the time interval within which such transitions appear;  
c) D-value refers to the activity in t he radioactive source that may cause serious tissue 
reaction if not supervised; the D -value is specified in Annex  1 to this implementing 
decree;  
d) equivalent dose refers to the product of the radiation weighing factor and the mean 
absorbed dose in an organ o r tissue for ionising radiation, or the sum of such products, if 
the ionising radiation field is composed of more types and energies; the radiation 
weighing factor is specified in Annex  2 to this implementing decree;  
                                                 
1) Council Directive  2013/51/Euratom of 22  October  2013 laying down r equirements for the protection of the 
health of the general public with regard to radioactive substances in water intended for human consumption.  
Council Directive 2013/59/Euratom of 5  December  2013 laying down basic safety standards for protection 
against  the dangers arising from exposure to ionising radiation, and repealing Directives  89/618/Euratom, 
90/641/Euratom, 96/29/Euratom, 97/43/Euratom and 2003/122/Euratom.  - 2 - 
 
 e) effective dose refers to the sum of the  products of tissue weighing factors and the 
equivalent dose in exposed tissues or organs; the tissue weighing factor is specified in 
Annex  2 to this implementing decree;  
f) collective effective dose refers to the sum of the effective doses of everyone in a certain 
group;  
g) time τ  
1. refers to 50 years for radionuclide intake in adults, or  
2. a period until the age of 70 for radionuclide intake in children;  
h) committed effective dose refers to the integral over time of the effective dose rate over 
time τ as of radionuclide intake;  
i) committed equivalent dose refers to the integral over time of the equivalent dose rate over 
time τ as of radionuclide intake;  
j) dose equivalent refers to the product of the absorbed dose at a point of tissue and the 
quality factor that expresses the different biological efficiency of different kinds of 
ionising radiation; the quality factor is specified in Annex  2 to this implementing decree;  
k) individual dose equivalent refers to the dose equivalent at a point under the body surface 
in the depth of tissue.  
CELEX : 32013L0059  
§ 3 
For the purposes of this implementing decree, the following definitions apply  
a) equivalent activity volume concentration of radon refers to the weighted sum of the 
activity volume concentration a 1 218Po, the activity volu me concentration a 2 214Pb and the 
activity volume concentration a 3 214Bi; the equivalent activity volume concentration of 
radon is equal to the sum of 0.106×a 1 , 0.513×a 2 and 0.381×a 3; 
b) radionuclide intake refers to the radionuclide activity received by a h uman body from the 
environment, usually by ingestion or inhalation;  
c) conversion factor of radionuclide intake refers to the coefficient specifying the effective 
dose corresponding to a unit radionuclide intake; the conventional values of the 
conversion fac tors of radionuclide intake are specified in Annex  3 to this implementing 
decree;  
d) hing conversion factor of radionuclide intake by ingestion;  
e) hinh conversion factor of radionuclide intake by inhalation;  
f) Ii,ing annual radionuclide intake by ingestion;  
g) Ii,inh annual radionuclide intake by inhalation;  
h) indicative dose refers to the committed effective dose from the annual intake of all 
radionuclides present in water, with the exception of tritium, 40K, 222Rn and its short -lived 
progeny;  
i) dental computed tomograp hy refers to a dental panoramic device or a different device 
used for dental treatment in dental radiodiagnostics for making images of the teeth, jaws 
or skull allowing tomographic or panoramic images to be taken using a wide cone -beam, 
or images to be acq uired by computed tomography, or creating three -dimensional images 
or tomography scans.  
CELEX: 32013L0051  
CELEX: 32013L0059  
 - 3 - 
 
 PART TWO  
RADIATION PROTECTION  
Title  I 
General rules of radiation protection  
Part 1 
Limits  
(For the implementation of§  63(4) of the  Atomic Act)  
§ 4 
General limits for the public  
The general limits for public exposure from all allowed or registered activities per 
calendar year are  
a) 1 mSv for the sum of effective doses from external exposure and committed effective 
doses from internal exposure;  
b) 15 mSv for the equivalent dose for the eye lens; and  
c) 50 mSv for the average equivalent dose per cm2 of the skin regardless of the size of 
exposed surface.  
CELEX: 32013L0059  
§ 5 
Limits for exposed workers  
(1) The limits for exposed workers shall be applied to the restrictions of occupational 
exposures and are  
a) 20 mSv for the sum of effective doses from external exposure and committed effective 
doses from internal exposure per calendar year or the value approved by t he State Office 
for Nuclear Safety (hereinafter referred to as the “Office”) pursuant to §  63(4) of the 
Atomic Act, however, less than or equal to 100  mSv over any five consecutive calendar 
years and simultaneously 50  mSv per calendar year;  
b) 100 mSv for the  equivalent dose in the eye lens over any five consecutive years and 
simultaneously 50  mSv per calendar year;  
c) 500 mSv for the average equivalent dose per cm2 of the skin per calendar year regardless 
of the size of exposed surface; and  
d) 500 mSv per calendar year for the equivalent dose in the upper extremities from the 
fingers to the forearm and in the lower extremities from the feet to the ankles.  
(2) The assessment of whether the limits for exposed workers have been exceeded or not 
shall  
a) be performed systematic ally; 
b) take into account the sum of doses from all exposure pathways and during all work 
activities that an exposed worker performs; and  
c) take into account, in the case of an exposed worker who is not an outside worker, the 
performance of all work activities  during which the exposed worker is exposed, while the - 4 - 
 
 exposure is subject to the limits for an exposed worker, for more declarants, registrants or 
licensees.  
(3) An exposed worker in whom the exceeding of the exposure limits is detected shall not 
be temporari ly allowed to work with a source of ionising radiation until their medical fitness 
for further work with the source of ionising radiation is assessed and conditions for such work 
specified.  
(4) Exceeding the limits for an exposed worker who is found medically fit pursuant to 
subsection  3 shall not be the reason for their exclusion from usual work activity or their 
relocation to a different workplace unless the person for whom the work activity is performed 
has some other serious reasons that resulted in exceedi ng the limit for an exposed worker.  
CELEX: 32013L0059  
§ 6 
Limits for pupils students  
(1) The following limits for pupils and students shall be assessed by the licensee in 
whose workplace the pupils and students are to work with a source of ionising radiation 
during their studies.  
(2) The assessment of whether the limits for pupils and students have been exceeded or 
not shall  
a) be performed systematically, while  
b) taking into account the sum of all exposure pathways and all activities performed by th e 
pupils and students with the source of ionising radiation.  
(3) The limits per calendar year for pupils and students between the ages of 16 and 18 
who have to work with a source of ionising radiation during their studies are  
a) 6 mSv for the sum of effective dos es from external exposure and committed effective 
doses from internal exposure;  
b) 15 mSv for the equivalent dose for the eye lens;  
c) 150 mSv for the average equivalent dose per cm2 of the skin regardless of exposed 
surface; and  
d) 150 mSv for the equivalent dose in the upper extremities from the fingers to the forearm 
and in the lower extremities from the feet to the ankles.  
(4) The limits for pupils and students below the age of 16 who have to work with a 
source of ionising radiation during their studies are the same  as those for the public.  
(5) The limits for pupils and students over the age of 18 who have to work with a source 
of ionising radiation during their studies are the same as those for an exposed worker.  
CELEX: 32013L0059  
§ 7 
Derived limits  
(1) Limits for exposed workers are regarded as not exceeded if quantitative indicators 
expressed in measurable quantities (hereinafter referred to as “derived limits”) have not been 
exceeded.  - 5 - 
 
 (2) The derived limits for external exposure are  
a) 500 mSv per calendar ye ar for the annual individual dose equivalent at a depth of 
0.07 mm; 
b) 20 mSv per calendar year for the annual individual dose equivalent at a depth of 3  mm; 
and 
c) 20 mSv per calendar year for the annual individual dose equivalent at a depth of 10  mm. 
(3) The deriv ed limits for internal exposure per calendar year, except for the cases laid 
down in subsections  6 and 7, are for individual radionuclide intake by an exposed worker  
a) by ingestion activity  
 
b) by inhalation activity  
 
(4) For simultaneous external and internal ex posure over a calendar year, except for the 
cases specified in subsections  7 and 8, the limits for exposed workers are regarded as not 
exceeded if the following conditions apply simultaneously  
 
 
where  
Hp(0.07) (Sv) refers to the annual individual dose eq uivalent at a depth of 0.07  mm; 
Hp(10) (Sv) refers to the annual individual dose equivalent at a depth of 10  mm; 
hi,ing (Sv/Bq) refers to the conversion factor for individual radionuclide intake by ingestion; 
the conversion factor is specified in Annex  3 to this implementing decree,  
Ii,ing (Bq) refers to an individual’s annual intake of radionuclides by digestion;  
hi,inh (Sv/Bq) refers to the conversion factor for individual radionuclide intake by inhalation; 
the conversion factor is specified in Annex  3 to this implementing decree, and  
Ii,inh (Bq) ref ers to an individual’s annual intake of radionuclides by inhalation.  
(5) The annual intake of radionuclides, their form or characteristics of inhaled aerosols 
for which Annex  3 to this implementing decree specifies the highest conversion factor for 
intake by ingestion or inhalation shall be used for the calculation pursuant to subsection  4 for 
non-identified radionuclides, chemical forms or characteristics o f inhaled aerosol.  
(6) For exposure to radon progeny, the derived limit is  
a) a value of 9.5  mJ for the intake of the latent energy of radon progeny;  
b) for a stay in a workplace for 2  000 hours and for pulmonary ventilation 1.2  m3/hour  
1. a value of 1.7  MBq for the an nual intake of the equivalent activity of radon;  
2. a value of 1.4  MBq.h.m-3 for exposure to radon progeny; or  - 6 - 
 
 3. a value of 710  Bq.m-3 for the annual average equivalent activity volume 
concentration of radon; or  
c) for a stay in a workplace for 2  000 hours, for pu lmonary ventilation 1  m3/hour and an 
imbalance factor of 0.4  
1. a value of 4.3  MBq for the annual intake of the activity of radon;  
2. a value of 3.6  MBq.h.m-3 for exposure to radon; or  
3. a value of 1  800 Bq.m-3 for the annual average activity volume concentration of 
radon.  
(7) For exposure to a mixture of long -lived radionuclides that emit alpha particles of the 
uranium -radium series, the derived limit refers to the intake of 3  200 Bq by inhalation per 
calendar year.  
Part 2 
Optimisation of radiation protection  
(For the  implementation of §  66(6)(c) of the Atomic Act)  
Procedures for the optimisation of radiation protection  
§ 8 
(1) When optimising radiation protection, any person who performs activities involving 
exposure situations shall specify the varian ts of radiation protection and choose the optimal 
variant to ensure radiation protection in the respective exposure situation.  
(2) The selection of the optimal variant of radiation protection shall be performed by 
comparing options to reduce the planned and po tential doses to which natural persons or 
groups of members of the public will be exposed. The measures taken to protect individuals 
or groups of members of the public against the influence of a source of ionising radiation can 
be applied  
a) at the source of ionising radiation;  
b) in the environment between the source of ionising radiation and the individual; or  
c) on the individual level.  
(3) When selecting the optimal variant of radiation protection to be ensured, a reduction 
of the magnitude of exposure directly at t he source of ionising radiation shall be preferred.  
(4) When selecting the optimal variant for ensuring radiation protection, representative 
features related to the respective activity shall be taken into account. The representative 
features are specified in A nnex  4 to this implementing decree.  
(5) When selecting the optimal variant for ensuring radiation protection, it is advisable to 
carry out a comparison of the costs related to various measures for improving radiation 
protection, if possible, particularly the e vacuation of individuals or the building of sufficient 
barriers, along with a financial analysis of the expected exposure reduction.  
(6) The comparison of costs according to subsection  5 shall be carried out by multiplying 
the reduction of the collective effec tive dose for the group of individuals being assessed by a 
factor of  
a) 0.5 MCZK/Sv for radiation activity for which the average effective dose for an individual 
is greater than 1/10 of the respective exposure limits;  
b) 1 MCZK/Sv for radiation activity for whic h the average effective dose for an individual 
is greater than 1/10 but less than 3/10 of the respective exposure limits;  - 7 - 
 
 c) 2.5 MCZK/Sv for radiation activity for which the average effective dose for an individual 
is greater than 3/10 of the respective expos ure limits;  
d) 1 MCZK/Sv for medical exposure;  
e) 0.5 MCZK/Sv for exposure from a natural source of ionising radiation that is not caused 
by radiation activity; or  
f) 2.5 MCZK/Sv for emergency exposures.  
CELEX: 32013L0059  
§ 9 
(1) Any person who perf orms activities within the framework of exposure situations shall 
regularly employ the procedures for the optimisation of radiation protection not to neglect any 
newly occurring conditions for the respective exposure situation or any new possibilities for 
ensuring radiation protection for the respective exposure situation, namely in the case where 
exposure limits, specified dose constraints or reference levels have been exceeded.  
(2) When specifying dose constraints for radiation activity or a source of ionisin g 
radiation, the following shall be taken into account  
a) previous experience concerning similar activities and sources of ionising radiation so that 
the radiation protection level is not lower than before; and  
b) influences of other activities and sources of io nising radiation to avoid exceeding 
exposure limits.  
(3) When optimising radiation protection, the entire procedure for such optimisation shall 
be documented.  
(4) Documentation of the optimisation of radiation protection shall  
a) describe the procedure for such optim isation systematically and in a structured way;  
b) take into account all significant aspects concerning the exposure situation used for such 
optimisation; and  
c) include the employed variants of radiation protection to be ensured along with 
representative featur es. 
CELEX: 32013L0059  
§ 10 
Evaluation of the exposure of a representative person and an optimisation study  
(For the implementation of §  81(3)(d) and §  82(4) of the Atomic Act)  
(1) The evaluation of the exposure of a representative person sh all be performed by 
conservative estimates. The procedures for the execution of the conservative estimates of the 
exposure of a representative person are specified in Annex  5 to this implementing decree.  
(2) The content of the optimisation study to establish t he authorised exposure limit for a 
representative person is specified in Annex  6 to this implementing decree.  
CELEX: 32013L0059  - 8 - 
 
 Part 3 
Categorisation  
§ 11 
Exemption  
(For the implementation of §  67(4) of the Atomic Act)  
(1) The exemption lev els for the activity of radionuclides are specified in Annex  7 to this 
implementing decree. The exemption levels for activity are related to a total amount of 
radioactive substances used by a person within the framework of a certain radiation activity.  
(2) The exemption levels for the activity weight concentration of the radionuclides used 
within the framework of a certain radiation activity are specified in Annex  7 to this 
implementing decree.  
(3) The activity of a mixture of radionuclides is lower than the exempt ion levels if the 
sum of the quotients of the activities of individual radionuclides and the respective exemption 
levels of activities is less than 1.  
(4) The activity weight concentration of a mixture of radionuclides is lower than the 
exemption levels if the  sum of the quotients of the activity weight concentrations of individual 
radionuclides and the respective exemption levels of the activity weight concentration is less 
than 1.  
CELEX: 32013L0059  
§ 12 
High -activity source  
(For the implem entation of §  60(4)(b) of the Atomic Act)  
The activity level that makes a sealed radioactive source a high -activity source is 
specified in Annex  8 to this implementing decree.  
CELEX: 32013L0059  
Categorisation of sources of ionising radiation  
(For the imple mentation of §  61(6)(a) of the Atomic Act)  
§ 13 
A non -significant source of ionising radiation refers to  
a) a radiation generator emitting ionising radiation whose energy does not exceed 5  keV, 
which is not a significant source of ionising  radiation;  
b) a cathode -ray tube designed for imaging or different electrical equipment operating at a 
potential difference not exceeding 30  kV for which the dose rate equivalent at any 
accessible point at a distance of 0.1  m from its surface is less than 1  µSv/h; or  
c) a radioactive substance for which the sum of the quotients  
1. of the activities for particular radionuclides and the respective exemption levels of 
activity is not greater than 1; or  
2. of the activity weight concentrations for particular radionuclides  and the respective 
exemption levels of activity weight concentration is not greater than 1.  - 9 - 
 
 § 14 
A minor source of ionising radiation refers to  
a) a radiation generator that is not a non -significant source or a significant source of ionis ing 
radiation provided that it is constructed in a manner allowing the dose equivalent rate at 
any accessible point at a distance of 0.1  m from the equipment surface to be less than 
1 µSv/h, with the exception of points that are exclusively intended for ha ndling and 
operating by hand under normal operating conditions, where the dose equivalent rate can 
be up to 250  µSv/h;  
b) a sealed radioactive source that is not a non -significant source of ionising radiation and 
for which the sum of the quotients of the acti vities for individual radionuclides and the 
respective exemption levels of activity or the sum of the quotients of the activity weight 
concentrations for individual radionuclides and the respective exemption levels of 
activity weight concentrations is less  than 100 in the case of long -lived radioactive 
sources emitting alpha particles, including radioactive sources emitting neutrons, and less 
than 1  000 in the remaining cases;  
c) any equipment containing a sealed radioactive source that is not a non -significan t source 
of ionising radiation provided that it is constructed in a manner allowing the dose 
equivalent rate at any accessible point at a distance of 0.1  m from the equipment surface 
to be less than 1  µSv/h, with the exception of points that are exclusivel y intended for 
handling and operating by hand under normal operating conditions, where the dose 
equivalent rate can be up to 250  µSv/h; or  
d) an unsealed radioactive source that is not a non -significant source of ionising radiation 
for which the sum of the qu otients of the activities and the respective exemption levels of 
activities or the sum of the quotients of the activity weight concentrations and the 
respective exemption levels of activity weight concentrations for individual radionuclides 
is less than 10 . 
§ 15 
A simple source of ionising radiation refers to a source of ionising radiation that is 
not classified as a non -significant, minor, significant and very significant source of 
ionising radiation.  
§ 16 
A signific ant source of ionising radiation refers to  
a) a radiation generator intended for radiotherapy and radiodiagnostics in human medicine, 
with the exception of a bone densitometer and a dental X -ray device other than for dental 
computed tomography;  
b) a particle acc elerator;  
c) a source of ionising radiation designed for proton, neutron and other heavy -particle 
radiotherapy;  
d) equipment containing a sealed radioactive source designed for radiotherapy, including 
brachytherapy;  
e) equipment containing a sealed radioactive sour ce designed for irradiation of objects, 
including food and raw materials, objects of common use or other objects;  
f) a mobile flaw detector with a sealed radioactive source; or  
g) a high -activity source.  - 10 - 
 
 § 17 
A nuclear reactor is classified a s a very significant source of ionising radiation.  
Categorisation for the purposes of cross -border motion and security  
(For the implementation of §  61(6)(b) of the Atomic Act)  
§ 18 
(1) A source of ionising radiation of security level 1 refe rs to 
a) a radioactive thermoelectric generator;  
b) a radioactive irradiator, including an irradiator for tissues and blood;  
c) a sealed radioactive source for which the ratio of its current activity and D -value is equal 
to or greater than 1  000; or  
d) an unsealed rad ioactive source for which the ratio of the highest processed activity in the 
workplace and D -value is equal to or greater than 1  000. 
(2) A source of ionising radiation of security level 2 refers to  
a) a sealed radioactive source designed for flaw detection;  
b) a sealed radioactive source designed for brachytherapy with a high or medium dose rate;  
c) a sealed radioactive source not provided in paragraph  a or b for which the ratio of its 
current activity and D -value is less than 1  000 and simultaneously equal to or s gre ater 
than 10; or  
d) an unsealed radioactive source for which the ratio of the highest processed activity in the 
workplace and D -value is less than 1  000 and simultaneously equal to or greater than 10.  
(3) A source of ionising radiation of security level 3 refers to 
a) a sealed radioactive source designed for logging;  
b) a sealed radioactive source in an indicating or measuring device that is a high -activity 
source;  
c) a sealed radioactive source not provided in paragraph  a or b for which the ratio of its 
current activity a nd D -value is less than 10 and simultaneously equal to or greater than 1;  
d) an unsealed radioactive source for which the ratio of the highest processed activity in the 
workplace and D -value is less than 10 and simultaneously equal to or greater than 1; or  
e) A liquid or solid substance containing more than 30  % uranium whose activity exceeds 
160 MBq.  
§ 19 
(1) A source of ionising radiation of security level 4 refers to  
a) a sealed radioactive source designed for brachytherapy with a low dose rate wi th the 
exception of an eye applicator or a permanent implant;  
b) a sealed radioactive source in an indicating or measuring device that is not a high -activity 
source;  
c) a sealed radioactive source in a radioactive static eliminator;  
d) a sealed radioactive source n ot provided in paragraph  a through c for which the ratio of 
its current activity and D -value is less than 1 and simultaneously equal to or greater than 
0.01; or  
e) an unsealed radioactive source for which the ratio of the highest processed activity in the 
workplace and D -value is less than 1 and simultaneously equal to or greater than 0.01.  - 11 - 
 
 (2) A source of ionising radiation of security level 5 refers to  
a) an eye applicator and a permanent implant for radiotherapy;  
b) a source of ionising radiation for radionuclide X -ray fluorescence analysis;  
c) an electron -capture detector;  
d) a radioactive source for Mössbauer spectrometry;  
e) a calibration source of ionising radiation for positron -emission tomography;  
f) a sealed radioactive source for which the ratio of its current activity an d D-value is less 
than 0.01 and simultaneously its current activity is greater than the exemption level; or  
g) an unsealed radioactive source for which the ratio of the highest processed activity in the 
workplace and D -value is less than 0.01 and simultaneous ly its current activity is greater 
than the exemption level.  
(3) In a workplace where radioactive sources are collected, the category of security for 
the entire set of sources of ionising radiation in the workplace or in the transport package shall 
be used for  the purposes of security.  
(4) The security level of the entire set of sources of ionising radiation pursuant to 
subsection  3 shall be specified on the basis of the A/D aggregate ratio calculated in the 
following manner:  
 
where A i,n refers to activity A of ev ery individual source i of radionuclide n and D n refers 
to the D -value for radionuclide n.  
Categorisation of workplaces  
(For the implementation of §  61(6)(c) of the Atomic Act)  
§ 20 
(1) A level  I workplace refers to  
a) a workplace handling a m inor source of ionising radiation whose type is not approved by 
the Office;  
b) a workplace handling a bone densitometer that is not a minor source of ionising radiation;  
c) a workplace handling veterinary or dental X -ray devices;  
d) a workplace handling a cabin X -ray unit;  
e) a workplace handling an indicating or measuring device containing a sealed radioactive 
source whose character of radiation activity does not require a delineation of the 
controlled area; and  
f) a workplace handling an industrial X -ray device whose ch aracter of radiation activity 
does not require a delineation of the controlled area.  
(2) A level  II workplace refers to  
a) a workplace handling a simple source of ionising radiation that is not classified as a 
level  I workplace;  
b) a workplace handling an X -ray devi ce designed for radiodiagnostics or radiotherapy, with 
the exception of  
1. a bone densitometer;  
2. a dental X -ray device; or  
3. a veterinary X -ray device;  
c) a workplace handling a mobile flaw detector containing a sealed radioactive source;  - 12 - 
 
 d) a workplace handling a mob ile irradiator containing a sealed radioactive source;  
e) a workplace handling an indicating or measuring device containing a sealed radioactive 
source whose character of radiation activity requires a delineation of the controlled area;  
f) a workplace handling a n industrial X -ray device whose character of radiation activity 
requires a delineation of the controlled area; and  
g) a workplace handling a compact extracorporeal blood irradiator containing a sealed 
radioactive source.  
§ 21 
(1) A level  III w orkplace refers to  
a) a workplace handling a particle accelerator;  
b) a workplace handling equipment containing a sealed radioactive source that is designed 
for radiotherapy, including brachytherapy, and that is a significant source of ionising 
radiation;  
c) an app roved stock;  
d) a workplace handling equipment containing a sealed radioactive source that is designed 
for the irradiation of objects, including food and raw materials, objects of common use or 
other objects; and  
e) a workplace where activities related to the ex traction of a radioactive mineral are 
handled.  
(2) A level  IV workplace refers to  
a) a workplace handling a nuclear installation; and  
b) a workplace handling a nuclear waste repository that is not a nuclear installation.  
(3) The criterion for the categorisation of a wor kplace handling an unsealed radioactive 
source, with the exception of the workplaces provided in subsection  1(e) and subsection  2, 
consists of providing the workplace with ventilation, insulation and shielding equipment 
along with drainage. The requirement s for standard workplace equipment for the purposes of 
its categorisation are specified in Annex  9 to this implementing decree.  
§ 22 
Categorisation of exposed workers  
(For the implementation of §  61(6)(d) of the Atomic Act)  
(1) The categori sation of an exposed worker as category  A or B shall take into account 
the following  
a) the expected exposure of the exposed worker under normal operations; and  
b) the potential exposure of the exposed worker.  
(2) Category  A exposed worker refers to an exposed worke r who could be exposed  
a) to an effective dose exceeding 6  mSv per year,  
b) to an equivalent dose exceeding 15  mSv per the eye lens; or  
c) to an equivalent dose exceeding 3/10 of the exposure limit for the skin and the 
extremities.  
(3) Category  B exposed worker refers to exposed workers other than those provided in 
subsection  2 provided that the Atomic Act requires their categorisation.  
CELEX: 32013L0059  - 13 - 
 
 Part 4 
Quantities and facts relevant to radiation protection  
§ 23 
List of quantities and facts re levant to radiation protection  
(For the implementation of §  25(2)(a) of the Atomic Act)  
(1) Quantities relevant to radiation protection refer to the quantities  
a) used to determine an individual dose for an individual;  
b) characterising the field of ionising radiati on and the occurrence of radionuclides in the 
workplace;  
c) characterising the effluents of radionuclides into the environment of the workplace;  
d) characterising the field of ionising radiation and the occurrence of radionuclides in the 
environment of the workp lace;  
e) used to evaluate the characteristics of a source of ionising radiation;  
f) characterising the source of ionising radiation; and  
g) used to evaluate exposure from a natural source of radiation.  
(2) Facts relevant to radiation protection refer to the following  
a) characteristics of a source of ionising radiation;  
b) protective characteristics of personal protective equipment and other protective aids and 
equipment intended for work with a source of ionising radiation;  
c) characteristics of packaging for the carriage, stor age or deposit of radioactive or fissile 
material;  
d) characteristics of accessories relevant to radiation protection;  
e) facts demonstrating the type approval in the case of a source of ionising radiation subject 
to type approval;  
f) facts provided in the certific ate of a sealed radioactive source;  
g) facts provided in the accompanying document for an unsealed radioactive source;  
h) information on the employed methods and monitoring of the persons, workplace, 
workplace environment and effluents along with results of such  monitoring;  
i) facts demonstrating the familiarisations of an exposed worker with the risk of their work;  
j) facts demonstrating the instruction of persons entering the controlled area;  
k) facts demonstrating the testing of an exposed worker's knowledge of the saf e 
management of a source of ionising radiation and an exposed worker's’ competence in 
this respect by regular testing;  
l) conclusions of prophylactic medical check -ups to verify the medical fitness of category  A 
exposed workers;  
m) facts demonstrating a failure to adhere to requirements for radiation protection discovered 
within the framework of systematic surveillance;  
n) data concerning exposed worker, workplaces and the results of the exposed worker 
individual monitoring of s;  
o) data recorded in the personal radiat ion passport;  
p) data on the entry and period of stay of individuals in the controlled area;  
q) results of the inventory of sealed radioactive sources; and  
r) facts stated in measurement reports issued by the licensee pursuant to §  9(2)(h)(2) and (5) 
through (7) of  the Atomic Act.  - 14 - 
 
 § 24 
Scope of monitoring, measurement, evaluation, verification and recording of quantities 
and facts relevant to radiation protection  
(For the implementation of §  25(2)(b) of the Atomic Act)  
(1) The characteristics of a so urce of ionising radiation shall be monitored, measured, 
evaluated, verified and recorded  
a) during production, import or distribution within the scope necessary for  
1. the assessment of the conformity of a source of ionising radiation with the approved 
type;  
2. the assessment of the compliance of a source of ionising radiation with the 
requirements imposed by the applicable technical regulations;  
3. the issuance of a certificate for a sealed radioactive source; or  
4. the issuance of an accompanying document for an unseal ed radioactive source;  
b) upon the takeover of a source of ionising radiation and before the commencement of its 
use in the form of an acceptance test; and  
c) during the use of a source of ionising radiation in the form of  
1. a test of long -term stability; and  
2. a test of operational reliability.  
(2) The facts demonstrating type approval, facts recorded in the certificate of a sealed 
radioactive source and facts recorded in the accompanying document for an unsealed 
radioactive source shall be recorded within the scope nec essary for keeping records on 
sources of ionising radiation.  
(3) The facts demonstrating the familiarisations of an exposed worker with the risk 
related to their work and facts demonstrating the instruction of persons entering the controlled 
area shall be moni tored and recorded within the scope specified by §  52, and data on entries 
and periods of stay of individuals in the controlled area shall be monitored and recorded 
within the scope specified by §  35(3).  
(4) The facts demonstrating the testing of an exposed wo rker's’ knowledge of the safe 
management of a source of ionising radiation and their competence in this respect by regular 
testing shall be monitored and recorded within the scope specified by §  52. 
(5) The data recorded in the personal radiation passport shal l be monitored, evaluated and 
recorded within the scope specified by §  38. 
(6) The results of the inventory of sealed radioactive sources shall be recorded within the 
scope specified by §  43. 
Facts provided in the certificate of a sealed radioactive source  
(For the implementation of §  25(2)(b) of the Atomic Act)  
§ 25 
The facts provided in the certificate of a sealed radioactive source shall be recorded 
within the following scope:  
a) the identification number of the certificate of the sealed rad ioactive source;  
b) the serial or identification number of the sealed radioactive source;  
c) the manufacturer and the country of origin of the sealed radioactive source;  
d) the designation of the approved type with whose characteristics the characteristics of the 
sealed radioactive source are in conformity;  - 15 - 
 
 e) data on the radionuclide type;  
f) data on the activity of the sealed radioactive source along with the date that the activity is 
related to, and data on the highest content of the basic radionuclide;  
g) in the case of a significant source of ionising radiation, the kerma rate in the air along 
with the date that the kerma rate is related to;  
h) data on the chemical and physical form of the radionuclide and its carrier;  
i) data on the dimensions of the sealed radioactive source ; 
j) data on sealing in a capsule or protective cover;  
k) the grade of resistance of the sealed radioactive source compared to the approved type;  
l) the results of the performed tests of radioactive contamination and the tightness of the 
sealed radioactive source;  
m) the recommended time of use for the sealed radioactive source;  
n) the date of issue of the certificate of the sealed radioactive source; and  
o) identification details of the person who issued the certificate of the sealed radioactive 
source, and the signature of  authorised this person’s representative.  
§ 26 
In the case of a sealed radioactive source that cannot be designated with a mark and a 
serial number and that is not a high -activity source, for all sealed radioactive sources of the 
same t ype and of the same size containing the same quantity of the same radionuclides 
managed by the same person, facts provided in the certificate of the sealed radioactive source 
shall be recorded within the following scope:  
a) the identification number of the ce rtificate of the sealed radioactive source;  
b) the number of sealed radioactive sources of the same licensee;  
c) the designation of the approved type with whose characteristics the characteristics of the 
sealed radioactive source are in conformity;  
d) information o n the radionuclide type;  
e) information on the activity of the sealed radioactive sources along with the specification 
of the date that the activity is related to;  
f) information on the highest content of the basic radionuclide in the sealed radioactive 
sources;  
g) data on the chemical and physical form of the radionuclide and its carrier;  
h) data on the dimensions of the sealed radioactive sources;  
i) data on sealing in a capsule or protective cover;  
j) the grade of resistance of the sealed radioactive sources compared to t he approved type;  
k) the results of the performed tests of radioactive contamination and the tightness of the 
sealed radioactive sources;  
l) the recommended time of use of the radioactive sources and other data for the planned 
verification of their tightness; an d 
m) the date of issue of the certificate of the sealed radioactive sources and the identification 
details of the person who issued the certificate of the sealed radioactive sources, and the 
signature of the person’s authorised representative.  
§ 27 
Facts provided in the accompanying document for an unsealed radioactive source  
(For the implementation of§  25(2)(b) of the Atomic Act)  
(1) The facts provided in the accompanying document for an unsealed radioactive source 
shall be recorded within th e following scope:  - 16 - 
 
 a) the identification number of the accompanying document for the unsealed radioactive 
source;  
b) the specification or identification number of the unsealed radioactive source;  
c) in the case of an unsealed radioactive source subject to the appro val of the type, the 
designation of the approved type with whose characteristics the characteristics of the 
unsealed source are in conformity;  
d) information on the radionuclide type;  
e) data on the chemical and physical form of the radionuclide and its carrier;  
f) data on the activity and activity weight concentration of the unsealed radioactive source 
along with the specification of the time that the data are related to;  
g) data on chemical and radiochemical purity, if available;  
h) data on the type of package of the un sealed radioactive source;  
i) date of issue of the accompanying document for the unsealed radioactive source;  
j) changes in the facts provided in paragraphs  d through i),; and  
k) identification details of the person who issued the accompanying document for the 
unsealed radioactive source, and the signature of the authorised person’s representative.  
(2) For the same radioactive sources handed over together, the facts provided in the 
accompanying document for an unsealed radioactive source shall be recorded within the 
scope specified in subsection  1, and for each radionuclide or for each mixture of radionuclides 
a total number of handed -over unsealed radioactive sources shall be specified.  
(3) If objects or substances contaminated by radionuclides from a nuclear installation o r 
workplace during the operation of which radionuclides are generated or concentrated are 
handed over to a different person, the facts stated in the accompanying document for an 
unsealed radioactive source shall be recorded within the following scope:  
a) data pursuant to subsection  1(a), (b), (d), (h), (i) and (k),  
b) data on activity and the highest dose equivalent rate at a distance of 0.1  m from the 
surface; and  
c) data on the highest surface activity per 100  cm2 of the surface in the case of surface 
contaminatio n by radionuclides.  
CELEX: 32013L0059  
Part 5 
Tests of a source of ionising radiation  
§ 28 
Acceptance test  
(For the implementation of §  68(2)(a) of the Atomic Act)  
(1) The acceptance test shall be performed after the installation of a source  of ionising 
radiation before the commencement of its use.  
(2) The acceptance test shall include  
a) a visual check of the integrity and undamaged state of the source of ionising radiation;  
b) in the case of an unsealed radioactive source, the verification of data pr ovided in the 
accompanying document for the unsealed radioactive source issued by the manufacturer 
pursuant to §  27(1)(a) and (b),  
c) in the case of a sealed radioactive source  
1. the verification of data provided in the certificate of a sealed radioactive sourc e; and  - 17 - 
 
 2. the test of the tightness, including the determination of measurement uncertainty; the 
scope and method of the performance of the tightness test for a sealed radioactive 
source is specified in Annex  10 to this implementing decree;  
d) in the case of equ ipment with a sealed radioactive source  
1. the verification of the functionality of the equipment with the sealed radioactive 
source;  
2. the verification of the functionality of the control, actuating, safety, alarm and 
indicating systems;  
3. the verification of th e operating parameters and characteristics of the equipment with 
the sealed radioactive source;  
4. the determination of dosimetric quantities relevant in respect of the purpose of the 
use of such equipment, including their deviations in the case of radiothera py; 
5. the test of the tightness for a sealed radioactive source bay smear test on a substitute 
surface, including the determination of the measurement uncertainty; the scope and 
method of the performance of the smear test on a substitute surface are specifie d in 
Annex  10 to this implementing decree; and  
6. the measurement or estimate of scattered and leaking ionising radiation in the 
environment of the equipment containing a sealed radioactive source;  
e) in the case of a radiation generator  
1. the verification of the radiation generator functionality;  
2. the verification of the functionality of the control, actuating, safety, alarm, indicating 
and imaging systems;  
3. the verification of the operating parameters and characteristics of the radiation 
generator;  
4. the determinatio n of dosimetric quantities relevant in respect of the purpose of use of 
the radiation generator, including their deviations in the case of radiotherapy;  
5. the measurement of scattered and leaking ionising radiation in the environment of the 
radiation generat or or estimate thereof, if a dental intraoral and a dental panoramic 
X-ray device is concerned; and  
f) the verification of all data provided by the manufacturer that is relevant to radiation 
protection in respect of the possible method of the equipment use.  
(3) In the case of a source of ionising radiation subject to type approval, the acceptance 
test shall be performed within the scope specified in subsection  2 and the decision on 
approval of the type of product.  
(4) The person performing the acceptance test shall a dapt its scope to the specific purpose 
of the use and specific characteristics of the source of ionising radiation and its accessories 
that are relevant to radiation protection.  
CELEX: 32013L0059  
Test of long -term stability  
(For the implementation of §  68(2)(a) of the Atomic Act)  
§ 29 
(1) The test of long -term stability shall be performed  
a) regularly, with a minimum frequency  
1. once every 12 months in the case of a source of ionising radiation designed for 
medical exposure in radiotherapy;  - 18 - 
 
 2. once every 12 months in the case of a significant source of ionising radiation 
designed for medical exposure in radiodiagnostics or interventional radiology;  
3. once every 12 months in the case of a mobile flaw detector with a sealed radioactive 
source;  
4. specified in Annex  11 to this implementing decree in the case of a sealed radioactive 
source that is not part of equipment with a sealed radioactive source or that can be 
removed from such equipment to carry out an independent test of long -term stability;  
5. once every  24 months in the case of a significant source of ionising radiation not 
stated in paragraphs  1 through 4; and  
6. once every 36 months in the case of a simple source of ionising radiation not stated 
in paragraphs  1 through 4;  
b) if there is a reasonable suspicio n of the improper functionality of the source of ionising 
radiation or its accessories relevant to radiation protection;  
c) if there is a suspicion of leakage of the sealed radioactive source;  
d) if the results of operational reliability tests indicate or demons trate the improper 
functionality of the source of ionising radiation or its accessories relevant to radiation 
protection;  
e) after maintenance, repair or other service intervention that could affect any characteristic 
verified during the test of long -term sta bility or any parameter verified during thereof;  
f) after the replacement of the accessories of the source of ionising radiation relevant to 
radiation protection; and  
g) after the removal of any defect discovered during the test of long -term stability.  
(2) The test of long -term stability performed according to subsection  1(a) shall be carried 
out no later than in the calendar month in the course of which the time limit for the test 
performance expires.  
CELEX: 32013L0059  
§ 30 
(1) The test of long -term stability shall include  
a) a visual check of the integrity and undamaged state of the source of ionising radiation;  
b) in the case of a sealed radioactive source  
1. the verification of data provided in the certificate of a sealed radioactive source; and  
2. the test of  the tightness, including the determination of measurement uncertainty; the 
scope and method of the performance of a tightness test for a sealed radioactive 
source is specified in Annex  10 to this implementing decree;  
c) in the case of equipment with a sealed  radioactive source  
1. the verification of the functionality of the equipment with the sealed radioactive 
source;  
2. the verification of the functionality of the control, actuating, safety, alarm and 
indicating systems;  
3. the verification of the operating paramete rs and characteristics of the equipment with 
the sealed radioactive source and stability thereof;  
4. the determination of dosimetric quantities relevant in respect of the purpose of such 
equipment, the verification of their stability, and their deviations in the case of 
radiotherapy;  
5. the test of the tightness for a sealed radioactive source by a smear test on a substitute 
surface, including the determination of measurement deviation; the scope and 
method of the performance of the smear test on a substitute sur face are specified in 
Annex  10 to this implementing decree; and  - 19 - 
 
 6. the measurement or estimate of scattered ionising radiation in the environment of the 
equipment with the sealed radioactive source in the case of a change in its use that 
could affect the valu es provided in the last measurement and an estimate of scattered 
and leaking ionising radiation;  
d) in the case of a radiation generator  
1. the verification of the functionality of the radiation generator;  
2. the verification of the functionality of the control, ac tuating, safety, alarm, indicating 
and imaging systems;  
3. the verification of the operating parameters and characteristics of the radiation 
generator and their stability;  
4. the determination of dosimetric quantities relevant in respect of the purpose of the 
radiation generator, the verification of their stability, and their deviations in the case 
of radiotherapy; and  
5. the measurement of scattered ionising radiation in the environment of the radiation 
generator or in the case of a dental intraoral and dental pano ramic X -ray device, its 
estimate, if a change in its use that could affect the values provided in the last 
measurement or estimate of scattered and leaking ionising radiation occurred;  
e) in the case of a source of ionising radiation subject to type approval , the tests within the 
scope defined in the decision on the product type; and  
f) in the case of the test of long -term stability after replacement of the accessories of a 
source of ionising radiation affecting radiation protection, the verification of the 
correctness of the data provided in technical documentation for such accessories that are 
relevant to the common use of the source of ionising radiation or its accessories from the 
point of view of radiation protection.  
(2) The person performing the test of long -term stability shall adapt its scope to the 
specific purpose of the use and specific characteristics of the source of ionising radiation and 
its accessories that are relevant to radiation protection.  
CELEX: 32013L0059  
§ 31 
(1) The test of lo ng-term stability performed pursuant to §  29(1)(b) through (g) can be 
performed within a limited scope so that in the case pursuant to  
a) § 29(1)(b), any suspicion of the improper functionality of the source of ionising radiation 
or its accessories relevant t o radiation protection is either confirmed or disproved;  
b) § 29(1)(c), any suspicion of the leakage of the sealed radioactive source is either 
confirmed or disproved;  
c) § 29(1)(d), the characteristics of the source of ionising radiation or its accessories 
relevant to radiation protection that can be related to the results of the test of operational 
reliability can be verified;  
d) § 29(1)(e), the characteristics and parameters verified during the test of long -term 
stability that could be affected by maintenance, re pair or service intervention can be 
verified;  
e) § 29(1)(f), the characteristics and parameters verified during the test of long -term stability 
that could be affected by the replacement of the accessories of the source of ionising 
radiation relevant to radiat ion protection can be verified; and  
f) § 29(1)(g), it can be verified whether  
1. any defects discovered during the previous test of long -term stability have been 
removed; and  
2. that no new defect resulted from the removal of such a defect.  - 20 - 
 
 (2) The test of long -term st ability carried out within the limited scope pursuant to 
subsection  1 (hereinafter referred to as “partial test of long -term stability”) cannot replace the 
test of long -term stability pursuant to §  29(1)(a).  
CELEX: 32013L0059  
§ 32 
Evalu ation of the test of long -term stability and removal of defects  
(For the implementation of §  68(2)(g) of the Atomic Act)  
(1) Any defects discovered during the test of long -term stability are categorised as very 
significant or less significant. The rules of the  categorisation of defects discovered during the 
test of long -term stability are specified in Annex  12 to this implementing decree.  
(2) The test of long -term stability is regarded as successful  
a) if no defects are discovered during the test;  
b) for the period until  the expiry of the time limit for the removal of a less significant defect 
discovered during the test of long -term stability; or  
c) if no defects were discovered during the partial test of long -term stability executed 
pursuant to §  31(1)(f).  
(3) The test of long -term stability is regarded as unsuccessful if  
a) a very significant defect was discovered during the test; or  
b) a less significant defect failed to be removed within the time limit and its removal failed 
to be confirmed by a successful test of long -term stabili ty or a successful partial test of 
long-term stability.  
(4) If a very significant defect is discovered during the test of long -term stability, the 
person who performs the test shall immediately inform the licensee or the registrant of this 
fact in writing and state this fact in the report of the test of long -term stability.  
(5) The time limit for the removal of a less significant defect shall be specified by the 
person who performs the test of long -term stability during which such a defect was 
discovered. The perso n shall inform the licensee or the registrant of the time limit for removal 
of a less significant defect and state it in the report of the test of long -term stability along with 
any operating limitations arising from the discovered defect.  
(6) When determining  the time limit for the removal of a less significant defect, the 
character of the discovered less significant defect and the method of common use of the 
source of ionising radiation and its accessories relevant to radiation protection shall be taken 
into account.  
(7) The time limit for the removal of a less significant defect shall not exceed three 
months and shall start running as of the date of execution of the test of long -term stability 
during which such a defect was discovered.  
CELEX: 32013L0059  
Test of o perational reliability  
(For the implementation of§  68(2)(b) through (f) of the Atomic Act)  
§ 33 
(1) The registrant shall execute tests of operational reliability within the scope and with 
frequency provided in Annex  13 to this implementing decree.  - 21 - 
 
 (2) The licensee shall specify the scope and frequency of operational reliability tests to 
cover  
a) a visual check of the integrity and undamaged state of the source of ionising radiation;  
b) the verification of the characteristic operating parameters and ch aracteristics of the source 
of ionising radiation and its accessories relevant to radiation protection; and  
c) in the case of a sealed radioactive source or equipment, the test of the tightness of a 
sealed radioactive source, namely  
1. regularly, at least once e very 12 months;  
2. if used in a chemically aggressive environment or where there is an increased risk of 
mechanical damage, at least once every three months; and  
3. upon every cleaning.  
(3) The scope and method of the performance of a tightness test for a sealed rad ioactive 
source is specified in Annex  10 to this implementing decree.  
(4) When determining the scope and frequency of tests of operational reliability, the 
licensee shall take into account  
a) the condition of the source of ionising radiation and its accessories r elevant to radiation 
protection;  
b) the common methods of use and operation of the source of ionising radiation and its 
accessories relevant to radiation protection;  
c) the scope and frequency of such tests, which are  
1. specified in the manufacturer's instructions ; 
2. provided in the decision on the type approval for the source of ionising radiation; or  
3. specified in the report of the acceptance test or test of long -term stability; and  
d) rules of good practice ensuring radiation protection when using the source of ionisi ng 
radiation.  
CELEX: 32013L0059  
§ 34 
(1) Tests of operational reliability for a source of ionising radiation used for medical 
exposure  
a) with a frequency greater than once a month shall be performed by  
1. a physician who commonly describes X -ray images on the monitor within the 
framework of clinical practice, provided that a test of operational reliability 
consisting in the inspection of the functionality of the respective diagnostic monitor 
in radiodiagnostics is concerned;  
2. a radiology assistant , radiology technician, biomedical engineer, biomedical 
technician or medical physics expert who uses the source of ionising radiation in 
clinical practice, provided that a test of operational reliability of the source of 
ionising radiation used in radioth erapy is concerned; or  
3. a radiology assistant who uses the source of ionising radiation in clinical practice, or 
a radiology technician, provided that a test of operational reliability of the source of 
ionising radiation used in computed tomography is conce rned;  
b) with a frequency equal to or greater than once a month shall be performed by  
4. a healthcare professional who uses the source of ionising radiation in clinical 
practice, provided that a test of operational reliability of the source of ionising 
radiation  used in interventional radiology, dental radiodiagnostics or bone 
densitometry is concerned; or  - 22 - 
 
 5. a radiology assistant who uses the source of ionising radiation in clinical practice, or 
a radiology technician, provided that a test of operational reliabilit y of the source of 
ionising radiation used in mammography, fluorography or fluoroscopy not consisting 
in the inspection of the respective diagnostic monitor in radiodiagnostics is 
concerned; and  
c) with a frequency equal to or less than once a month, shall be  executed by a radiology 
technician or medical physics expert, provided that a test of operational reliability of the 
source of ionising radiation used in radiotherapy is concerned.  
(2) The person obliged to ensure the verification of the characteristics of th e source of 
ionising radiation by a test of operational reliability, the continuous evaluation of the results 
of such a test, and in the case of unsatisfactory results the implementation of corrective 
measures, refers to  
a) a clinical medical physics expert, provided that their availability is required according to 
a different legal regulation; or  
b) unless the availability of a medical physics expert is required pursuant to a different legal 
regulation;  
1. a supervisor, provided that the source of ionising radiatio n is managed by the 
licensee; or  
2. the person providing for radiation protection for the registrant, provided that the 
source of ionising radiation is managed by the registrant.  
(3) The person obliged to determine the scope and frequency of tests of operational 
reliability for the licensee refers to  
a) a medical physics expert, provided that their availability is required according to a 
different legal regulation; or  
b) a supervisor, unless the availability of a medical physics expert is required pursuant to a 
differen t legal regulation.  
(4) Evaluation of the results of the test of operational reliability shall be  
a) carried out immediately after the test performance;  
b) recorded in writing; and  
c) immediately submitted to the person specified in subsection  2. 
(5) If, based on the resul ts of the test of operational reliability, any corrective measures 
have been implemented, all workers using the source of ionising radiation in common 
operation shall be informed of such results of the test of operational reliability, including the 
correct ive measures arising therefrom.  
CELEX: 32013L0059  
Part 6 
Keeping records  
§ 35 
Keeping records on individual doses by the licensee  
(For the implementation of §  25(2)(b) and (c) of the Atomic Act)  
(1) The licensee shall keep the following rec ords in the register of individual doses of 
category  A exposed workers:  
a) surname;  - 23 - 
 
 b) name, or names where applicable;  
c) personal identification number, if assigned, or date of birth;  
d) the magnitude of individual doses and other information related to individual d oses 
received from the licensee for the performance of individual dosimetry; and  
e) information characterising exposure specified in the monitoring programme.  
(2) The information pursuant to subsection  1 shall be kept on file throughout the time a 
work activity i nvolving ionising radiation exposure is performed, and subsequently until the 
time when the exposed worker reaches or would have reached 75 years of age, however no 
shorter than 30 years after the termination of the work activity during which the exposed 
worker was exposed to ionising radiation.  
(3) The controlled -area operator shall record any entry of individuals who are not 
category  A exposed workers into this area. The following records shall be kept on file in 
respect of the registration of entry into the controlled area:  
a) surname;  
b) name, or names where applicable;  
c) date of birth;  
d) time of stay;  
e) results of individual monitoring, provided that such results are available; and  
f) a conservative estimate of the effective dose unless the information pursuant to 
paragra ph e is available.  
(4) The information pursuant to subsection  3 shall be kept on file by the controlled -area 
operator for 10 years.  
(5) Individual doses from extraordinary exposure and from emergency exposure shall be 
recorded independently.  
(6) The licensee shall sub mit to the Office the following information on the exposure of 
exposed workers:  
a) personal data of category  A exposed workers and data characterising their expected 
exposure within one month as of the commencement of the work activity during which 
the expose d worker is exposed to ionising radiation, and upon any change in such data; 
the list of this data is specified in Annex  14 to this implementing decree;  
b) data on the individual doses for all category  A exposed workers within two months of the 
end of a monit oring period; and  
c) an annual summary of the individual doses for all category  A exposed workers by 
31 March of the current year for the preceding year.  
(7) The information pursuant to subsection  6 shall be submitted to the Office in a 
machine -readable electroni c format allowing database processing.  
(8) The licensee shall immediately submit to the Office the following information on  
a) effective doses from external exposure exceeding a value of 10  mSv or effective doses 
per the eye lens from external exposure exceeding 10 mSv or the equivalent dose of 
150 mSv for the extremities or the skin, attained over the monitoring period or on a one -
time basis, along with an evaluation of the causes of such a situation and conclusions 
reached;  
b) effective doses from external exposure  exceeding a value of 15  mSv or effective doses 
per the eye lens from external exposure exceeding 15  mSv or the equivalent dose of 
300 mSv for the extremities or the skin, attained by summing up the doses received in - 24 - 
 
 individual monitoring periods, along wi th an evaluation of the causes of such a situation 
and conclusions reached; and  
c) the committed effective dose from internal exposure exceeding 6  mSv, on a one -time as 
well as summary basis, along with the evaluation of the causes of such a situation and 
conclusions reached.  
(9) The notification pursuant to subsection  8(a) or (b) shall be carried out also in the case 
that the dosimeter was placed on the protective apron. The attenuation caused by the apron 
shall be taken into account within the framework of the e valuation of the causes of such a 
situation.  
CELEX: 32013L0059  
§ 36 
Keeping records on individual doses by the licensee to carry out individual dosimetry  
(For the implementation of §  25(2)(b) and §78(3)(a) of the Atomic Act)  
(1) To carry ou t individual dosimetry, the licensee shall keep records on individual doses 
of category  A exposed workers at least for the whole calendar year following the year in 
which the record was made.  
(2) To carry out individual dosimetry, the licensee shall submit the  results of the 
evaluation of category  A exposed workers' exposure to the licensee for whom individual 
dosimetry was carried out and to the Office, immediately upon  
a) the evaluation of the dosimeter due to unplanned single exposure;  
b) a discovery of  
1. an effecti ve dose from external exposure exceeding 10  mSv,  
2. an equivalent dose from external exposure exceeding 10  mSv for the eye lens or 
150 mSv for the equivalent dose for the extremities or the skin; or  
3. the committed effective dose from internal exposure exceedin g 6 mSv.  
(3) To carry out individual dosimetry, the licensee shall inform the Office within one 
month of the date of effect or expiry of the contract on the execution of individual dosimetry 
concluded with the licensee being a holder of a licence to manage a s ource of ionising 
radiation.  
CELEX: 32013L0059  
Personal radiation passport  
(For the implementation of §  79(9) of the Atomic Act)  
§ 37 
(1) The person obliged to ensure radiation protection for an outside worker shall apply to 
the Office to i ssue a personal radiation passport before this worker starts performing radiation 
activities. The applicant shall attach a photograph with dimensions 3.5 × 4.5  cm to the 
application for the issuance of a personal radiation passport.  
(2) The personal radiation passport consists of the following  
a) part A, intended for continuous records on doses and valid until exhausted, however, no 
later than 10 years as of the issue of the personal radiation passport; and  
b) part B, intended for records on doses in the current cale ndar year and valid for the current 
year.  - 25 - 
 
 (3) The validity of the personal radiation passport shall expire  
a) upon the outside worker's death; or  
b) upon the expiry of the licence, if the outside worker is also the licensee.  
(4) A specimen of the personal radiation pass port is specified Annex  15 to this 
implementing decree.  
CELEX: 32013L0059  
§ 38 
(1) The person obliged to ensure radiation protection for an outside worker shall  
a) apply to the Office for a new part B of the personal radiation passport no late r than by 
30 November of the preceding calendar year,  
b) submit to the Office no later than by 28  February of the subsequent calendar year part B 
of the personal radiation passport where all doses received by an outside worker in the 
previous calendar year ar e recorded along with the total annual individual dose evaluated 
and confirmed by the licensee who applied for the issue of the personal radiation 
passport;  
c) immediately inform the Office of a loss of the personal radiation passport;  
d) immediately apply to th e Office for the issuance of a new personal radiation passport in 
the case of loss of the personal radiation passport and complete all details from the lost 
personal radiation passport in the newly issued one;  
e) submit part  A of the personal radiation passpo rt to the Office upon its exhaustion;  
f) apply to the Office for the issue of a new personal radiation passport no later than 30 days 
before the expected expiry of the personal radiation passport's validity;  
g) submit the personal radiation passport to the Offic e no later than 30 days after the 
termination of the outside worker's employment or the termination of the person's own 
activity if the person obliged to ensure radiation protection is the outside worker;  
h) inform the Office of any change in details provided  in paragraphs  1, 7 or 8 of part  A of 
the personal radiation passport and submit the personal radiation passport to the Office to 
record such changes;  
i) record in part  A of the personal radiation passport doses received for the previous four -
year period so t hat it is always possible to monitor the five -year total individual dose of 
the outside worker;  
j) record in part  B of the personal radiation passport, which was issued in the course of a 
calendar year, all individual doses received by an outside worker until  the issue of the 
personal radiation passport so that it is possible to evaluate the total annual individual 
dose received by the outside worker;  
k) record in part  B of the personal radiation passport the monthly summaries of individual 
doses received by the outside worker, including the results of monitoring from all 
controlled -area operators for whom the outside worker performed work activity in the 
calendar month concerned;  
l) record in part  A of the personal radiation passport total individual annual doses re ceived 
by the outside worker;  
m) record in the personal radiation passport the results of the outside worker's medical 
check -up performed pursuant to §  80(4) of the Atomic Act; and  
n) make a record on instructions and preparation of the outside worker pursuant t o § 52. 
(2) The operator of the controlled area where the outside worker performs work activity 
shall ensure in accordance with the monitoring programme for the operator's controlled area 
an evaluation of the individual dose received by the outside worker when  performing work - 26 - 
 
 activity in the operator's controlled area. The operator of the controlled area shall record the 
evaluated dose on a continuous basis, however, no later than at monthly intervals in part  B of 
the personal radiation passport of the outside worker.  
(3) If the operator of the controlled area pursuant to subsection  2 does not have all results 
of measurement before the completion of the outside worker's activity in the operator's 
controlled area, the operator shall submit such results immediately up on the evaluation of the 
dose to the person obliged to ensure radiation protection for the outside worker.  
CELEX: 32013L0059  
§ 39 
Keeping records on other quantities and facts relevant to radiation protection  
(For the implementation of § 25(2)(b) and (c) of the Atomic Act)  
(1) The licensee being a holder of the licence to manage a source of ionising radiation 
pursuant to §  9(2)(f)(8) of the Atomic Act and to provide services relevant to radiation 
protection pursuant to §  9(2)(h)(2) and (5) o f the Atomic Act shall submit to the Office within 
one month of the execution of measurement, evaluation or determination a report of the 
results for  
a) the measurement and evaluation of the characteristics of a source of ionising radiation;  
b) the determination  of individual doses for an exposed worker; or  
c) the measurement and evaluation of exposure from a natural source of radiation.  
(2) The documents demonstrating the conclusions of prophylactic medical check -ups to 
attest to category  A exposed worker's’ medical fi tness shall be kept on file until the time when 
an exposed worker reaches or would have reached 75 years of age, however no shorter than 
30 years after the termination of the work activity during which the exposed worker was 
exposed to ionising radiation.  
(3) The results of the monitoring of a level  IV workplace, being a workplace handling a 
nuclear installation, shall be kept on file for a period of  
a) the operation of such a workplace;  
b) the decommissioning of such a workplace; and  
c) 10 years after the workplace wa s decommissioned.  
(4) Unless this implementing decree or the implementing decree on radiation situation 
monitoring provides otherwise, quantities and facts relevant to radiation protection shall be 
kept on file for at least 10 years.  
CELEX: 32013L0059  
Keeping records on sources of ionising radiation by a licensee and registrant  
(For the implementation of§  25(2)(d) of the Atomic Act)  
§ 40 
(1) A licensee or registrant shall keep the following documents and records on each 
source of ionising radiat ion that they manage:  
a) a description of the source of ionising radiation enabling the source's’ unambiguous 
identification, including namely its name, type designation, manufacturer's’ name, serial 
or identification number;  - 27 - 
 
 b) the purpose of the management of sources of ionising radiation;  
c) licences and other decisions concerning the management of ionising radiation sources;  
d) operational records characterising the method and scope of the management of a source 
of ionising radiation; and for an unsealed radioactiv e source, its purpose and consumption 
balance; and  
e) records concerning the management of a source of ionising radiation acquired within the 
framework of systematic surveillance of radiation protection, and records of inspection 
activities.  
(2) A licensee or reg istrant shall also keep the following documents and records on each 
source of ionising radiation that they possess:  
a) the date of physical acceptance of the source of ionising radiation;  
b) a document attesting to the acquisition of the source of ionising radia tion; 
c) for a source of ionising radiation that is subjected to type approval, with the exception of 
a radioactive source, the declaration of conformity issued by its manufacturer, importer or 
distributor;  
d) in the case of a sealed radioactive source, the cert ificate of the sealed radioactive source;  
e) in the case of an unsealed source, the accompanying document issued upon the transfer of 
the source by its previous owner;  
f) the report of the acceptance test and reports on tests of long -term stability if such tests  are 
required for the source of ionising radiation;  
g) records with the results of measurements performed within the framework of tests of 
operational reliability and images resulting from the performance thereof;  
h) if the source of ionising radiation is transf erred to be possessed by a different person, the 
information on to whom and when the source was handed over, and in the case of an 
unsealed radioactive source also the accompanying document issued for such a transfer;  
i) if the radioactive source is subject t o clearance from the workplace, records made on its 
clearance from the workplace;  
j) if the radioactive source is disposed of as radioactive waste, a record on to whom and 
where it was handed over along with the accompanying document for radioactive waste 
issued for such handover; and  
k) for a high -activity source, a photograph or similar representation if provided so by the 
Atomic Act.  
(3) A report of the acceptance test shall be kept on file over the period of the use of the 
source of ionising radiation.  
(4) A report o f the test of long -term stability shall be kept on file until the next test of 
long-term stability is performed, however, at least for three years as of the performance of the 
test of long -term stability. If the test of long -term stability included the mea surement or 
estimate of scattered radiation in the environment of the source of ionising radiation, the 
report of this test of long -term stability shall be kept on file for the entire period of operation 
of the source of ionising radiation.  
(5) A record contai ning the results of measurements executed within the framework of 
operational reliability tests and images resulting from such tests shall be kept on file until the 
next test of long -term stability; however, at least for one year as of their acquisition.  
(6) Unless this implementing decree provides otherwise, the information pursuant to 
subsections  1 and 2 shall be kept on file at least for two years from the termination of the 
management of the source of ionising radiation.  
CELEX: 32013L0059  - 28 - 
 
 § 41 
(1) The holder of the licence to manage a source of ionising radiation and the registrant 
shall submit to the Office written information on the source of ionising radiation that they 
possess with the exception of a non -significant source of ionising rad iation and a minor 
source of ionising radiation whose type was approved by the Office, namely on  
a) a radiation generator no later than within one month of  
1. the successful completion of the acceptance test;  
2. a change in the information;  
3. transfer to the possessi on of a different person; and  
4. decommissioning;  
b) a sealed radioactive source no later than within one month of  
1. the physical takeover of a sealed radioactive source;  
2. a change in the information;  
3. transfer to the possession of a different person; and  
4. disposal t hereof as radioactive waste or different disposal thereof;  
c) equipment with a sealed radioactive source no later than within one month of  
1. the successful completion of the acceptance test;  
2. a change in the information;  
3. equipment transfer to the possession of a  different person; and  
4. equipment decommissioning.  
(2) The scope of information submitted to the Office pursuant to subsection  1 is provided 
by Annex  16 to this implementing decree.  
(3) The holder of the licence to manufacture, import, distribute or export a source  of 
ionising radiation and the registrant shall submit to the Office a written list summarising the 
manufactured, imported, distributed or exported sources of ionising radiation for the previous 
calendar quarter no later than within one month of the end of  the quarter. The scope of 
submitted information is specified in Annex  17 to this implementing decree.  
CELEX: 32013L0059  
§ 42 
Keeping records on sources of ionising radiation by a registrant  
(For the implementation of §  71(2) of the Ato mic Act)  
(1) The registrant shall make and keep the following records on a source of ionising 
radiation:  
a) a description of the source of ionising radiation enabling the source's’ unambiguous 
identification, including namely its name, type designation, manufactu rer's’ name, serial 
or identification number;  
b) the purpose of the use of the source of ionising radiation; and  
c) information contained in the instructions for use of the source of ionising radiation.  
(2) The registrant shall also keep the following records on a s ource of ionising radiation:  
a) the date of physical acceptance of the source of ionising radiation;  
b) information on the method of acquisition of the source of ionising radiation;  
c) information contained in the declaration of conformity issued by the manufacture r, 
importer or distributor of the source of ionising radiation;  - 29 - 
 
 d) for a sealed radioactive source, the information provided in the certificate of the sealed 
radioactive source;  
e) for an unsealed radioactive source, the information provided in the accompanying 
document for the unsealed radioactive source; and  
f) information on the location of the source of ionising radiation.  
(3) The registrant shall keep the records pursuant to subsections  1 and 2 for at least two 
years from the transfer to a different person or the d isposal of the source of ionising radiation.  
§ 43 
Inventory of sources of ionising radiation  
(For the implementation of §  69(2)(b) of the Atomic Act)  
(1) Inventory inspection shall be executed for sealed radioactive sources that are simple 
sources of ionising radiation or significant sources of ionising radiation.  
(2) Inventory inspection shall be performed  
a) on an annual basis, as of 31  March;  
b) immediately upon the declaration of the licensee's bankruptcy; and  
c) at least once a month in the case tha t a high -activity source that is part of a technological 
unit has not been used for a period exceeding 30 days.  
(3) Inventory inspection shall be performed within the following scope:  
a) in the case pursuant to subsection  2(a) or (b)  
1. the verification of documents  related to a sealed radioactive source; and  
2. the verification of the physical presence of a sealed radioactive source in the shield;  
b) in the case pursuant to subsection  2(c), the verification of the physical presence of a 
sealed radioactive source in the sh ield. 
(4) The licensee shall submit to the Office, by the end of the month following the 
performed inventory inspection pursuant to subsection  2(a) or (b), a report containing  
a) the serial number of the sealed radioactive source, the number of the certificate of  the 
sealed radioactive source and information on the radionuclide type;  
b) information on the type of shield in which the radioactive source is placed, and its serial 
number;  
c) the designation of the area or part of the technological system where the radioacti ve 
source is located; and  
d) the date of carrying out the inventory inspection.  
(5) The licensee shall record the result of the verification of physical presence of a sealed 
radioactive source pursuant to subsection  2(c). 
CELEX: 32013L0059  
§ 44 
Identification and designation of a high -activity source  
(For the implementation of §  89(2) of the Atomic Act)  
(1) The holder of the licence to manufacture or import a high -activity source shall  
a) provide the high -activity source with a unique identifier;  - 30 - 
 
 b) engrave, print or mark the identifier on the high -activity source otherwise in a permanent 
manner, if feasible;  
c) engrave, print or mark the identifier on the high -activity source's’ container; if this is not 
possible or in the case of reusable transport contain ers, the licensee shall provide the 
container with the characteristics of the high -activity source;  
d) provide the container for a high -activity source, and if practicable, also the high -activity 
source with a warning sign about radiation danger; and  
e) ensure t hat the documentation for each manufactured or imported type of high -activity 
source includes a photograph or any other similar representation of the high -activity 
source and its usually used container.  
(2) A person who possess a high -activity source shall ens ure that  
a) the high -activity source and its container are always accompanied by written information 
allowing the high -activity source along with its nature to be identified;  
b) the high -activity source and its container are, if practicable, designated and equip ped with 
a sign about radiation danger and that marks and signs remain legible; and  
c) the documentation for the high -activity source contains photographs, a technical drawing 
or any other similar representation of the high -activity source, its container, tra nsport 
container, the equipment that the high -activity source is part of, its accessories; a 
photograph or any other similar representation may not be provided if it cannot be 
acquired without dismantling the equipment.  
CELEX: 32013L0059  
Title  II 
Planned e xposure situations  
Part 1 
Systematic supervision of radiation protection  
§ 45 
Supervisor  
(For the implementation of §  72(5)(a) and (b) of the Atomic Act)  
(1) The supervisor in the workplace where the controlled area is delineated shall refe r to 
category  A exposed workers. In the remaining cases, supervisor refers to category  B exposed 
workers.  
(2) A supervisor shall perform the supervision of radiation protection  
a) by monitoring and evaluating the performance of the licensee's’ duties related to e nsuring 
all measures to be taken for  
1. the safe management of the source of ionising radiation;  
2. the performance of radiation activities;  
3. the safe operation of the workplace where radiation activity is performed; and  
4. the decommissioning of the workplace where  radiation activity is performed; and  
b) by providing assistance to the licensee in relation to  
1. the preparation and implementation of new activities pertaining to the provision of 
radiation protection; and  
2. the purchase of the source of ionising radiation, pro tective aids and equipment or 
measuring devices.  - 31 - 
 
 (3) A supervisor shall provide the licensee with, in particular, the following  
a) informing an exposed worker and a trainee preparing themselves in the controlled or 
supervised area for employment of facts relevant  to radiation protection;  
b) education of exposed workers;  
c) preparation of the monitoring programme, the execution of monitoring and evaluation of 
monitoring results according to the monitoring programme;  
d) keeping records on individual doses, including the sum of individual doses from all work 
activities by exposed workers;  
e) measurement or estimate of an effective dose for a person who entered the controlled 
area;  
f) performing the optimisation of radiation protection and specifying dose constraints;  
g) maintaining doc umentation for the licensed activity, including the management system or 
the programme for ensuring radiation protection;  
h) performing an evaluation of the method for ensuring radiation protection;  
i) keeping records on the sources of ionising radiation and ins truments relevant to radiation 
protection and maintaining records on their movement and condition;  
j) performing annual inventory inspections of the sources of ionising radiation;  
k) organising acceptance tests and tests of long -term stability and cooperation wi th the 
person performing such tests;  
l) a test of operational reliability, unless this implementing decree provides otherwise;  
m) investigation of radiation incidents, loss, theft or damage to the source of ionising 
radiation and the preparation of proposals for  corrective measures and verification of the 
corrective measures;  
n) addressing a radiological event;  
o) the monitoring and settlement of a non -conformity that is not a radiation incident in the 
area of radiation protection;  
p) the supervision of ensuring the provi sion of occupational health services to an exposed 
worker;  
q) operational communication with an exposed worker and a different person, if 
consultation with them is necessary considering the current radiation situation, so that the 
information is communicated clearly, in a comprehensible manner and without any undue 
delay; and  
r) the methodological guidance for radiation protection officers and coordination of their 
activities.  
CELEX: 32013L0059  
§ 46 
Radiation protection officer  
(For the implem entation of §  72(5)(c) and (d) of the Atomic Act)  
(1) A radiation protection officer in a workplace where the controlled area is delineated 
shall be a category  A exposed worker. In the remaining cases, radiation protection officer 
refers to category  B exposed workers.  
(2) A radiation protection officer shall supervise the performance of radiation activities in 
the licensee's workplace on a permanent basis and, in particular,  
a) cooperate with the supervisor;  
b) plan and prepare working procedures and prepare documents fo r the activities to be 
carried out;  - 32 - 
 
 c) inform an exposed worker and a different individual of the current situation and measures 
taken in response to a situation that has occurred;  
d) verify whether the exposed worker and the different individual entering the co ntrolled 
area when performing a radiation activity meet occupational requirements and technical 
administrative requirements aimed at ensuring radiation protection;  
e) participate in the investigation of a radiation incident;  
f) participate in the settlement of a ny non -conformity in the area of radiation protection that 
is not an incident; and  
g) communicate with an exposed worker and other individuals if a consultation with them is 
necessary considering the current radiation situation, or manage their activities, so  that 
the information is communicated clearly, in a comprehensible manner and without any 
undue delay.  
CELEX: 32013L0059  
§ 47 
Specialised radiation protection unit ensuring continuous supervision of radiation 
protection at an energy -generating nuclear installation  
(For the implementation of §  72(5)(e) of the Atomic Act)  
A specialised radiation protection unit ensuring continuous supervision of radiation 
protection at an energy -generating nuclear installation shall ensure at such an insta llation the 
activities pursuant to §  45(2) and (3), check the fulfilment of requirements for ensuring 
radiation protection and ensure in particular the following  
a) direct supervision of radiation protection for all individuals entering the controlled area;  
b) assessment and taking measures to ensure radiation protection of all individuals entering 
the controlled area;  
c) preparation  
1. of proposals for changes in documentation for the licensed activity related to 
radiation protection; and  
2. of internal regulations of th e licensee related to radiation protection;  
d) evaluation of the effect of effluents on the representative person and the inspection of the 
observance of authorised limits;  
e) investigation of events related to radiation protection, including the preparation of 
proposals for corrective measures to be taken and assistance provided by other 
departments of the licensee during the implementation of such corrective measures; and  
f) assistance provided by other departments of the licensee when managing a radiation 
inciden t. 
CELEX: 32013L0059  
Part 2 
Controlled and supervised areas  
Controlled area  
(For the implementation of §  73(3) of the Atomic Act)  
§ 48 
(1) The controlled area shall be delineated as part of the workplace  
a) integrated and clearly defined;  
b) structurally separated, if practicable; and  - 33 - 
 
 c) with protection against entry of any unauthorised person.  
(2) The controlled area shall designated at the entrance or the delineation marked  
a) by a sign about radiation danger;  
b) by the notice “Controlled area with sources of ionising radiation. No admittance 
unauthorised to persons”,; and  
c) information on the nature of the source of ionising radiation and the related risk.  
(3) The controlled area shall be delineated within the scope that includes all working 
places where it is no t possible to avoid that  
a) the average dose equivalent rate in the working place can be greater than 2.5  µSv/h per 
calendar year;  
b) the sum of the products of the activity volume concentrations for individual radionuclides 
in the air at the workplace and the c onversion factors h inh for intake by inhalation by an 
exposed worker can be greater than 2.5  µSv/m3 on average per year; or  
c) surface contamination in the workplace can be greater than the values of surface 
contamination specified in Annex  18 to this impleme nting decree.  
(4) The controlled area may be entered only by an individual who has received 
instruction about behaviour that does not endanger the person's’ health or the health of other 
individuals. For an individual who should undergo medical or non -medical exposure in the 
controlled area, the instruction pursuant to subparagraph  1 is not required.  
(5) A person younger than 18 years of age may enter the controlled area if the person is 
being trained there for their future work or is undergoing medical exposure or  non-medical 
exposure.  
(6) A pregnant woman may enter the controlled area if she is to undergo medical or non -
medical exposure there or if she works in the controlled area.  
(7) Work in the controlled area may only be performed by category  A exposed workers. 
A diff erent individual may perform, in the controlled area,  
a) necessary and accidental activities  
1. for the necessary period and  
2. under the supervision of a category  A exposed worker appointed by the controlled -
area operator; or  
b) in the case of a category  B exposed wo rker, activities consisting in helping an individual 
undergoing medical exposure.  
(8) The Office inspector may enter the controlled area on their own.  
(9) Cleaning or maintenance in the controlled area may be performed  
a) by a category  B exposed worker or a different  individual on their own in a workplace 
handling a radiation generator, a sealed radioactive source or equipment containing a 
sealed radioactive source provided that it is ensured that during their presence the 
equipment cannot be activated; or  
b) a category  B exposed worker in a level  II or level  III workplace handling an unsealed 
radioactive source provided that such a source is not handled in the workplace in their 
presence and if it has been confirmed by measurement that surface contamination in the 
workpl ace is lower than the values provided in Annex  18 to this implementing decree.  
CELEX: 32013L0059  - 34 - 
 
 § 49 
Radiation protection in the controlled area shall be ensured in the following way:  
a) the rooms and space in the controlled area of a wor kplace with a nuclear installation 
where the values provided in §  48(3) are exceeded on a permanent or temporary basis 
shall be designated with a sign providing the measured values of the dose rate of activity 
volume concentration for individual radionucli des; 
b) the surface contamination of workplaces or structural parts of the controlled area shall be 
lower than the values of radioactive contamination specified in Annex  18 to this 
implementing decree; if surface contamination during handling a source of ioni sing 
radiation exceeds these values, effective decontamination shall be performed;  
c) the controlled -area operator shall provide individuals entering the controlled area with 
personal protective equipment and aids suitable in respect of the radiation situatio n in the 
controlled area and the method of work to be performed and reasons for entering the 
controlled area;  
d) if during standard operation or in the case of foreseeable deviations from standard 
operation the dose equivalent rate in the controlled area can exceed 1  mSv/h, the 
controlled -area operator shall provide each individual entering the controlled area, with 
the exception of individuals who re to undergo medical exposure or non -medical 
exposure in the controlled area, with an operational signal dosimet er; 
e) if in the controlled area surface contamination of a person entering cannot be eliminated, 
it is possible to enter after changing they e their clothes and put on the clothes specified 
by the internal regulation of the controlled -area operator; when lea ving the controlled 
area a check for surface contamination of the individual shall be performed and if any 
surface contamination is discovered personal clean -up and decontamination shall be 
performed; if it is not possible to remove surface contamination, the individual can leave 
the controlled area under the conditions provided in the internal regulation of the 
controlled -area operator;  
f) if it is not possible to eliminate surface contamination of objects taken from the 
controlled area, a check of their surf ace contamination shall be performed along with 
their decontamination in the case that surface contamination is discovered;  
g) it is forbidden to smoke in the controlled area of a workplace handling an unsealed 
radioactive source; it is possible to eat and dr ink only in the case that considering the 
scope of the controlled area and the type of activity performed, it is not possible to leave 
the controlled area on a short -term basis; in such a case the controlled -area operator shall 
define a special area for co nsumption with the possibility to check surface contamination 
of individuals along with measures eliminating the contamination of food; and  
h) for an individual who is not an exposed worker and who is entering the controlled area, 
the controlled -area operator  shall specify in the monitoring programme operational values 
to ensure that dose constraints for members of the public will not be exceeded.  
CELEX: 32013L0059  
§ 50 
(1) Documentation for the licensed activity in the controlled area shall in clude the 
following  
a) the scope of the controlled area by providing a list of rooms and a schematic plan;  
b) justification proposed scope of the controlled area, in particular, by calculations and other 
evidence demonstrating the fulfilment of the requirements specified in this implementing 
decree and the Atomic Act;  - 35 - 
 
 c) a description of structural and technical safeguarding of the controlled area preventing 
access of an unauthorised individual;  
d) a description of ensuring radiation protection in the controlled area; and 
e) information on the expected number of individuals working in the controlled area and the 
method of their instruction as to risks related to work in the controlled area.  
(2) The documentation concerning the operation of the controlled area shall include  
a) instructions for entering the controlled area and conditions for entering the controlled 
area to be fulfilled by an exposed worker or a different individual;  
b) procedures for individual activities performed in the controlled area;  
c) procedures for the evaluation  of the exposure of different individuals entering the 
controlled area; and  
d) conditions for leaving the controlled area by an individual and taking objects out of the 
controlled area, including the method of decontamination.  
CELEX: 32013L0059  
§ 51 
Supervised area  
(For the implementation of §  74(4) of the Atomic Act)  
(1) The supervised area shall be delineated as part of the workplace  
a) integrated and clearly defined; and  
b) structurally separated, if practicable.  
(2) The supervised area shall be desig nated at the entrance or its delineation marked  
a) by a sign about radiation danger,  
b) by a notice that says“Supervised area with sources of ionising radiation”, and  
c) with information on the nature of the source of ionising radiation and the related risk.  
(3) Radiat ion protection in the supervised area shall be ensured in the following way:  
a) radiation activity may only be performed by a category  A exposed worker;  
b) for an individual who is not an exposed worker and who is entering the supervised area, 
the supervised -area operator shall specify in the monitoring programme operational 
values to ensure that dose constraints for members of the public will not be exceeded;  
c) the workplace in the supervised area shall be equipped with protective equipment and 
aids along with shi elding depending on the nature of the handled source of ionising 
radiation; and  
d) the surface contamination of the workplaces or structural parts of the supervised area 
shall be lower than the values of radioactive contamination specified in Annex  18 to this  
implementing decree; if surface contamination during the handling of the source of 
ionising radiation exceeds these values, effective decontamination shall be performed.  
(4) The documentation for operation of the supervised area shall include procedures for 
individual activities executed in the supervised area.  
CELEX: 32013L0059  - 36 - 
 
 Part 3 
Workers, documentation and evaluation of radiation protection  
Informing and preparing workers  
(For the implementation of §  68(2)(h) of the Atomic Act)  
§ 52 
(1) An exposed worker and an individual who is trained in the controlled area or 
supervised area for their future work shall be informed by the licensee or the registrant of the 
following  
a) the nature and scope of possible danger to their health, risks related to  work in an 
environment containing ionising radiation and possible damage to their health;  
b) the general procedures and principles of radiation protection and measures that shall be 
taken in relation to the respective activity;  
c) specific operating and working  conditions related to the workplace and work activity to 
which they may be assigned;  
d) importance of meeting the requirement for health protection and the technical and 
administrative requirements aimed at ensuring radiation protection;  
e) the importance of a safety culture for ensuring radiation protection; and  
f) the importance of early reporting on pregnancy and breastfeeding due to the risk arising 
from possible exposure of the foetus and infant if a woman is concerned.  
(2) The licensee or registrant shall make a record of the provision of information pursuant 
to subsection  1. The record shall be confirmed by the exposed worker or the individual who is 
trained in the controlled area or supervised area for their future work by their signature.  
(3) The licensee or regist rant shall provide for a system of continuous education for an 
exposed worker to ensure that the workers are familiar with  
a) general rules and procedures for radiation protection;  
b) measures concerning radiation protection when performing radiation activities during 
standard operation, under foreseeable deviations from such operation or upon the 
occurrence of a radiation incident; and  
c) internal regulations and documentation for licensed activities.  
(4) For an exposed worker working in the controlled area in a level  IV workplace, the 
system of continuous education shall include an introduction to internal regulations and 
documentation for the controlled area.  
(5) The exposed worker's’ knowledge and competence to perform radiation activities in a 
safe manner shall be teste d prior to the commencement of work and also at regular intervals, 
at least once a year in the form of an exam of which a record must be made. If the exposed 
worker fails the exam, a corrective measure shall be specified.  
(6) The record of the exam pursuant to  subsection  5 shall include the following  
a) the scope of tested knowledge;  
b) a list of names of all tested exposed workers;  
c) the date of the exam;  
d) criteria for the evaluation of the exam;  
e) the result of the exam; and  
f) a description of measures taken in case any o f the exposed workers fail the exam.  - 37 - 
 
 (7) Testing pursuant to subsection  5 is not required  
a) for an exposed worker who actively performs the role of the supervisor for the respective 
licensee; or  
b) for an exposed worker who, for the respective registrant, actively performs the role of the 
person providing the registrant's radiation protection.  
CELEX: 32013L0059  
Programme ensuring radiation protection  
(For the implementation of §  24(7) of the Atomic Act)  
§ 53 
The programme ensuring radiation prote ction shall include  
a) a description of the licensed activity;  
b) the place of the performance of the licensed activity;  
c) the specification of the types of sources of ionising radiation within the framework of the 
licensed activity;  
d) a description of the organisat ional structure of the person performing the licensed 
activity;  
e) rights, duties and mutual relationships between individuals who manage, perform or 
evaluate the licensed activity;  
f) a description of the method of documentation and records management within th e 
framework of the licensed activity, including a list of such documentation and records;  
g) a description of the method of the submission of information to the Office;  
h) a description of the method of addressing non -conformities, including the application of 
corrective measures and the evaluation of their effect;  
i) a description of the system of informing and educating an exposed worker in the field of 
radiation protection and readiness to response to a radiation incident and testing their 
knowledge; and  
j) a descri ption of the scope of monitoring, measurement, evaluation, verification and 
recording quantities and facts relevant to radiation protection.  
CELEX: 32013L0059  
§ 54 
The programme ensuring radiation protection shall also include for  
a) the m anagement of sources of ionising radiation in a level  I or level  II workplace  
1. a description of the method of ensuring occupational health services for exposed 
workers;  
2. a description of ensuring metrologically correct measurements and measuring 
devices;  
3. a description of the method of ensuring acceptance tests and tests of long -term 
stability;  
4. the scope and description of the method of the performance of tests of operational 
reliability; and  
5. the frequency of tests of operational reliability;  
b) the management o f sources of ionising radiation in a workplace handling unsealed 
radioactive sources  
1. the principles of radioactive waste management;  
2. the principles of the clearance of radioactive substances from a workplace; and  - 38 - 
 
 3. the principles of using personal protective  equipment and aids, their characteristics 
and a description of the system of their assignment;  
c) the management of sources of ionising radiation in a workplace performing medical 
exposure;  
1. a description of the method of recording a radiological event, perfo rming 
investigation of said event and taking measures to eliminate its occurrence and 
mitigate its consequences; and  
2. the principles of using personal protective equipment and aids, their characteristics 
and a description of the system of their assignment; and 
d) the import, export or distribution of a source of ionising radiation  
1. specification of the documentation handed over to the users of an imported, exported 
or distributed source of ionising radiation, and  
2. a description of the method of ensuring the trans port of a source of ionising radiation 
with the exception of a radiation generator.  
CELEX: 32013L0059  
§ 55 
The programme ensuring radiation protection shall also include for  
a) the provision of services in the controlled area by the operat ors of a level  IV workplace  
1. a list of the controlled areas in which the licensed activity is performed;  
2. a description of the method of ensuring occupational health services to exposed 
workers;  
3. a description of the system of monitoring and evaluation of in dividual doses received 
by exposed workers;  
4. a description of the system of management of personal radiation passports;  
5. a description of activities provided by suppliers; and  
6. the principles of using personal protective equipment and aids, their characterist ics 
and a description of the system of their assignment;  
b) the evaluation of the characteristics of a source of ionising radiation pursuant to 
§ 9(2)(f)(8) of the Atomic Act  
1. a description of the method of ensuring occupational health services for exposed 
workers;  
2. the principles of using personal protective equipment and aids, their characteristics 
and a description of the system of their assignment;  
3. a description of the method of ensuring assistance of a person for whom the 
evaluation of the characteristics o f a source of ionising radiation is performed;  
4. a description of the method of evaluation of the results of the test of long -term 
stability and the acceptance test;  
5. a description of the determination of time limits for the removal of less significant 
defect s; 
6. a description of the procedure to be followed if a change in the scope of operational 
reliability tests is proposed within the framework of the test of long -term stability;  
7. a description of the method of keeping materials acquired during the tests of a source 
of ionising radiation; and  
8. a description of activities provided by suppliers;  
c) the management of products of mining activity resulting from activities related to the 
extraction of a radioactive mineral and deposited in spoil heaps and sludge settling  
lagoons  - 39 - 
 
 1. the principles of the management of products of mining activity resulting from 
activities related to the extraction of a radioactive mineral;  
2. principles of the clearance of products of mining activity resulting from activities 
related to the extra ction of a radioactive mineral into the environment; and  
3. the principles of using personal protective equipment and aids, their characteristics 
and a description of the system of their assignment; and  
d) services relevant to radiation protection pursuant to §  9(2)(h)(2) and (5) through (7) of the 
Atomic Act  
1. a description of ensuring metrologically correct measurements and measuring 
devices;  
2. a description of the system for the education of individuals participating in the 
provision of this service; and  
3. a degree of the physical participation of the person managing the provision of this 
service during measurements executed within the framework of the service 
provision.  
§ 56 
Other documentation  
(For the implementation of §  24(7) of the Atomic Act ) 
The content of other documentation for licensed activities within the framework of 
exposure situations other than the programme to ensure radiation protection is specified in 
Annex  19 to this implementing decree.  
§ 57 
Evaluation of th e method of radiation protection ensuring  
(For the implementation of §  69(2)(a) of the Atomic Act)  
(1) The evaluation of the method of ensuring radiation protection by the licensee shall 
include the following  
a) a description of the assessment of the radiation pr otection optimisation based on the 
results of individual monitoring or workplace monitoring;  
b) a list and a summary of deviations from standard operation and exceeding monitoring 
levels or dose constraints and measures taken;  
c) an overview of the fulfilment of  duties imposed on the licensee, namely  
1. the provision of occupational health services for exposed workers;  
2. the education of exposed workers; and  
3. testing the exposed workers'’ competence to perform radiation activities in a safe 
manner;  
d) an assessment of the  availability of protective equipment and aids;  
e) an evaluation of the condition of the source of ionising radiation based on the results of 
the tests performed;  
f) an assessment of the security of the source of ionising radiation;  
g) an evaluation of the performe d inventory inspection of sealed radioactive sources,  
h) an evaluation of the balance of spent activity for unsealed radioactive sources;  
i) a list and analysis of radiological events and cases when a radiological event could have 
occurred if the causes had not been early discovered and removed;  
j) a list of revisions of local diagnostic reference levels; and  
k) a description of the evaluation of executed practical exercises.  - 40 - 
 
 (2) The evaluation of the method of ensuring radiation protection shall be approved by 
the license e or its statutory body if the licensee is a legal person.  
CELEX: 32013L0059  
Part 4 
Workplace operation  
§ 58 
Conditions of safe operation for a workplace handling a radiation generator  
(For the implementation of §  75(5)(a) of the Atomic  Act) 
(1) A radiation generator can be used only for a period necessary for achieving the 
required purpose.  
(2) When using a radiation generator, measuring or signalling before entry into the 
delineated or shielded irradiation room and after the work is finished s hall verify that the 
radiation generator is off.  
(3) A stationary X -ray unit and a different radiation generator shall be  
a) located in a separate irradiation room or an examination room;  
b) operated from a shielded control room with the exception of an X -ray unit t he design or 
purpose of the use of which is to ensure that exposure limits are not exceeded.  
(4) An X -ray unit for radiodiagnostics that must be operated directly from the 
examination room shall be operated with the use of a fixed or sliding shield limiting 
occupational exposure.  
(5) A device or equipment containing a radiation generator and protective shielding can 
be used provided that  
a) it is ensured that the device or equipment cannot be activated if the protective shielding is 
removed; and  
b) the device or equipmen t is automatically deactivated if the protective shielding is opened.  
§ 59 
Conditions for the safe operation of a sealed radioactive source along with installation 
and workplace  
(For the implementation of §  75(5)(a) of the Atomic Act)  
(1) A sealed radioactive source shall be used only for the period necessary for achieving 
the required purpose.  
(2) If the sealed radioactive source is not used, it shall be deposited in a protective shield 
or shielded otherwise so that  
a) during storage the dose equi valent rate  
1. on the surface of the shield, container, shielded storage rooms, vaults and shielded 
boxes does not exceed a value of 100  µSv/h; and  
2. at a distance of 1  m from the surface of the shield, container, shielded storage rooms, 
vaults or shielded boxe s the dose equivalent rate does not exceed a value of 
10 µSv/h; and  - 41 - 
 
 b) when a sealed radioactive source is being transported around the workplace, the dose 
equivalent rate at a distance of 1  m from the surface of the transport shield does not 
exceed a value o f 100  µSv/h.  
(3) When using a sealed radioactive source, it shall be verified by measuring or signalling 
after the finished work or before entering the delineated or shielded irradiation room whether 
the sealed source is properly shielded or inserted in a shie ld. 
(4) For handling a sealed radioactive source whose loosening from the irradiation 
equipment or loss cannot be ruled out, a measuring device that is able to indicate the source's’ 
location under all circumstances shall be used.  
(5) The functionality of the acce ssories of mobile equipment containing a sealed 
radioactive source shall be verified at regular intervals, at least once a year.  
(6) If a leakage of a sealed radioactive source is discovered, the shutdown of the sealed 
radioactive source together with its equi pment shall be ensured along with their proper 
protection against misuse.  
(7) In the case of significant leakage with more than 100 times the limit value pursuant to 
Annex  10(2) of this implementing decree, the environment of the sealed radioactive source 
together with its equipment shall be closed until a test of radioactive contamination and 
effective decontamination, if necessary, are performed.  
§ 60 
Conditions for the safe operation of a workplace handling an unsealed radioactive 
source  
(For the implementation of §  75(5)(a) of the Atomic Act)  
(1) At a level  I-III workplace handling an unsealed radioactive source, it is possible at 
individual workplaces to process at the same time the maximum activity defined based on 
criteria taking into acco unt the ventilation, insulation and shielding equipment available at 
individual workplaces along with the drainage, physical and chemical characteristics of the 
materials that are to be processed, particularly the volatility and dust nuisance and the 
deman ds and risk level of the assumed work activities. The procedure for the determination of 
the maximum processed activity is specified in Annex  9 to this implementing decree.  
(2) When the unsealed radioactive source is not used and unless a source consisting of 
technological units or workplace media is concerned, it shall be deposited in a protective 
shield or container that effectively prevents the scattering of the radioactive substance and so 
that 
a) during storage the dose equivalent rate  
1. on the surface of the s hield, container, shielded storage rooms, vaults and shielded 
boxes does not exceed a value of 100  µSv/h; and  
2. at a distance of 1  m from the surface of the shield, container, shielded storage rooms, 
vaults or shielded boxes the dose equivalent rate does not  exceed a value of 
10 µSv/h; and  
b) when an unsealed radioactive source is being transported around the workplace, the dose 
equivalent rate at a distance of 1  m from the surface of the transport container does not 
exceed a value of 100  µSv/h.  - 42 - 
 
 (3) Requirements pro vided in subsection  1 shall not apply to  
a) a level  III workplace where activities related to the extraction of radioactive minerals are 
performed;  
b) a workplace handling a nuclear installation; and  
c) a workplace handling a nuclear waste repository that is not a nuclear installation.  
Temporary workplace  
§ 61 
(For the implementation of §  77(2) of the Atomic Act)  
(1) A licensee using a source of ionising radiation in a temporary workplace shall ensure 
radiation protection of the public, workers and t he environment of the temporary workplace  
a) by directing the primary beam of ionising radiation in a manner preventing exposure of 
an individual;  
b) by selecting the time for the performance of activities with regard to the movement of 
individuals in the enviro nment of the temporary workplace;  
c) by informing an individual who might be affected by the activity at the temporary 
workplace; and  
d) by using natural barriers preventing the entry of an unauthorised person together with the 
delimitation of the controlled are a. 
(2) The perimeter of the controlled area at a temporary workplace shall be designated  
a) by a warning strip;  
b) by a sign about radiation danger;  
c) by a notice that says “Controlled area with sources of ionising radiation. No admittance”,; 
and 
d) in the case of reduce d visibility, by light signalling.  
(3) The members of the working team providing activities in a temporary workplace 
where the controlled area is delineated shall include, at the moment of the performance of 
activities, at least two category  A exposed workers competent to execute the respective 
radiation activity in a safe manner, of whom one is the supervisor or the radiation protection 
officer in the respective expert field of the application of the source of ionising radiation.  
(4) The working team shall be equi pped with a detector to monitor the workplace within 
the scope corresponding to the used sources of ionising radiation.  
(5) If the dose equivalent rate in a temporary workplace can exceed 1  mSv/h, the exposed 
worker shall be equipped with an operational signal  or direct -reading personal dosimeter.  
CELEX: 32013L0059  
§ 62 
(1) The holder of the licence to handle a source of ionising radiation that is an 
insignificant, minor or simple source of ionising radiation, with the exception of an X -ray 
flaw detector and a logging unit with a sealed radioactive source, shall submit to the Office 
before the first use of the source of ionising radiation in a temporary workplace  
a) a list of used sources of ionising radiation;  
b) a description of the work activities; and 
c) the expected number of interventions in the temporary workplace per calendar year.  - 43 - 
 
 (2) The holder of the licence to use a source of ionising radiation that is a significant 
source of ionising radiation, an X -ray flaw detector or a logging unit with a seale d radioactive 
source shall submit to the Office the following information in writing at least one day in 
advance  
a) the date of commencement of the work activities;  
b) the assumed time of work in the temporary workplace;  
c) a description of the work activities;  
d) a list of used sources of ionising radiation; and  
e) a telephone number of the worker who will execute continuous supervision in the 
temporary workplace.  
(3) A holder of the licence to use a source of ionising radiation that is a significant source 
of ionising radia tion, an X -ray flaw detector or a logging unit with a sealed source of 
radioactive shall submit to the Office before commencement of work activities an 
unambiguous specification of the workplace with the source of ionising radiation, namely by 
providing th e geographic coordinates or address of the temporary workplace, including the 
house number of the building on the premises or the plot number.  
(4) A holder of the licence to use a source of ionising radiation shall immediately inform 
the Office of the completi on of work in the temporary workplace.  
Part 5  
Changes in radiation protection  
(For the implementation of §  9(2)(c) and §  69(2)(d) and (e) of the Atomic Act)  
§ 63 
List of changes affecting radiation protection for a level III or level IV  workplace  
(For the implementation of §  9(2)(c) of the Atomic Act)  
(1) A change affecting radiation protection of a level IV workplace refers to  
a) a change in the structural design of the level IV workplace;  
b) reconstruction of the source of ionising radiation or a change modifying the shielding 
characteristics of its accessories;  
c) a change in the arrangement of the controlled area that modifies the method of its use;  
d) an organisational change in the activity management particularly relevant to radiation 
protection; or 
e) a change in the person performing activities particularly relevant to radiation protection.  
(2) A change affecting radiation protection for a level III or level IV workplace refers to  
a) a change in the structural part or the technological system or equipment in the controlled 
area in the workplace resulting in a change in their shielding, insulating or protecting 
characteristics;  
b) a change in the structural part or equipment in the workplace controlled area resulting in a 
change in the method for safeguarding t he source of ionising radiation;  
c) a change in the method for decommissioning such a workplace;  
d) a change in the conditions for further use of the territories and structures, components or 
systems after the decommissioning of such a workplace unless a complet e 
decommissioning is concerned; or  
e) a change in the possibility of accumulation of the radioactive substance in the 
environment in the case of its long -term release from the workplace.  - 44 - 
 
 (3) A change affecting radiation protection in a level  III workplace , with the exception 
of a workplace where medical exposure is performed, and a level IV workplace refers to a 
change in the method of the monitored quantity value determination, architecture of the 
installed monitoring systems, the concept of data processing or t he physical principle of 
measurement  
a) for a monitoring device whose output is compared to limits and conditions;  
b) for a monitoring device that serves  
1. for the verification of the observance of exposure limits;  
2. for the verification of the observance of the aut horised limits for effluents; or  
3. for the purposes of clearance of the radioactive substance from the workplace; or  
c) for a stationary monitoring device that is designed for the detection of radioactive 
substance leaks or for the monitoring of the radiation s ituation during a radiation incident.  
§ 64 
List of changes related to radiation protection for a workplace handling a source of 
ionising radiation  
(For the implementation of §  69(2)(d) of the Atomic Act)  
(1) A change related to radiation pr otection for a level  IV workplace refers to a change 
in the type of monitoring device with the preserved physical principle of measurement or a 
change in the number of monitoring devices;  
a) whose outputs are compared to limits and conditions;  
b) that serves  
1. for the verification of the observance of the exposure limits;  
2. for the verification of the observance of the authorised limits for effluents; or  
3. for the purposes of clearance of the radioactive substance from the workplace; or  
c) that are designed for the detect ion of radioactive substance leaks or for the monitoring of 
the radiation situation during a radiation incident.  
§ 65 
Scope and method of the documentation of a change related to radiation protection for a 
workplace handling a source of  ionising radiation and the method and time limits for its 
reporting to the Office  
(For the implementation of §  69(2)(e) of the Atomic Act)  
(1) The documentation of a change related to radiation protection in a workplace 
handling a source of ionising radiation  shall include the following  
a) a description and reasons for the change;  
b) a list of documentation for the licensed activity updated in respect of the change;  
c) the assumed time schedule for implementation of the change; and  
d) the assessment of the change impact o n radiation protection.  
(2) The Office shall be notified of a change related to radiation protection in a workplace 
handling a source of ionising radiation in writing 30 days prior to the change implementation.  - 45 - 
 
 Part 6  
Registration  
§ 66 
Specification of the job to be performed by the registrant's person responsible for 
radiation protection  
(For the implementation of §  70(2)(b) of the Atomic Act)  
The person ensuring radiation protection for the registrant shall ensure  
a) that exposed workers and  trainee preparing for their future work in the workplace of facts 
relevant to radiation protection and the potential risk of work with a source of ionising 
radiation;  
b) continuous education for exposed workers concerning the safe use of a source of ionising  
radiation;  
c) the proper management of documentation for the registered activity;  
d) the records of the movement and condition of sources of ionising radiation;  
e) the organisation of acceptance tests, long -term stability tests and operational reliability 
tests fo r sources of ionising radiation and participation in such tests;  
f) the execution of procedures for safe handling of a source of ionising radiation, including 
procedures preventing unauthorised management of the source of ionising radiation, its 
loss, theft o r damage, and including procedures to be followed in the case of deviations 
from standard operation;  
g) the investigation of a radiological incident and measures taken in relation thereto; and  
h) regular verification of the protective characteristics of personal  protective equipment and 
other protective aids.  
§ 67 
Procedures for ensuring radiation protection by the registrant when handling a source 
of ionising radiation  
(For the implementation of §  70(2)(c) of the Atomic Act)  
The procedures fo r ensuring radiation protection by the registrant when handling a source 
of ionising radiation are specified in Annex  20 to this implementing decree.  
§ 68 
Documentation for the registered activity  
(For the implementation of §  17(3) of t he Atomic Act)  
(1) The documentation for the registered activity refers to  
a) a report of the acceptance test or the last test of long -term stability of the source of 
ionising radiation; and  
b) a document attesting to the completion of the preparation of the registr ant's person 
responsible for radiation protection.  
(2) The specimens of the registration forms are provided in Annex  21 to this 
implementing decree.  - 46 - 
 
 Part 7  
Monitoring  
§ 69 
Monitoring programme  
(For the implementation of §  24(7) of the Atomi c Act)  
(1) Depending on the types of monitoring that the licensee is obliged to perform, the 
monitoring programme shall consist of the following parts  
a) monitoring of a workplace;  
b) individual monitoring;  
c) monitoring of effluents; and  
d) monitoring of the environment.  
(2) The monitoring programme shall include monitoring rules for the standard operation 
of the workplace, foreseeable deviations from the standard operation of the workplace, 
radiation incidents and radiation accidents, namely  
a) the specification of monitored qu antities;  
b) the method, scope and frequency of measurements;  
c) the method of recording and retention period for measurement results;  
d) procedures for the evaluation of measurement results;  
e) the values of monitoring levels and measures to be taken when such levels  are exceeded;  
f) the values of dose constraints;  
g) a description of the measurement methods;  
h) a description of the monitoring of persons intervening in the case of a radiation incident 
or radiation accident according to the on -site emergency plan for the workpl ace; 
i) a specification of the part of an exposed worker's body where a personal dosimeter is 
placed; and  
j) a specification of the types of measuring devices and aids, including parameters thereof.  
(3) The content of this monitoring programme shall be drawn up in a  way that allows  
a) verification of observance of the exposure limits;  
b) the demonstration of the optimised state of radiation protection; and  
c) early detection of deviations from the standard operation of the workplace.  
§ 70 
Procedures for th e evaluation of quantities measured within the framework of 
monitoring  
(For the implementation of §  78(3)(d) of the Atomic Act)  
(1) In the case of the conversion of activities of received radionuclides into the 
committed effective dose, the conversion factors shall be applied. In the case of unidentified 
radionuclides and chemical forms or characteristics of inhaled aerosol, the activity for 
radionuclides, their forms or aerosol with the highest conversion factor for intake by ingestion 
or inhalation shall be a pplied. The conversion factors for the conversion according to 
subparagraphs  1 and 2 are specified in Annex  3 to this implementing decree.  
(2) If no data better corresponding to a given situation where exposure occurs are 
available, the quantity of inhaled air  per year for the representative person is  
a) up to 1 year of age, inclusive, 1  000 m3, - 47 - 
 
 b) from 1 to 2 years of age, inclusive, 2  000 m3, 
c) from 2 to 7 years of age, inclusive, 4  000 m3, 
d) from 7 to 12 years of age, inclusive, 6  000 m3, 
e) from 12 to 17 years of age, i nclusive, 8  000 m3 and 
f) above 17 years of age, 8  500 m3. 
(3) If no data better corresponding to a given situation where exposure occurs are 
available, the quantity of ingested water per year for the representative person is  
a) under 2 years of age, 0.25  m3 in liqu id form;  
b) from 2 to 17 years of age, 0.45  m3 in liquid form; and  
c) above 17 years of age, 1  m3 of water, of which 0.7  m3 in liquid form.  
(4) If, during the determination of external exposure, a conversion of the average activity 
volume concentration of rare radio active gases dispersed in the air into the effective dose rate 
is executed, the conversion factors specified in Annex  3 to this implementing decree shall be 
applied.  
(5) For the calculation of the effective dose due to inhalation of radon progeny from the 
air in the area affected by extraction and processing of uranium ore, the value of background 
radiation of radon equivalent activity volume concentration is 10  Bq/m3, unless a different 
value in this area is known.  
(6) For the determination of internal exposure b y radon progeny and intake by inhalation 
of a mixture of long -lived radionuclides emitting the alpha particles of the uranium -radium 
series per year, an exposed worker performing extraction activity or activity executed in a 
mining manner underground durin g work lasting 2  000 hours inhales 2  400 m3 of air.  
§ 71 
Monitoring levels  
(For the implementation of §  81(3)(b) of the Atomic Act)  
(1) The monitoring levels refer to  
a) a recording level;  
b) an investigation level; and  
c) an intervention level.  
(2) The recording levels shall be specified  
a) at the level of  
1. 1/10 of the exposure limits; or  
2. the minimum detectable value of the measured quantity; and  
b) considering the duration of the monitoring period.  
(3) The investigation levels shall be specified at the level of  
a) 3/10 of the exposure limits; or  
b) the upper limit for normally monitored values of the measured quantity.  
(4) Upon reaching or exceeding the recording level, the data shall be recorded and 
retained.  
(5) Upon exceeding the investigation level, an investigation into t he causes and 
determining the consequences of the deviation of the radiation protection monitored quantity 
shall be performed.  - 48 - 
 
 (6) Upon exceeding the intervention limit, a predefined measure shall be implemented to  
a) repair the resulting state; and  
b) prevent any u ndesirable development of the resulting state.  
§ 72 
Workplace monitoring  
(For the implementation of §  78(3)(b) of the Atomic Act)  
(1) In a level  I-IV workplace, with the exception of a level  I workplace where only minor 
sources of ionising radiation are used, the workplace monitoring shall be executed by the 
monitoring, measurement, evaluation and recording of quantities and parameters 
characterising the field of ionising radiation and the occurrence of radionuclides in the 
workplace.  
(2) Depend ing on the type of the sources of ionising radiation used, workplace 
monitoring shall be executed  
a) by monitoring the dose equivalent rate in the workplace;  
b) by monitoring the activity volume concentrations in the air in the workplace and the 
surface activiti es in the workplace; or  
c) by measuring scattered radiation at the source of ionising radiation.  
(3) The efficiency of protection against external and internal exposures shall be verified 
by the measurements of the dose equivalent rate, activity volume concentrat ion or other 
quantities necessary for the verification of the efficiency of protection against external and 
internal exposure, namely at the source of ionising radiation, in workplaces with such a source 
and in places where exposed workers or other individ uals may stay upon  
a) the commencement of the workplace operation;  
b) a change in working procedures;  
c) a change in ensuring radiation protection; or  
d) a change in the monitoring of the radiation situation.  
(4) The monitoring of radioactive contamination shall be execut ed in a workplace 
handling an unsealed radioactive source in a manner  
a) allowing  
1. deviations in operation from standard operation; and  
2. insufficient function or failure of barriers preventing scattering to be signalled; and  
b) making it possible to confirm that t he values for surface radioactive contamination have 
not been exceeded; the values for surface radioactive contamination are specified in 
Annex  18 to this implementing decree.  
(5) The continuous monitoring of the activity volume concentrations for radionuclide s in 
the air shall be performed in:  
a) a level  IV workplace;  
b) a workplace where an activity related to the extraction of a radioactive mineral is 
executed, and  
c) a different workplace of the level III category handling an unsealed radioactive source 
where contam ination of the atmosphere may occur considering the character of the used 
radioactive source and the method of its handling.  
CELEX: 32013L0059  - 49 - 
 
 Individual monitoring of an exposed worker  
(For the implementation of §  73(3)(a) of the Atomic Act)  
§ 73 
(1) The individual monitoring of an exposed worker shall be executed to determine the 
individual doses received by a exposed worker by monitoring, measurement and evaluation of 
their external as well as internal exposure.  
(2) The individual monitoring of external exposure by a personal dosimeter shall be 
ensured for the category A exposed worker. For the category A exposed worker, the period 
for the evaluation of the personal dosimeter shall be 1 calendar month.  
(3) The personal dosimeter shall be placed in  a reference point being the left front side of 
the chest (hereinafter referred to as the “reference point ”) or in a different point depending on 
exposure geometry. If a protective shielding apron is used, the personal dosimeter shall be 
placed outside su ch an apron.  
(4) If one dosimeter does not allow a sufficiently accurate determination of the effective 
dose and equivalent dose in the bodies and tissues for which limits are defined, the exposed 
worker shall be equipped with other personal dosimeters allowin g such determination due to 
their characteristics or positioning.  
(5) The personal dosimeter shall measure all kinds of radiation which contribute to the 
exposed worker's external exposure. If one personal dosimeter fails to fulfil this requirement, 
the expose d worker shall be equipped with other personal dosimeters unless the monitoring 
programme defines a different method of individual monitoring for the exposed worker.  
(6) The exposed worker who performs activities, which are executed and monitored 
using a sourc e of ionising radiation in the exposed worker's presence in the irradiation room, 
shall be equipped with a protective shielding apron and two personal dosimeters of which one 
is placed on such an apron and the other one under it. Based on the evaluation of  both 
dosimeters, the evaluation of the coefficient of attenuation of the used protective shielding 
apron shall be ensured along with the evaluation of the actual effective dose received by the 
exposed worker when taking into account the exposure of unprot ected parts of body.  
CELEX: 32013L0059  
§ 74 
(1) If it is not possible to eliminate the exceeding of the exposure limits for an exposed 
worker due to single external exposure, the exposed worker shall be equipped with 
operational personal do simeters which are able to directly signal the exceeding of the set level 
of the monitored quantity.  
(2) If single exposure caused by a source of ionising radiation can exceed five -times the 
occupational limit for exposed workers, individual monitoring of an e xposed worker shall 
allow doses and their distribution in the exposed worker's body to be determined.  
(3) At workplaces with a possibility of internal exposure of an exposed worker, 
radionuclide intakes or committed effective doses caused by the internal expos ure of 
individual exposed workers shall be determined by radionuclide activity measurements in the 
exposed worker's body or the worker's excretes where such activities shall be converted into 
an intake of radionuclides or committed effective dose using the  models of the respiratory and 
digestive tracts and the kinetics of appropriate chemical elements.  - 50 - 
 
 (4) When working with an unsealed radioactive source, the measurement of activity for 
radionuclides in the exposed worker's body or excretes shall be executed pu rsuant to 
subsection  2 
a) in a level IV workplace at least once a year, and  
b) in category I -III workplaces based on the evaluation of the potential risk of an exposed 
worker's internal exposure.  
(5) In the event of the suspected, unplanned, single exposure of an ex posed worker, 
which might result in exceeding the limits for the exposed worker, the immediate evaluation 
of the personal dosimeter and dosimetric evaluation of such an event shall be ensured.  
CELEX: 32013L0059  
§ 75 
(1) Individual monitorin g of the category B exposed worker shall be ensured  
a) by a personal dosimeter,  
b) by the calculation of the individual doses for the exposed worker based on data from the 
monitoring of the workplace where the exposed worker performs work activities, and by 
the monitoring of the duration of their stay in such a workplace, or  
c) by equipping one or more category B exposed workers performing the same work 
activity in the same workplace with a personal dosimeter and by assigning the individual 
dose acquired by its eval uation to the other exposed workers without a personal 
dosimeter working in the same workplace.  
(2) The results of the evaluation of individual doses for the category B exposed worker 
shall be used for the demonstration  
a) of the accuracy of the exposed worker's classification into the category, and  
b) of the stability of exposure conditions in the workplace.  
(3) The licensee shall inform the exposed worker in a comprehensible manner so that it is 
clear that the exposed worker has been informed of  
a) the results of their in dividual monitoring and  
b) procedures after the investigation of the causes of reaching the set investigation or 
intervention level.  
CELEX: 32013L0059  
§ 76 
Effluents monitoring  
(For the implementation of §  81(3)(a) of the Atomic Act)  
(1) The m onitoring of effluents from a workplace shall be performed by the monitoring, 
measurement, recording and evaluation of quantities and parameters characterising the 
released radioactive substances, particularly by the determination of the balance of the tot al 
discharged activity and the activity volume concentration for individual radionuclides.  
(2) The monitoring of effluents shall include  
a) the continuous monitoring of radionuclides that significantly contribute to the exposure 
of the public and that are dischar ged for a defined period (hereinafter referred to as 
“balance measurement”),  - 51 - 
 
 b) the non -stop monitoring of radionuclides, which allows for quick detection of a deviation 
from standard operation for a level IV workplace, and  
c) the operational monitoring of other  potential pathways of the radioactive substance’s 
release from the workplace in the event of a leak, which would allowing such a leak to be 
included in the balance of effluents.  
(3) The recording level shall be determined in a manner  
a) allowing requirements for  the minimum detectable value of the monitored quantity to be 
fulfilled during the balance measurement, pursuant to the implementing decree on 
radiation monitoring, and  
b) allowing all operating states to be checked within the framework of the continuous 
moni toring of radionuclides.  
(4) The investigation level shall be defined  
a) during the balance measurement at the level of the expected value of the radionuclide 
effluent balance, taking into account the monitoring period duration, and  
b) during the monitoring of devia tions from standard operation of the workplace as the 
upper limit of the usually monitored values of the monitored quantity.  
(5) The intervention level shall be determined in a manner allowing  
a) measures to be taken at the balance measurement of effluents in ord er to prevent the 
exceedance of the authorised limits or the non -observance of the licence conditions,  
b) measures to be taken simultaneously with the monitoring of deviations from standard 
operation of the workplace in order to correct the resulting state an d prevent any further 
undesirable developments.  
CELEX: 32013L0059  
§ 77 
Workplace environment monitoring  
(1) The monitoring of the environment of the workplace from which radioactive 
substances are discharged or released by different pathway s shall be executed by the 
monitoring, measurement, evaluation and recording of quantities and parameters 
characterising the field of ionising radiation and the occurrence of radionuclides in the 
workplace environment, particularly  
a) dose rates,  
b) activity vol ume concentrations for individual radionuclides, and  
c) activity weight concentrations for individual radionuclides.  
(2) The recording level shall be determined in a manner that allows the requirements for 
the minimum detectable value of the monitored quantity, p ursuant to the implementing decree 
on radiation monitoring, to be fulfilled.  
(3) The investigation level shall be determined as the upper limit of the usually monitored 
values of the monitored quantity.  
(4) The intervention level shall be determined in accordance with the requirements for 
public exposure optimisation.  
CELEX: 32013L0059  - 52 - 
 
 Part 8  
Medical exposure  
§ 78 
Equipment of a workplace for x -ray diagnostics and radiotherapy  
(For the implementation of §  86(3)(a) of the Atomic Act)  
(1) Workplaces i ntended for x -ray diagnostics and radiotherapy shall be equipped with, 
in the case of  
a) brachytherapy, an x -ray unit designed for the localisation of applicators as well as a 
planning unit and dosimetric equipment for testing the characteristics of a source  of 
ionising radiation,  
b) handling a radiotherapeutic x -ray unit, dosimetric equipment for testing the 
characteristics of a source of ionising radiation,  
c) handling a radioactive irradiator or particle accelerator,  
1. a planning unit,  
2. a simulator,  
3. dosimetric equi pment for testing the characteristics of a source of ionising radiation,  
4. if radical radiotherapy is performed, a verification system, and  
5. if radical radiotherapy is performed, a system for dosimetric verification of applied 
doses, be this an in -vivo dosime try system or a full -valued alternative.  
(2) Workplaces intended for x -ray diagnostics and radiotherapy shall post, in a visible 
place, a notification of the necessity to inform healthcare provider employees of pregnancy 
prior to the execution of medical expos ure. 
(3) The equipment of a workplace intended for x -ray diagnostics and radiotherapy shall 
take into account the special needs and character of this medical exposure in the event of  
a) medical exposure of children,  
b) health screening, or  
c) exposure with a high dose is performed on a patient undergoing radiotherapy, 
interventional radiology and computed tomography.  
CELEX: 32013L0059  
Requirements imposed on sources of ionising radiation used for medical exposure  
(For the implementation of §  86(3)(a) of the Atomic Act)  
§ 79 
A source of ionising radiation used for medical exposure  
a)  in radiotherapy shall be equipped with aids for the execution of operational reliability 
tests at monthly or shorter intervals,  
b) designed for radiodiagnostics or for planning , management and verification purposes in 
radiotherapy, shall be equipped with a device or corresponding means providing 
quantitative information on the patient's exposure; if technically feasible, such 
information shall be automatically transferred to a r ecord on the patient's examination,  
c) for interventional radiology  
1. after the examination, it shall provide quantitative information on the patient's 
exposure,  
2. for fluorography/fluoroscopy purposes, it shall indicate the total product of kerma 
and area along with cumulative reference kerma,  - 53 - 
 
 3. it shall be equipped with aids for the execution of operational reliability tests at 
monthly or shorter intervals,  
4. it shall generate structured reports on radiation doses which are automatically 
transferred to the record on  the patient's examination, and  
5. during the course of the examination, it shall inform the person performing the 
examination of the quantity of emitted ionising radiation, and  
d) for computed tomography  
1. after examination, it shall provide quantitative informat ion on the patient's exposure,  
2. during which images of children are acquired, it shall be equipped with examination 
protocols that are adapted to the examination of children,  
3. it shall be equipped with aids for the execution of operational reliability tests  at 
monthly or shorter intervals,  
4. it shall provide information on the product of kerma and duration,  
5. it shall provide information on the weighted kerma index for computed tomography, 
or the volume kerma index for computed tomography,  
6. it shall generate stru ctured reports on radiation doses which are automatically 
transferred to the record on the patient's examination, and  
7. it shall be equipped with an automatic exposure control system.  
CELEX: 32013L0059  
§ 80 
(1) Sources of ionising radiation u sed for medical exposure  
a) for fluorography purposes  
1. shall not allow abreography,  
2. stationary with a digital image receptor, with the exception of a device designed 
exclusively for scanning the extremities, shall be equipped with an automatic 
exposure control  system or organ pre -settings,  
3. shall be equipped with aids for the execution of operational reliability tests at 
monthly or shorter intervals, and  
4. stationary, with the exception of a device designed exclusively for scanning the 
extremities, shall be equipp ed with an automatic exposure control system,  
b) for fluoroscopy purposes  
1. shall not allow imaging by direct fluoroscopy,  
2. shall be equipped for automatic dose rate regulation,  
3. shall automatically set the magnitude of the x -ray beam according to the size of the  
receptor image and the distance of the focus from the image receptor,  
4. shall be equipped with an audible alarm that sounds once the total fluoroscopy 
duration exceeds five minutes,  
5. shall be equipped with a function that allows the last image on the monitor  to be 
preserved upon exposure completion,  
6. with a circular image receptor, shall not have a rectangular primary diaphragm, and  
7. it shall be equipped with aids for the execution of operational reliability tests at 
monthly or shorter intervals,  
c) for mammograph y purposes  
1. shall be equipped with an automatic exposure control system that adapts the 
electrical charge to the radiation -penetrated volume,  
2. with a film image receptor or with indirect digitisation, shall be equipped with an 
anti-diffusing screen,  
3. shall pr ovide information on compression force and compressed thickness,  - 54 - 
 
 4. shall be equipped with an automatic filter exchange function, depending on 
compressed thickness,  
5. shall be equipped with an image receptor with the minimal dimensions of 18  cm × 
24 cm, unless it is intended for stereotaxis, and  
6. shall be equipped with aids for the execution of operational reliability tests at 
monthly or shorter intervals, and  
d) dental intraoral  
1. shall have a nominal voltage of at least 60  kV, 
2. shall have a distance of the focus from  the end of the tube at least 20  cm, 
3. shall be equipped with aids for the execution of all operational liability tests,  
4. shall be equipped with beam collimation corresponding to the image receptor in 
terms of shape and size,  
5. shall be equipped with a correspo nding holder for the image receptor, and  
6. shall not be portable.  
(2) Sources of ionising radiation used for medical exposure - dental panoramic x -ray 
units, dental computed tomographs or bone densitometers, shall be equipped with aids for the 
execution of all o perational reliability tests.  
CELEX: 32013L0059  
§ 81 
Therapeutic and diagnostic application of a radionuclide  
(For the implementation of §  86(3)(b) of the Atomic Act)  
(1) Upon the therapeutic and diagnostic application of a radionuclide, th e activity of a 
radionuclide used as an unsealed radioactive source applied to the patient shall be measured, 
namely before its administration.  
(2) The therapeutic application of a radionuclide used as an unsealed radioactive source, 
with the exception of thos e used for brachytherapy, shall be executed in the residential part of 
the healthcare provider's medical facility, specifically adapted and equipped for this purpose. 
Upon such therapeutic application of a radionuclide, it shall be ensured that the patient  is not 
wearing their own clothes.  
(3) Upon releasing the patient after the application of an unsealed radioactive source, 
with the exception of brachytherapy, all items of personal use shall be checked for possible 
contamination by the radionuclide, and if su ch contamination is detected, the affected items 
must be decontaminated or disposed of as radioactive waste.  
(4) If the patient undergoes therapeutic application of a radionuclide, the licensee shall 
provide the patient or their legal representative, prior to the patient's leaving the healthcare 
facility,  
a) with written information on the risks related to ionising radiation, and  
b) with written instructions on how to reduce doses received by an individual who comes 
into contact with the patient to the minimum, reaso nably attainable level.  
(5) If the patient undergoes diagnostic application of a radionuclide, the licensee shall 
provide the patient, prior to the patient's leaving the healthcare facility, with the written 
instructions set out in subsection  3(b), in the even t that the exposure of an individual who 
comes into contact with the patient could approach the values of the general limits for the 
public.  - 55 - 
 
 (6) Workplaces earmarked for the therapeutic or diagnostic application of a radionuclide 
shall post, in a visible place , a notification of the necessity to inform the healthcare provider's 
employees of pregnancy or breastfeeding prior to the execution of medical exposure.  
(7) The equipment of a workplace where therapeutic or diagnostic application of a 
radionuclide, medical ex posure of children, medical exposure within the framework of health 
screening or medical exposure related to a high dose received by a patient is executed shall 
comply with the special needs and character of such medical exposure.  
CELEX: 32013L0059  
§ 82 
National diagnostic reference levels  
(For the implementation of §  84(6) of the Atomic Act)  
(1) The national diagnostic reference levels are specified in Annex  22 to this 
implementing decree.  
(2) Records on the results of the investigation of a sy stematic deviation from the local 
diagnostic reference level shall include  
a) the period during which such a deviation occurred,  
b) the approximate number of patients affected by such deviation,  
c) the scope of such deviation,  
d) reasons for such deviation,  
e) the course  and results of optimisation, where optimisation was executed based on the 
investigation, and  
f) a record on the revision of the local diagnostic reference levels, where such revision was 
performed based on the investigation.  
(3) The record on the result of the i nvestigation of significant exceedance of the local 
diagnostic reference level shall include  
a) the date and time when such significant exceedance occurred,  
b) the identification details of the patient affected by such exceedance, and  
c) information on whether such  exceedance is a radiological event.  
CELEX: 32013L0059  
§ 83 
Incorrect exposure of a patient  
(For the implementation of §  60(4)(a) of the Atomic Act)  
(1) The incorrect exposure of a patient, for the purposes of the definition of a radiologic al 
event, refers to  
a) exposure which may endanger the patient's life upon medical exposure due to tissue 
reactions,  
b) exposure resulting from  
1. an unintentional event during medical exposure, including human error or instrument 
failure, or  
2. different events whose  consequences cannot be ignored in terms of radiation 
protection,  
c) in radiotherapy  
1. exposure in the event of patient mix -up, - 56 - 
 
 2. the therapeutic exposure of a different tissue or organ than was planned,  
3. the application of the total dose or a dose per fraction wh ich considerably differs 
from the indicated dose,  
4. the application of an incorrectly prescribed dose, or  
5. exposure preceding the interruption of a planned treatment, the result of which means 
that radiobiological effect of the treatment does not correspond t o the originally 
planned effect,  
d) in nuclear medicine  
1. the application of a different radiopharmaceutical product than was planned,  
2. the application of an activity considerably different from the prescribed activity,  
3. exposure in the event of patient mix -up, o r 
4. the application of an incorrectly prescribed activity or radiopharmaceutical product,  
e) in radiodiagnostics  
1. exposure that is several times greater than necessary,  
2. exposure in the event of patient mix -up, 
3. the exposure of a different organ or tissue than was  planned, or  
4. in the case of surgery on a pregnant woman, the exposure of the embryo or foetus by 
a direct beam which was not indicated, and  
f) in interventional radiology  
1. exposure that is several times greater than necessary,  
2. exposure in the event of patient mix-up, 
3. the exposure of a different organ or tissue than was planned,  
4. in the case of surgery on a pregnant woman, the exposure of the embryo or foetus by 
a direct beam which was not indicated, or  
5. cases where tissue reaction occurs due to the incorrect exec ution of surgery.  
(2) The application of an activity that is considerably different from the prescribed 
activity in nuclear medicine, for the purposes of the definition of incorrect exposure, refers to  
a) in the case of the therapeutic application of a radionucli de, the application of an activity 
which differs from the prescribed activity by more than 20  %, or  
b) in the case of the diagnostic application of a radionuclide, the application of an activity 
which differs from the prescribed activity by more than 40  %. 
CELEX: 32013L0059  
§ 84 
Radiological events  
(For the implementation of §  87(5)(a) and (b) of the Atomic Act)  
(1) Radiological events shall be classified with respect to their seriousness into categories 
A, B and C. The criteria for radiologica l event classification are specified in Annex  23 to this 
implementing decree.  
(2) Category A or B radiological events refer to serious radiological events.  
(3) Annex  23 to this implementing decree provides  
a) procedures to be followed in the event of a radiological e vent or in the event a 
radiological event could have arisen had the causes not been detected and eliminated in 
good time,  
b) a retention period for records from the investigation of a radiological event or in the event 
a radiological event could have arisen h ad the causes not been detected and eliminated in 
good time,  - 57 - 
 
 c) the scope and the time limit for the provision of information about a serious radiological 
event.  
CELEX: 32013L0059  
§ 85 
Definition of the distribution of doses received by th e public due to medical exposure  
(For the implementation of §  85(4) of the Atomic Act)  
(1) The scope of healthcare services during which ionising radiation was used and which 
were reported by the healthcare provider and paid by the health insurance company, pr ovided 
to the Office by the health insurance company, is specified in Annex  24 to this implementing 
decree.  
(2) The information defined in subsection  1 shall be submitted to the Office in a 
machine -readable electronic format.  
CELEX: 32013L0059  
Part 9 
Non-medic al exposure  
(For the implementation of §  83(7) of the Atomic Act)  
§ 86 
Records on non -medical exposure to medical radiological equipment  
Records on non -medical exposure to medical radiological equipment shall include  
a) the identification of the individual who undergoes non -medical exposure,  
b) reasons for each non -medical exposure,  
c) the date and time of execution of each non -medical exposure,  
d) a record on the exposure parameters on the basis of which it is possible to estimate the 
dose from non -medical exposure,  
e) the identification of the source of ionising radiation with which non -medical exposure 
was performed,  
f) the comparison of the dose from non -medical exposure with the local diagnostic 
reference level used for examination within the framewor k of medical exposure with a 
similar procedure and source of ionising radiation, and  
g) information on the execution of non -medical exposure without the consent of the 
individual subject to exposure, where this procedure is in compliance with a different 
legal regulation.  
CELEX: 32013L0059  
§ 87 
Records on non -medical exposure to a different source of ionising radiation  
Records on non -medical exposure to a different source of ionising radiation shall include  
a) the identification of the individ ual who undergoes non -medical exposure,  
b) the age and gender of the individual who undergoes non -medical exposure,  
c) reasons for each non -medical exposure,  
d) information on the circumstances wherein an individual who was to undergo non -medical 
exposure refused i t, - 58 - 
 
 e) the date and time of execution of each non -medical exposure,  
f) a record on the exposure parameters on the basis of which it is possible to estimate the 
dose from non -medical exposure,  
g) the identification of the source of ionising radiation with which non -medical exposure 
was performed,  
h) the comparison of the dose from non -medical exposure with the dose constraint, and  
i) information on the execution of non -medical exposure without the consent of the 
individual subject to exposure, where this procedure is in com pliance with a different 
legal regulation.  
CELEX: 32013L0059  
Part 10 
Radiation protection for activity related to radioactive mineral extraction  
(For the implementation of §  88(6) of the Atomic Act)  
§ 88 
Workplace handling activity rela ted to radioactive mineral extraction  
(1) When performing an activity related to the extraction of a radioactive mineral, 
radiation protection shall be ensured by the delineation of  
a) a supervised area at  
1. sludge settling lagoons,  
2. decontamination stations,  
3. mine w ater treatment plants, and  
4. industrial water treatment plants from workplaces that are part of the technological 
system for the radioactive minerals treatment process, and  
b) a controlled area  
1. in underground workplaces where radioactive minerals are extracted,  
2. on above -ground technological units related to original mining activity during which 
radioactive minerals are extracted,  
3. in drying plants for uranium concentrate,  
4. in storage locations for uranium concentrate, and  
5. in the technologically integrated part of uranium ore chemical treatment plants.  
(2) When delineating a supervised area and controlled area, pursuant to subsection  1, and 
ensuring radiation protection therein, the procedures provided in section  48 through 51 shall 
be followed accordingly.  
§ 89 
Special requirements for ensuring radiation protection during activity related to 
radioactive mineral extraction  
The inspection of surface contamination when leaving a controlled area of a workplace 
where activities related to the extraction o f radioactive minerals are performed pursuant to s. 
49(e) is not to be executed.  - 59 - 
 
 Part 11 
Natural sources of ionising radiation  
§ 90 
Workplaces handling material with increased natural radionuclide content  
(For the implementation of §  93(4)(a) of the Atomic Act)  
Workplaces handling material with increased natural radionuclide content refers to 
workplaces where the following is executed  
a) extraction, transport by pipelines or processing of crude oil and gas,  
b) coal extraction,  
c) ore extraction,  
d) processing of niobium or tantalum ore,  
e) processing of raw materials containing rare earth elements,  
f) primary iron output,  
g) smelting of tin, lead or copper,  
h) production of cement, including maintenance of clinker furnaces,  
i) production of phosphate fertilisers, p roduction of phosphoric acid or thermal production 
of phosphorus,  
j) production of a titanium -dioxide -based pigment,  
k) processing of zircon or zirconium,  
l) production, processing or use of materials containing thorium and uranium,  
m) combustion of coal in an install ation with thermal output exceeding 5  MW, including the 
maintenance of boilers,  
n) generation of geothermal energy,  
o) operation of a treatment plant to treat underground water or sludge resulting from a 
source of underground water,  
p) treatment of material in whic h it was discovered that its natural radionuclide content 
exceeds the clearance level or increases the spatial dose equivalent rate by more than 
0.5 µSv/h,  
q) mining activity, or  
r) mining activity performed underground, including the establishment, operation an d 
treatment of spoil heaps, waste heaps and sludge settling lagoons related to such 
activities.  
CELEX: 32013L0059  
§ 91 
Definition of individual doses for workers in workplaces that may be subject to 
increased exposure due to a natural s ource of radiation  
(For the implementation of §  93(4)(b) of the Atomic Act)  
(1) The method of measurement to define individual doses  
a) for workers handling material with an increased natural radionuclide content in 
workplaces handling material with an increased natural radionuclide content shall include  
1. the measurement of the spatial dose equivalent rate,  
2. the measurement of the average volume activity concentrations for radionuclides in 
the air,  
3. the measurement of surface contamination in the workplace, and  
4. keepi ng records on time spent in the workplace, or  - 60 - 
 
 b) for workers who are members of the crew on board a plane, in the case of flights at 
altitudes exceeding 8  km, shall include the definition  
1. of the degree of participation in individual flights,  
2. flight characteri stics, and  
3. parameters for the calculation of the effective dose, repeatedly for each calendar 
year.  
(2) In workplaces handling material with an increased natural radionuclide content, it is 
necessary to perform measurements in order to assess whether the level s of 
a) 300 Bq/m3 for the radon average activity volume concentration in the air during work 
performance and  
b) 1 mSv per year for the effective dose, which does not include doses received from 
exposure to natural background radiation or from exposure to radon a nd its progeny, have 
been exceeded.  
(3) In workplaces handling material with an increased natural radionuclide content, 
where the level defined under subsection  2 has been exceeded, individual doses for workers 
shall be defined on the basis of repeated measure ment and duration of stay in the workplace. 
In the case of work in several workplaces with the possibility of increased exposure to a 
natural source of radiation, individual doses of workers shall be aggregated. The defined 
individual doses of workers shal l be evaluated based on the values provided in 
subsection  4(b).  
(4) The definition of individual doses for workers does not have to be performed in the 
workplace handling material with an increased natural radionuclide content, on the condition 
that no change in the working conditions, production procedures or raw materials occurred, 
and 
a) no exceedance of the levels defined in to subsection  2 was detected, or  
b) upon the repeated measurement, pursuant to subsection  3, no possibility of exceeding  
1. 6 mSv per year for the effective dose or  
2. one third of the limits defined per calendar year in §  5(1)(b) through (d) was 
discovered.  
(5) In workplaces where values of individual doses for workers, pursuant to 
subsection  4(b), may be exceeded, individual doses for workers shall be  determined 
repeatedly in each calendar year.  
CELEX: 32013L0059  
§ 92 
Information on workplaces that may be subject to increased exposure to a natural 
source of radiation and submission of such information to the Office  
(For the implemen tation of §  93(4)(b) and (c) of the Atomic Act)  
(1) Data acquired by measurement, pursuant to §  91(2), and data on defined individual 
doses shall be kept on file for the entire period of a worker's work activity until the exposed 
worker reaches or would have r eached 75 years of age; however, no less than 30 years after 
the termination of the work activity.  
(2) The data defined in subsection  1 and information on exceedance of the values defined 
in § 91(2) and subsection  4(b) shall be submitted to the Office within o ne month of its 
acquisition.  - 61 - 
 
 (3) The following information on a workplace that may be subject to increased exposure 
to a natural source of radiation must be submitted to the Office:  
a) the identification details of the person performing the activity during which the 
workplace is operated,  
b) the name and address of the workplace,  
c) data on the workplace classification under §  93(1) of the Atomic Act and §  90, 
d) data on the raw material used in the workplace and a description of the technology used 
in the workplace,  
e) a des cription of the workplace as well as the organisation, method and regime of work 
and the duration of the worker’s stay in the workplace,  
f) the method of radioactive substance clearance from the workplace that may be subject to 
increased exposure to a natural  source of radiation,  
g) information on whether the released radioactive substance is used for the production of 
building material, and  
h) a description of the optimisation of radiation protection in the workplace, a description of 
measures taken to ensure radia tion protection and a description of the requirements under 
§ 94(2) of the Atomic Act in the workplace.  
(4) The information pursuant to subsection  3 shall be submitted to the Office for the first 
time prior to the commencement of the workplace operation and al so upon any change 
thereto.  
(5) The information defined in subsection  3 shall be kept on file for at least 30 years after 
the termination of the operation of the workplace that may be subject to increased exposure to 
a natural source of radiation.  
CELEX: 32013 L0059  
§ 93 
Optimisation of radiation protection in workplaces that may be subject to increased 
exposure to a natural source of radiation  
(For the implementation of §  66(6)(c) and s. 93(4)(d) of the Atomic Act)  
(1) The optimisation of radiat ion protection in a workplace that may be subject to 
increased exposure to a natural source of radiation shall be executed upon the exceedance of 
the level defined in §  91(3).  
(2) The measures taken to execute the radiation protection optimisation, pursuant to  
subsection  1, include in particular  
a) a change in  
1. raw materials used,  
2. technology, or  
3. the organisation, method or regime of work, and  
b) modification of the workplace that may be subject to increased exposure to a natural 
source of radiation, including modifica tion of the ventilation system.  
CELEX: 32013L0059  - 62 - 
 
 § 94 
Clearance of a radioactive substance from workplaces that may be subject to increased 
exposure to a natural source of radiation  
(For the implementation of §  95(6)(a) through (c) of the Atomic Act)  
(1) The measurement and evaluation of the content of radionuclides in a radioactive 
substance released from a workplace that may be subject to increased exposure to a natural 
source of radiation shall be executed, in the case of a workplace han dling material with an 
increased natural radionuclide content, particularly for  
a) deposits,  
b) sludge,  
c) used filters,  
d) waste and waste water discharged outside the workplace, and  
e) materials from this workplace intended for re -use or recycling.  
(2) The measurement and  evaluation pursuant to subsection  1 shall be performed for the 
first time upon the commencement of the workplace’s operation and then upon any change 
which could affect the radionuclide content of radioactive substances, at least once every 12 
months.  
(3) The internal regulation for the management of a radioactive substance released from a 
workplace that may be subject to increased exposure to a natural source of radiation shall 
include  
a) a list of radioactive substances handled in the workplace, including data on their 
radionuclide content,  
b) a description of the management of radioactive substances handled by the workplace, 
including the method of their disposal or clearance from the workplace,  
c) instructions for the safe management of radioactive substances handle d in the workplace, 
and 
d) procedures for keeping records on the quantity of radioactive substances.  
(4) The reports containing results of measurement and evaluation, pursuant to 
subsection  1, shall be submitted to the Office within 1 month of their acquisition, either 
directly or through the licensee, pursuant to §  9(2)(h)(7) of the Atomic Act.  
(5) The reports containing the results of measurement and evaluation, pursuant to 
subsection  1, shall be kept on file for at least 5 years after the termination of the operati on of 
the workplace that may be subject increased exposure to a natural source of radiation.  
CELEX: 32013L0059  
Title  III 
Existing exposure situations  
§ 95 
Workplace that may be subject to increased exposure to radon  
(For the implementat ion of §  96(3)(a) of the Atomic Act)  
The conditions for the classification of a workplace located on an underground or first 
above -ground floor of a building as a workplace that may be subject to increased exposure to 
radon are specified in Annex  25 to thi s implementing decree.  - 63 - 
 
 CELEX: 32013L0059  
§ 96 
Effective dose for a worker in a workplace that may be subject to increased exposure to 
radon  
(For the implementation of §  96(3)(b) of the Atomic Act)  
(1) In a workplace that may be subject to i ncreased exposure to radon, measurement to 
assess whether the reference level of 300  Bq/m3 for the radon average activity volume 
concentration has been exceeded at the time of the worker's stay in the workplace lasting 
2 000 hours over 12 months shall be e xecuted. In the case of a different duration of the 
worker's stay in the workplace, the integral over -time of the radon activity volume 
concentration corresponding to the duration of stay shall be used.  
(2) In a workplace that may be subject to increased expos ure to radon where exceedance 
of the reference level under subsection  1 has been discovered, it shall be assessed based on 
repeated measurements and determination of the effective dose whether for any worker the 
effective dose value of 6  mSv over 12 months  can be exceeded. If work is performed in 
several workplaces that may be subject to increased exposure to radon, the individual doses of 
a worker shall be aggregated.  
(3) In a workplace that may be subject to increased exposure to radon, where no 
exceedance of  the reference level under to subsection  1 was detected, or where during 
repeated measurements, pursuant to subsection  2, no possibility of exceeding the effective 
dose value of 6  mSv over 12 months was discovered, the measurement and determination of 
the effective dose does not have to be performed, unless  
a) there has been a change in  
1. working conditions,  
2. the organisation or regime of work, or  
b) the arrangement of the workplace, including a change in the ventilation system.  
(4) In a workplace that may be subject to  increased exposure to radon, where a possibility 
of exceeding the effective dose value for a worker of 6  mSv over 12 months has been 
discovered based on repeated measurements, pursuant to subsection  2, the measurement and 
determination of the effective do se shall be performed every calendar year.  
CELEX: 32013L0059  
§ 97 
Information on a workplace that may be subject to increased exposure to radon and 
submission of such information to the Office  
(For the implementation of §  96(3)(c) and ( d) of the Atomic Act)  
(1) The data acquired by measurement, pursuant to §  96(1), and data on defined 
individual doses for workers in a workplace that may be subject to increased exposure to 
radon, shall be kept on file in relation the period of the worker's wo rk activity, until the 
worker reaches or would have reached 75 years of age; however no less than 30 years after 
the termination of the work activity.  
(2) The data under to subsection  1 and information on exceedance of the values defined 
in § 96(1) and (2) sha ll be submitted to the Office within one month of its acquisition.  - 64 - 
 
 (3) The following information on the workplace that may be subject to increased 
exposure to radon shall be submitted to the Office:  
a) the identification details of the person performing the activ ity during which the 
workplace is operated,  
b) the name and address of the workplace,  
c) the type of workplace, pursuant to §  93(1) of the Atomic Act,  
d) a description of the workplace as well as the organisation, method and regime of work, 
ventilation conditions a nd the duration of the worker’s stay in the workplace,  
e) a description of the optimisation of radiation protection in the workplace, and  
f) where the condition pursuant to §  97(1) of the Atomic Act is fulfilled, a description of 
measures taken to ensure radiati on protection and a description of the requirements under 
§ 97(2) of the Atomic Act in the workplace.  
(4) The information defined in subsection  3 shall be submitted to the Office for the first 
time prior to the commencement of the operation of the workplace th at may be subject to an 
increased exposure to radon as well as upon any change in such information.  
(5) The information defined in subsection  3 shall be kept on file for at least 30 years after 
the termination of the operation of the workplace that may be subj ect to increased exposure to 
radon.  
CELEX: 32013L0059  
§ 98 
Optimisation of radiation protection in a workplace that may be subject to increased 
exposure to radon  
(For the implementation of §  66(6)(c) of the Atomic Act)  
(1) The optimisation of radiation protection in a workplace that may be subject to 
increased exposure to radon shall be executed upon exceedance of the reference level defined 
in § 96(1).  
(2) The measures taken to execute the radiation protection optimisation, pursuant to 
subsecti on 1, include in particular  
a) a change in the organisation, method or regime of work, and  
b) modification of the workplace that may be subject to increased exposure to radon, 
including modification of the ventilation system.  
CELEX: 32013L0059  
§ 99 
Radon -related index of a site  
(For the implementation of §  98(4) of the Atomic Act)  
(1) To determine the radon -related index of a site  
a) a representative set of 222Rn activity volume concentration measurements in soil air shall 
be used,  
b) gas permeability i n building foundations soil shall be assessed, and  
c) the local and general characteristics of geological subsoil affecting the direction and 
speed of radon movement in building foundations soils shall be applied.  - 65 - 
 
 (2) The determination of the radon -related index of a site shall be evaluated based on a 
comparison of  
a) the statistical characteristics of radon activity volume concentration in soil air and  
b) gas permeability ascertained by measurement or assessment based on professional 
experience and knowledge.  
(3) The metho d of the evaluation of results for the determination of the radon -related 
index of a site is specified in Annex  26 to this implementing decree.  
(4) The radon -related index of a site is low if  
a) the detected radon activity volume concentration in soil air is lowe r than  
1. 10 kBq/m3 for high permeable building foundations soil,  
2. 20 kBq/m3 for medium permeable building foundations soil, or  
3. 30 kBq/m3 for low permeable building foundations soil, or  
b) the numerical value of the radon -related index of a site determined by mea surement is 
lower than 10.  
(5) The radon -related index of a site is medium if  
a) the detected radon activity volume concentration in soil air is  
1. greater than 10  kBq/m3 and less than 30  kBq/m3 for high permeable building 
foundations soil,  
2. greater than 20  kBq/m3 and less than 70  kBq/m3 for medium permeable building 
foundations soil, or  
3. greater than 30  kBq/m3 and less than 100  kBq/m3 for low permeable building 
foundations soil, or  
b) the numerical value of the radon -related index of a site determined by measurement is 
greater than 10 and less than 35.  
(6) The radon -related index of a site is high if  
a) the detected radon activity volume concentration in soil air is greater than  
1. 30 kBq/m3 for high permeable building foundations soil,  
2. 70 kBq/m3 for medium permeable building foun dations soil, or  
3. 100 kBq/m3 for low permeable building foundations soil, or  
b) the numerical value of the radon -related index of a site determined by measurement is 
greater than 35.  
CELEX: 32013L0059  
§ 100 
Protection of individuals against  exposure in buildings  
(For the implementation of §  66(6)(a) and s. 99(5) of the Atomic Act)  
(1) The reference level for natural exposure inside a building with living or 
accommodation rooms is  
a) 300 Bq/m3 for radon activity volume concentration in the internal  atmosphere of the 
living or accommodation rooms; this value applies to the average value related to 
ventilation that is customary during use, or  
b) 1 µSv/h for the maximum spatial dose equivalent rate in living or accommodation rooms 
at a height of 1  m above  the floor and at a distance of 0.5  m from the walls.  - 66 - 
 
 (2) The value of the annual average radon activity volume concentration in the air, upon 
the exceedance of which the owners of buildings with living or accommodation rooms are 
obliged to take measures reduc ing the level of exposure, is 3  000 Bq/m3. 
(3) If no data corresponding to the actual state is available, it shall be understood, for the 
purposes of the preparation and evaluation of the planned measures to reduce the level of 
exposure from a natural source o f radiation, that a radon activity volume concentration of 
300 Bq/m3 in the case of an annual stay of an individual in such a building for a period of 
7 000 hours results in an annual effective dose of 10  mSv.  
(4) When the reference level pursuant to subsectio n 1 is exceeded, building owners shall 
assess the effectiveness of measures, including, in particular  
a) the rearrangement of manner in which the building is used, including modification of the 
ventilation system, or  
b) implementing structural or technological r emedial measures.  
(5) When following the procedure defined in subsection  4, building owners shall  
a) reasonably apply the procedures for radiation protection optimisation, pursuant to 
§ 66(1)(2)(c) and (5) of the Atomic Act,  
b) use information on the source of radon  and its gravity, and  
c) before the implementation of such measures, assess individual variants of the measures, 
evaluate their feasibility and related costs and give preference the measures resulting in 
the highest potential benefit, considering their method  of implementation, scope and 
duration.  
CELEX: 32013L0059  
Protection against natural radionuclides in water  
(For the implementation of §  100(3)(a) through (c) of the Atomic Act)  
§ 101 
(1) The maximum permissible value of radon activity volu me concentration in drinking 
water for public need and for supplying bottled water to the market is specified in Annex  27 
to this implementing decree.  
(2) The reference levels of the content of natural radionuclides in drinking water for 
public need and for su pplying bottled water to the market is specified in Annex  27 to this 
implementing decree.  
(3) The method and scope of systematic measurement and evaluation of the content of 
natural radionuclides in water is specified in Annex  27 to this implementing decree.  
(4) The systematic measurement and evaluation of the content of natural radionuclides in 
water shall be executed in water from an underground source and in a mixture of water from 
an underground source and surface water  
a) for the first time before the commencemen t of the supply of drinking water for public 
need,  
b) for the first time before the commencement of the supply of bottled water on the market 
in the Czech Republic, and  
c) at regular intervals during the supply of drinking water for public need or bottled water 
on the market in the Czech Republic.  
(5) The frequency of systematic measurement and evaluation of the content of natural 
radionuclides in water is specified in Annex  27 to this implementing decree.  - 67 - 
 
 (6) Within the framework of systematic measurement and evaluation  of the content of 
natural radionuclides in water, the determination of an indicative dose shall be executed if the 
investigation level of the total alpha activity volume concentration or the total beta activity 
volume concentration is exceeded. The invest igation levels are specified in Annex  27 to this 
implementing decree.  
(7) The determination of the indicative dose, pursuant to subsection  6, shall be executed 
based on the results of an additional analysis. The procedure for such additional analysis is 
specif ied in Annex  27 to this implementing decree.  
CELEX: 32013L0051  
§ 102 
(1) If the investigation level of the total alpha activity volume concentration is not 
exceeded and the exceedance of the investigation level of the total beta activity vo lume 
concentration is caused only by the presence of 40K, the indicative dose, pursuant to §  101(6), 
does not have to be determined and its reference level is regarded as not exceeded.  
(2) The systematic measurement of the content of natural radionuclides in w ater can be 
executed within the scope of the basic analysis if it has been  
a) discovered that the reference level of the indicative dose is not exceeded, or  
b) if it has been proven that upon exceeding the reference level pursuant to paragraph  a), 
radiation prot ection is optimised.  
(3) The scope of the basic analysis, pursuant to subsection  2, is specified in Annex  27 to 
this implementing decree.  
(4) If the results over five consecutive years do not exceed the reference levels defined in 
§ 101(2), the systematic measurem ent and evaluation of the content of natural radionuclides 
in water shall be further executed only in the case of a change that could affect the content of 
natural radionuclides in water, with the exception of water treatment to reduce the content of 
natur al radionuclides.  
(5) Adherence to the values pursuant to §  101(1), (2) and (6) shall be assessed  
a) for water supplied from the water supply system, at the point where water leaves the tap,  
b) for water supply from a water tank, at the point where water leaves the water tank,  
c) for water transferred into a bottle or container intended for sale, at the point where water 
is transferred into the bottle or container, and  
d) for water used for the preparation of food in a food -processing plant, at the point where 
water is use d in such plant.  
(6) Samples of water shall be taken for the systematic measurement and evaluation of the 
content of natural radionuclides in water in a manner that is representative in terms of  
a) water supplied throughout an entire calendar year and for the who le region supplied with 
water, and  
b) all produced water transferred into bottles or containers.  
CELEX: 32013L0051  - 68 - 
 
 § 103 
Data related to protection against natural radionuclides in water and the submission of 
such data to the Office  
(For t he implementation of §  100(3)(d) of the Atomic Act)  
(1) Records on results of the measurement of the content of natural radionuclides in water 
and other data shall include, in the case of the supply of drinking water for public need, the 
following  
a) the name or,  where applicable, the names, surname, date of birth and residential address, 
identification number, if assigned, of the individual who is the water supplier,  
b) The trade name, registered office or address of the seat of the organisational entity in the 
territory of the Czech Republic, if established, identification number, if assigned, of the 
legal entity who is the water supplier,  
c) the name of the water supply system,  
d) the identification details of the water source,  
e) data on the water source yield and annual v olume of water supplied,  
f) a list of supplied municipalities and the number of members of the public supplied,  
g) data on water treatment,  
h) data on measures pursuant to §  100(2)(c) and (d) of the Atomic Act,  
i) data on the place, date and method of sample collectio n, 
j) reports containing the results of sample measurement, and  
k) the registration number of the licensee who carries out the measurement.  
(2) Records on the results of the measurement of the content of natural radionuclides in 
water and other data shall include, i n the case of bottled water supplied on the market in the 
Czech Republic, the following  
a) identification details, within the scope defined in subsection  1(a) and (b),  
1. of the bottled water producer, and  
2. the bottled water importer,  
b) the marking and type of bott led water,  
c) the identification details of the water source,  
d) the annual production volume or import capacity for bottled water,  
e) data on water treatment,  
f) data on measures pursuant to §  100(2)(c) and (d) of the Atomic Act,  
g) data on the place, date and method of  sample collection,  
h) reports containing the results of sample measurement, and  
i) the registration number of the licensee who carries out the measurement.  
(3) The data defined in subsections  1 and 2 shall be retained for a period of 5 years from 
the termination of  the supply of drinking water for public need or placing bottled water on the 
market in the Czech Republic.  
(4) The data, pursuant to subsection  1 and 2, shall be submitted to the Office  
a) for the first time prior to the commencement of drinking water supply for  public need or 
bottled water supply on the market in the Czech Republic, and  
b) every calendar year.  
(5) The data, pursuant to subsection  1(i) and (j), and subsection  2(g) and (h), may be 
submitted to the Office via the licensee, pursuant to §  9(2)(h)(6) of the Atomic Act.  - 69 - 
 
 (6) The data on the termination of drinking water supply for public need or bottled water 
supply on the market in the Czech Republic shall be submitted to the Office immediately.  
§ 104 
Optimisation of radiation protection for th e supply of drinking water for public need or 
bottled water supply on the market in the Czech Republic  
(For the implementation of §  66(6)(c) of the Atomic Act)  
When taking measures pursuant to §  100(2)(c) and (d) of the Atomic Act, the supplier of 
water an d the importer of bottled water shall take into account the effectiveness of such 
measures. These measures refer, in particular, to:  
a) the selection of a different source of water,  
b) in the case of bottled water import, the import of similar bottled water with  a lower 
natural radionuclide content, or  
c) the installation of equipment reducing the natural radionuclide content.  
CELEX: 32013L0051  
§ 105 
Protection against natural radionuclides in building materials  
(For the implementation of §  9(2)( j) and s. 101(4)(a) through (c) of the Atomic Act)  
(1) The list of building materials pursuant to §  9(2)(j) of the Atomic Act is specified in 
Annex  28 to this implementing decree.  
(2) The reference level for building material is 1  mSv per year for the effective do se 
received by the representative person from external exposure to gamma radiation when using 
a building with living or accommodation rooms, excluding doses received from exposure due 
to natural background radiation.  
(3) The activity weight concentration index  I is a dimensionless quantity given by the 
formula  
I=a K/3 000 Bq.kg-1 + aRa/300 Bq kg-1 + a Th/200 Bq kg-1 
based on activity weight concentrations expressed in Bq.kg-1 for the radionuclides 40K, 
226Ra and 228Th. 
(4) The value of the activity weight concentrati on index for building materials is 1. Upon 
exceeding this value, the reference level pursuant to subsection  2 is regarded as exceeded.  
(5) The systematic measurement and evaluation of the natural radionuclide content in 
building materials shall be executed by the determination of the activity weight concentration 
index  
a) for the first time prior to placing the building material on the market, and  
b) at least once per calendar year.  
(6) The effective dose for the representative person due to the use of building material 
from external exposure to gamma radiation shall be determined based on the results of the 
measurement defined in subsection  5 or 7 and evaluated by comparison with the reference 
level defined subsection  2, where the value of the activity weight concentrati on index for the 
building material defined in subsection  3 has been exceeded.  - 70 - 
 
 (7) If the building material or part thereof refers to a radioactive substance with an 
impaired balance of long -lived natural radionuclides released from a workplace containing 
mater ial with an increased natural radionuclide content, the determination of the activity 
weight concentration index shall be replaced by the measurement defined in to §  95(1)(b) of 
the Atomic Act. The results of this measurement shall be evaluated by comparis on with the 
reference level defined in to subsection  2. 
CELEX: 32013L0059  
§ 106 
Data related to protection against natural radionuclides in building material and the 
submission of such data to the Office  
(For the implementation of §  101(4)(d) of the Atomic Act)  
(1) Records on the results of the measurement of the natural radionuclide content in 
building materials and other data shall include  
a) the name or, where applicable, names, surname, date of birth and residential address of 
the place of residence, identification number, if assigned, of the individual who is the 
producer or importer of the building material,  
b) trade name, registered office or address of the seat of the organisational entity in the 
territory of the Czech Republic, if establis hed, identification number, if assigned, of the 
legal entity who is the producer or importer of the building material,  
c) designation or type of the building material and raw materials for its production and data 
on its origin,  
d) data on the annual volume of pr oduction or import of the building material,  
e) data on the origin of the imported building material,  
f) data characterising the scope and method of use of the building material in structures,  
g) data on the place, date and method of sample collection,  
h) reports cont aining the results of sample measurement, and  
i) the registration number of the licensee who carries out the measurement.  
(2) The data, pursuant to subsection  1, shall be retained for at least 5 years from the 
termination of the building material supply on the ma rket in the Czech Republic.  
(3) The data, pursuant to subsection  1, shall be submitted to the Office  
a) for the first time before the building material is placed on the market in the Czech 
Republic, and  
b) every calendar year.  
(4) The data, pursuant to subsection  1(g) a nd (h), can be submitted to the Office via the 
licensee, pursuant to §  9(2)(h)(6) of the Atomic Act.  
(5) Information on the termination of the building material supply on the market in the 
Czech Republic shall be submitted to the Office without any undue delay . - 71 - 
 
 Title  IV 
Clearance  
§ 107 
Clearance levels for a workplace handling sources of ionising radiation  
(For the implementation of §  76(6) of the Atomic Act)  
(1) The clearance levels for a workplace handling sources of ionising radiation are 
regarded as exceeded,  
a) in the case of the clearance of an object or solid substance, if  
1. in the object or the quantity of solid substance subject to clearance, the sum of the 
quotients of the average activity weight concentrations for individual radionuclides 
and their clearance levels of the activity weight concentration is greater than 1; the 
clearance levels of the activity weight concentration are specified in Annex  7 to this 
implementing decree, or  
2. wherever, over an area of 300  cm2 on the surface of the obj ect subject to clearance, 
surface contamination is greater than the surface activity clearance levels; the 
clearance levels for surface activity are specified in Annex  7 to this implementing 
decree,  
b) when discharging waste waters into surface waters, if the  sum of the products of the 
average activity volume concentrations for individual released radionuclides and their 
maximum conversion factors h ing for intake by ingestion for an adult member of the 
public is greater than 0.1  mSv/m3; the maximum conversion factor h ing for intake by 
ingestion for an adult member of the public is specified in Annex  3 to this implementing 
decree,  
c) when discharging waste water into the waste water disposal system for public need, if the 
sum of the products of the average activity  volume concentrations for individual 
radionuclides subject to clearance and their conversion factors h ing for intake by ingestion 
for an adult member of the public is greater than 10  mSv/m3, 
d) when releasing radionuclides into the atmosphere, if the sum of the products of the 
average activity volume concentrations for individual released radionuclides and their 
maximum conversion factors h inh for intake by inhalation for an adult member of the 
public, according to the tables in Annex  3 to this implementing d ecree, is greater than 
0.1 µSv/m3; the conversion factor h inh for intake by inhalation for an adult member of the 
public is specified in Annex  3 to this implementing decree,  
e) when depositing on a waste dump, if  
1. in the object or solid substance subject to cl earance the sum of the quotients of the 
average activity weight concentrations for individual radionuclides and their 
clearance levels of activity weight concentration is greater than 1, or  
2. the dose equivalent rate at a distance of 1  m from the surface of a waste dump at the 
point of deposition at the waste dump is greater than 0.4  µSv/h, and  
f) when incinerated in an incineration plant, if  
1. the combustion gases released into the atmosphere exceed the clearance levels 
pursuant to paragraph  d), or  
2. the ash that a rises from combustion exceeds the clearance levels pursuant to 
paragraph  a) or e).  
(2) The average activity weight concentration pursuant to, subsection  1(a) and (e), applies 
to every object subject to clearance or quantity of homogeneous solid substance subje ct to 
clearance. The quantity of solid substance subject to clearance is regarded as homogeneous if - 72 - 
 
 the density of the solid substance in no part of its volume differs from its average density by 
more than 30  %, and the activity weight concentration of the  solid substance in no part of the 
volume differs from its activity weight concentration by more than 30  %. 
(3) The average activity volume concentration of the quantity of the liquid or gaseous 
substance subject to clearance, pursuant to subsection  1(b) throu gh (d), shall be determined 
from a representative sample of the substance extracted before its release or extracted during 
release.  
CELEX: 32013L0059  
§ 108 
Clearance levels for a workplace that may be subject to increased exposure to a natural 
source of radiation  
(For the implementation of §  95(2) of the Atomic Act)  
(1) The clearance levels for the clearance of solid materials from a workplace that may be 
subject to increased exposure to a natural source of radiation, including their disposa l on 
waste dumps, clearance for re -use, recycling or combustion, are  
a) the activity weight concentration of natural radionuclides from the series 238U 1 kBq/kg,  
b) the activity weight concentration of natural radionuclides from the series 232Th 1  kBq/kg, 
or 
c) the activity weight concentration of 40K 10  kBq/kg.  
(2) The clearance levels, pursuant to subsection  1, are not regarded as exceeded if the 
average activity weight concentration of none of the radionuclides is greater than the value of 
the clearance level.  
(3) The cl earance levels for discharge of waste water into surface water are  
a) the average total alpha activity volume concentration in all substances 0.5  Bq/l,  
b) the average total beta activity volume concentration after the deduction of the 
contribution of 40K in all substances 1  Bq/l.  
(4) The clearance levels, pursuant to subsection  3, are not regarded as exceeded if the 
average alpha activity volume concentration or the average beta activity volume concentration 
after the deduction of the contribution of 40K is not great er than the value of the clearance 
level.  
(5) The clearance levels for discharge of waste water into the waste water disposal 
system for public need are  
a) the average total alpha activity volume concentration in all substances 50  Bq/l, and  
b) the average total beta  activity volume concentration after the deduction of the 
contribution of 40K in all substances 100  Bq/l.  
(6) The clearance levels pursuant to subsection  5 are not regarded as exceeded if the 
average alpha activity volume concentration or the average beta acti vity volume concentration 
after the deduction of the contribution of 40K is not greater than the value of the clearance 
level.  
(7) The average values, pursuant to subsection  1, 3 and 5, apply to the quantity of 
materials subject to clearance in which it is pos sible to regard the activity weight 
concentration or the activity volume concentration as homogeneous.  
CELEX: 32013L0059  - 73 - 
 
 Title  V 
Emergency exposure situations  
§ 109 
Reference levels for emergency exposure situations  
(For the implementat ion of §  66(6)(a) of the Atomic Act)  
The reference level for the exposure of an individual in an emergency exposure situation 
is 100  mSv for the sum of the effective dose from external exposure and the committed 
effective dose from internal exposure.  
§ 110 
Protective measures for an emergency exposure situation  
(For the implementation of §  104(9)(a) of the Atomic Act)  
(1) When substantiating and optimising within the framework of decision -making on the 
implementation of protective measures i n an emergency exposure situation, the following 
shall be taken into account  
a) circumstances affecting the feasibility of the protective measures, particularly  
1. population density,  
2. traffic situation,  
3. existence of large settlement units,  
4. time necessary for the  preparation of the evacuation of residents, or  
5. the current meteorological situation,  
b) the magnitude of exposure of individuals which would be averted due to the 
implementation of the protective measure, and  
c) the consequences of the implemented protective me asures.  
(2) Urgent protective measures shall be always implemented if doses absorbed in organs 
could exceed, over less than 2 days in any individual, the levels specified in Annex  29 to this 
implementing decree.  
(3) A justified urgent protective measure refers to  
a) sheltering, if the averted effective dose is greater than 10  mSv over the period of 
sheltering lasting no longer than 2 days,  
b) stable iodine administration, if  
1. internal contamination by radioactive iodine is imminent, and  
2. the averted committed equivalent do se in the thyroid gland caused by iodine 
radioisotopes is greater than 100  mSv over the first 7 days, or  
c) evacuation, if the sum of the effective dose so far received in an emergency exposure 
situation when taking into account the effect of the already impl emented protective 
measures and the effective dose, which could be averted, is greater than 100  mSv over the 
first 7 days.  
(4) A justified urgent recovery countermeasure refers to  
a) the limitation of the use of food, water and fodder contaminated by radionuclide s, if the 
averted annual committed effective dose is greater than 1  mSv, and  
b) the relocation of members of the public, if it is not possible to ensure an effective dose for 
the members of the public, after their return to the affected territory, of lower th an 
20 mSv over the following twelve months.  - 74 - 
 
 (5) When deciding on the cancellation of the implemented protective measures, exposure 
which would occur after the cancellation of the protective measures shall be taken into 
account.  
(6) The cancellation of protective m easure including sheltering, evacuation and 
relocation of members of the public is regarded as justified if the exposure, which would 
occur after the cancellation of protective measures over the following twelve months, were 
lower than 20  mSv.  
(7) In the case of a concurrent emergency exposure situation and a radiological 
emergency after a separate incident, any possible aggravation of damage sustained due to 
such a radiological emergency as a result of the implementation of a protective measure 
within a scope larger than the benefit from the reduction of exposure shall be taken into 
account.  
CELEX: 32013L0059  
Informing an emergency responder of the risk related to the intervention and data on 
intervention  
(For the implementation of §  104(9)(b) and (c) of the At omic Act)  
§ 111 
(1) An emergency responder whose assignment to the intervention is assumed 
beforehand shall receive, within the framework of their regular education, general and 
regularly updated information on  
a) the effects of ionising radia tion and the related potential health risks, and  
b) the precautions of radiation protection to avert or mitigate exposure.  
(2) The person responsible for appointing the emergency responder shall inform the 
emergency person before the intervention about  
a) the curren t radiation situation, and  
b) all protective measures which must be adhered to in the course of the intervention.  
(3) An emergency person whose assignment to the intervention is not assumed 
beforehand shall receive the information pursuant to subsection  1 within a reasonable scope. 
The emergency responder shall confirm in writing that they have received such information.  
(4) Emergency responders who are members of the Fire Rescue Service of the Czech 
republic, the Police of the Czech Republic or the Army of the Czech Republic shall be 
informed, prior to taking or swearing an oath of service, that within the framework of their 
service they can be assigned to an intervention where the reference level of 100  mSv may be 
exceeded.  
CELEX: 32013L0059  
§ 112 
(1) The consent of the emergency person with their participation in the intervention shall 
be recorded in writing along with the emergency responder's signature. The consent of the 
emergency responder who is a member of the team of the Fire Rescue Service of the Czech 
republic, of the Police of the Czech Republic or the Army of the Czech Republic is regarded 
as given upon taking or swearing an oath of service.  - 75 - 
 
 (2) Personal protective equipment and aids for emergency responders shall prevent 
surface and internal co ntamination of such persons.  
(3) The list of emergency responders and the records and data on facts pursuant to §  111 
and subsection  1 shall be retained by the delegating person for a period of 10 years as of the 
completion of the intervention.  
(4) Records on moni toring and the evaluation of the magnitude of exposure received by 
the emergency responder shall be retained by the delegating person for a period of 30 years as 
of the completion of the intervention.  
(5) Identification details of the emergency responder and t he dose received by them shall 
be submitted by the delegating person to the Office immediately upon the completion of the 
intervention.  
CELEX: 32013L0059  
§ 113 
Procedures for the optimisation of measures to manage lasting exposure resul ting from 
an emergency exposure situation  
(For the implementation of §  66(6)(c) of the Atomic Act)  
(1) When optimising measures to be taken to manage lasting exposure resulting from an 
emergency exposure situation, the following shall be taken into account in  the existing 
exposure situation  
a) external exposure due to environmental contamination, and  
b) internal exposure due to the intake of contaminated food or contaminated water.  
(2) Unless more accurate information on the duration of stay in buildings and in the fiel d 
is known, it shall be understood that the representative person spends 7  000 hours per 
calendar year inside buildings.  
(3) When optimising measures to be taken to manage lasting exposure resulting from the 
radioactive contamination of the food chain, the fol lowing shall be taken into account  
a) the level of contamination of items of the food chain, and  
b) the representation of the contaminated items of the food chain among the food purchases 
of the representative person.  
PART THREE  
SECURITY OF RADIOACT IVE SOURCES  
§ 114 
Procedures for the security of radioactive sources  
(For the implementation of §  164(2) of the Atomic Act)  
(1) The licensee shall provide for level 1 -3 security of a radioactive source by  
a) specifying information relevant to the security of a radioactive source and by providing 
for the protection of such information against misuse, and  
b) by taking measures to detect and restrict unauthorised access to radioactive sources and 
respond thereto, particularly  
1. by preventing unauthorised relocation , where a radioactive source from security level 
1 is concerned, and  - 76 - 
 
 2. by reducing the likelihood of unauthorised relocation to the minimum attainable 
level, where a radioactive source from security level 2 or 3 is concerned.  
(2) Securing a radioactive source fr om security categories 1 to 3 shall involve  
a) a system for the detection of unauthorised access to a radioactive source from security 
categories 1 to 3, which shall provide for  
1. the detection of unauthorised relocation of a radioactive source from security le vel 3,  
2. the detection of any attempted unauthorised access to a radioactive source from 
security levels 1 and 2,  
3. the detection of any attempted unauthorised access to a radioactive source from 
security level 1 by an unauthorised employee of the licensee, an d 
4. obtaining information necessary for the immediate evaluation of the detected 
unauthorised access,  
b) a system of barriers to restrict relocation of a radioactive source, which shall provide for  
1. a reduction in the likelihood of unauthorised relocation of a r adioactive source from 
security level 3,  
2. a reduction in the likelihood of unauthorised relocation of a radioactive source from 
security level 2 to the minimum attainable level, and  
3. sufficient restriction to be able to start an intervention and prevent unau thorised 
relocation of a radioactive source from security level 1, and  
c) a system of response to unauthorised access, which shall include  
1. taking measures in the event of unauthorised relocation of a radioactive source from 
security level 3,  
2. taking measures t o prevent or interrupt unauthorised relocation of a radioactive 
source from security level 2 in due time, and  
3. immediate intervention to prevent unauthorised relocation of a radioactive source 
and ensure sufficient human as well as material resources for su ch an intervention for 
a radioactive source from security level 1.  
§ 115 
Elements of the security system  
(For the implementation of §  164(2) of the Atomic Act)  
The elements which the security system for a radioactive source shall includ e are  
a) technical means and organisational measures obviously making access to a radioactive 
source more difficult and therefore discouraging an unauthorised individual from 
misconduct,  
b) technical means and organisational measures providing for the early dete ction of 
unauthorised access to a radioactive source,  
c) mechanical and other barriers extending as much as possible the time necessary for 
unauthorised relocation of a radioactive source,  
d) organisational measures ensuring a response to unauthorised access to a radioactive 
source, and  
e) rules for work with individuals, information and technical means aimed at securing a 
radioactive source.  - 77 - 
 
 § 116 
Security plan  
(For the implementation of §  24(7) of the Atomic Act)  
The security plan shall include  
a) a description of the radioactive source, its categorisation and a description of the method 
of its use,  
b) a description of the place of use and deposition of the radioactive source, its environment 
and its location in buildings and on premises,  
c) the location  of the buildings and premises in respect of places open to the public,  
d) the objectives of the security plan for the buildings and premises, taking into account the 
following  
1. special conditions and hazards, and  
2. procedures to prevent undesirable consequences  of unlawful acts,  
e) a description of measures taken to secure the radioactive source, including  
1. control of access to the radioactive source,  
2. the detection of unauthorised access to the radioactive source,  
3. the restriction of unauthorised access to the radioa ctive source,  
4. intervention in the event of unauthorised access to the radioactive source,  
5. methods of communication between the persons who evaluate outputs from the 
security system and the persons performing the intervention, and  
6. the assessment of the effe ctiveness of the measures pursuant to paragraphs  1-5, 
f) a description of administrative measures taken to secure the radioactive source, including  
1. the rights and duties of workers,  
2. standard and extraordinary operations with the radioactive source, maintenanc e and 
repairs of the technical means restricting access to the radioactive source and 
providing for the early detection of unauthorised access to the radioactive source,  
3. the method of ensuring the protection of information relevant to the radioactive 
sourc e security,  
4. the methods of controlling access to the radioactive source, and  
5. personnel training methods, and  
g) a description of measures to be taken if the threat becomes aggravated.  
§ 117 
Protection of information relevant to radioactive  source security  
(For the implementation of §  164(2) of the Atomic Act)  
(1) The information relevant to radioactive source security refers to  
a) data on radioactive sources and their location,  
b) the planned modes of transport and their route,  
c) data included in the s ecurity plan,  
d) data on the security system,  
e) data on safeguarding,  
f) data on administrative measures within the framework of the radioactive source security, 
and 
g) data on the intervention preventing unauthorised relocation of a radioactive source from 
security level 1.  - 78 - 
 
 (2) The information, pursuant to subsection  1, may be provided by the licensee only to 
those persons who need to be aware of said information in order to be able to carry out the 
activity entrusted to them, and only within the scope necessary for such  performance.  
(3) The licensee shall appoint an individual responsible for providing for the 
safeguarding of the radioactive source and the coordination of activities within the framework 
of the radioactive source security.  
(4) The licensee shall ensure that the i ndividual participating in the safeguarding of the 
radioactive source and the individual independently accessing the radioactive source from 
security level 1 are selected and continuously assessed with respect to the security risk that 
such a person may re present.  
PART FOUR  
FINAL PROVISIONS  
§ 118 
Notification  
This implementing decree was notified in accordance with Directive (EU)  2015/1535 of 
the European Parliament and of the Council of 9  September  2015 laying down a procedure for 
the p rovision of information in the field of technical regulations and of rules on Information 
Society services.  
§ 119 
Transitional provision  
(1) The long -term stability test performed ,pursuant to §  29(1)(a)(6), after the entry into 
force of th is implementing decree, on a simple source of ionising radiation  
a) a dental intraoral x -ray device used for medical exposure, manufactured before 2002, on 
which the previous long -term stability test was performed in 2016, shall be performed 
within 12 months of this long -term stability test,  
b) a dental intraoral x -ray device used for medical exposure, manufactured before 2004, on 
which the previous long -term stability test was performed in 2015, shall be performed 
within 24 months of this long -term stability tes t, 
c) a dental panoramic x -ray device used for medical exposure, manufactured before 2008, 
shall be performed within 12 months of the previous long -term stability test,  
d) a dental panoramic x -ray device used for medical exposure, manufactured between 2008 
and 2 011, shall be performed within 24 months of the previous long -term stability test, or  
e) a veterinary x -ray device manufactured before 2000, shall be performed within 24 months 
of the previous long -term stability test.  
(2) The requirements imposed on sources of i onising radiation used for medical exposure 
provided for in  
a) § 79(a) and (b), (c)(3) and (4) and (d)(3) and (6) shall be applied to those sources of 
ionising radiation installed after the entry into force of this implementing decree, and  
b) § 79(c)(5) and (d)( 7) shall be applied to those sources of ionising radiation installed after 
1 February  2018.  
(3) The requirements imposed on sources of ionising radiation used for medical exposure 
provided for in  - 79 - 
 
 a) § 80(a)(3), (b)(7), (c)(6), (d) and (e)(3) through (6) shall be applied to those sources of 
ionising radiation installed after the entry into force of this implementing decree, and  
b) § 80(a)(4) shall be applied to those sources of ionising radiation installed after 
1 February  2018.  
CELEX: 32013L0059  
§ 120 
Entry into force  
This implementing decree shall enter into force on 1  January  2017, with the exception of  
a) § 79(c)(2) and (d)(2) and §  80(b)(4) through (6), (c)(1) through (5) and (e)(1) and (2), 
which shall enter into force on 1  February  2018, and  
b) § 80(a)(1), which shall enter into force on 1  January  2021.  
CELEX: 32013L0059  
 
 
 
Chairwoman:  - 80 - 
 
 Annex  1 to Implementing Decree No. ........./...........Sb.  
 
D-values for selected radionuclides and their multiples  
 
Radionuclide  D-value 
[TBq]  
H-3 2.103 
Be-7 1.100 
Be-10 3.101 
C-11 6.10-2 
C-14 5. 101 
N-13 6.10-2 
F-18 6. 10-2 
Na-22 3. 10-2 
Na-24 2. 10-2 
Mg-28 2. 10-2 
Al-26 3. 10-2 
Si-31 1. 101 
Si-32* 7. 100 
P-32 1. 101 
P-33 2.102 
S-35 6. 101 
Cl-36 2. 101 
Cl-38 5. 10-2 
Ar-37 UL 
Ar-39 3.102 
Ar-41 5. 10-2 
K-40 UL 
K-42 2.10-1 
K-43 7. 10-2 
Ca-41 UL 
Ca-45 1.102 
Ca-47* 6. 10-2 
Sc-44 3. 10-2 
Sc-46 3. 10-2 
Sc-47 7.10-1 
Sc-48 2. 10-2 
Ti-44* 3. 10-2 
V-48 2. 10-2 Radionuclide  D-value 
[TBq]  
V-49 2.103 
Cr-51 2. 100 
Mn-52 2. 10-2 
Mn-53 UL 
Mn-54 8. 10-2 
Mn-56 4. 10-2 
Fe-52* 2. 10-2 
Fe-55 8.102 
Fe-59 6. 10-2 
Fe-60* 6. 10-2 
Co-55* 3. 10-2 
Co-56 2. 10-2 
Co-57 7.10-1 
Co-58 7. 10-2 
Co-58m*  7. 10-2 
Co-60 3. 10-2 
Ni-59 1.103 
Ni-63 6. 101 
Ni-65 1.10-1 
Cu-64 3.10-1 
Cu-67 7.10-1 
Zn-65 1.10-1 
Zn-69 3. 101 
Zn-69m*  2.10-1 
Ga-67 5.10-1 
Ga-68 7. 10-2 
Ga-72 3. 10-2 
Ge-68* 7. 10-2 
Ge-71 1.103 
Ge-77* 6. 10-2 
As-72 4.10-2 
As-73 4. 101 
As-74 9. 10-2 Radionuclide  D-value 
[TBq]  
As-76 2.10-1 
As-77 8. 100 
Se-75 2.10-1 
Se-79 2.102 
Br-76 3. 10-2 
Br-77 2.10-1 
Br-82 3. 10-2 
Kr-81 3.101 
Kr-85 3. 101 
Kr-85m 5.10-1 
Kr-87 9. 10-2 
Rb-81 1.10-1 
Rb-83 1.10-1 
Rb-84 7. 10-2 
Rb-86 7.10-1 
Rb-87 UL 
Sr-82 6. 10-2 
Sr-85 1.10-1 
Sr-85m*  1.10-1 
Sr-87m 2.10-1 
Sr-89 2. 101 
Sr-90* 1. 100 
Sr-91* 6. 10-2 
Sr-92* 4. 10-2 
Y-87* 9. 10-2 
Y-88 3. 10-2 
Y-90 5. 100 
Y-91 8. 100 
Y-91m*  1.10-1 
Y-92 2.10-1 
Y-93 6.10-1 
Zr-88* 2. 10-2 
Zr-93* UL - 81 - 
 
 Radionuclide  D-value 
[TBq]  
Zr-95* 4. 10-2 
Zr-97* 4. 10-2 
Nb-93m 3.102 
Nb-94 4. 10-2 
Nb-95 9. 10-2 
Nb-97 1.10-1 
Mo-93* 3.102 
Mo-99* 3.10-1 
Tc-95m 1.10-1 
Tc-96 3. 10-2 
Tc-96m*  3. 10-2 
Tc-97 UL 
Tc-97m 4.101 
Tc-98 5. 10-2 
Tc-99 3. 101 
Tc-99m 7.10-1 
Ru-97 3.10-1 
Ru-103*  1.10-1 
Ru-105*  8.10-2 
Ru-106*  3.10-1 
Rh-99 1.10-1 
Rh-101 3.10-1 
Rh-102 3.10-2 
Rh-102m  1.10-1 
Rh-103m  9.102 
Rh-105 9.10-1 
Pd-103*  9. 101 
Pd-107 UL 
Pd-109 2. 101 
Ag-105 1.10-1 
Ag-108m  4.10-2 
Ag-110m  2.10-2 
Ag-111 2. 100 
Cd-109 2. 101 
Cd-113m  4. 101 
Cd-115*  2.10-1 
Cd-115m  3. 100 Radionuclide  D-value 
[TBq]  
In-111 2.10-1 
In-113m  3.10-1 
In-114m  8.10-1 
In-115m  4.10-1 
Sn-113*  3.10-1 
Sn-117m  5.10-1 
Sn-119m  7. 101 
Sn-121m*  7. 101 
Sn-123 7. 100 
Sn-125 1.10-1 
Sn-126*  3.10-2 
Sb-122 1.10-1 
Sb-124 4.10-2 
Sb-125*  2.10-1 
Sb-126 2.10-2 
Te-121 1.10-1 
Te-121m*  1.10-1 
Te-123m  6.10-1 
Te-125m  1. 101 
Te-127 1. 101 
Te-127m*  3. 100 
Te-129 1. 100 
Te-129m*  1. 100 
Te-131m*  4.10-2 
Te-132*  3.10-2 
I-123 5.10-1 
I-124 6.10-2 
I-125 2.10-1 
I-126 1.10-1 
I-129 UL 
I-131 2.10-1 
I-132 3.10-2 
I-133 1.10-1 
I-134 3.10-2 
I-135 4.10-2 
Xe-122 6.10-2 
Xe-123*  9.10-2 Radionuclide  D-value 
[TBq]  
Xe-127 3.10-1 
Xe-131m  1. 101 
Xe-133 3. 100 
Xe-135 3.10-1 
Cs-129 3.10-1 
Cs-131 2. 101 
Cs-132 1.10-1 
Cs-134 4.10-2 
Cs-134m*  4.10-2 
Cs-135 UL 
Cs-136 3.10-2 
Cs-137*  1.10-1 
Ba-131*  2.10-1 
Ba-133 2.10-1 
Ba-133m  3.10-1 
Ba-140*  3.10-2 
La-137 2. 101 
La-140 3.10-2 
Ce-139 6.10-1 
Ce-141 1. 100 
Ce-143*  3.10-1 
Ce-144* 9.10-1 
Pr-142 1. 100 
Pr-143 3. 101 
Nd-147*  6.10-1 
Nd-149*  2.10-1 
Pm-143 2.10-1 
Pm-144 4.10-2 
Pm-145 1. 101 
Pm-147 4. 101 
Pm-148m  3.10-2 
Pm-149 6. 100 
Pm-151 2.10-1 
Sm-145*  4. 100 
Sm-147 UL 
Sm-151 5.102 
Sm-153 2. 100 - 82 - 
 
 Radionuclide  D-value 
[TBq]  
Eu-147 2.10-1 
Eu-148 3.10-2 
Eu-149 2. 100 
Eu-150b  2. 100 
Eu-150a  5.10-2 
Eu-152 6.10-2 
Eu-152m  2.10-1 
Eu-154 6.10-2 
Eu-155 2. 100 
Eu-156 5.10-2 
Gd-146*  3.10-2 
Gd-148 4.10-1 
Gd-153 1. 100 
Gd-159 2. 100 
Tb-157 1.102 
Tb-158 9.10-2 
Tb-160 6.10-2 
Dy-159 6. 100 
Dy-165 3. 100 
Dy-166*  1. 100 
Ho-166 2. 100 
Ho-166m  4.10-2 
Er-169 2.102 
Er-171 2.10-1 
Tm-167 6.10-1 
Tm-170 2. 101 
Tm-171 3.102 
Yb-169 3.10-1 
Yb-175 2. 100 
Lu-172 4.10-2 
Lu-173 9.10-1 
Lu-174 8.10-1 
Lu-174m*  6.10-1 
Lu-177 2. 100 
Hf-172*  4.10-2 
Hf-175 2.10-1 
Hf-181 1.10-1 Radionuclide  D-value 
[TBq]  
Hf-182*  5.10-2 
Ta-178a  7.10-2 
Ta-179 6. 100 
Ta-182 6.10-2 
W-178 9.10-1 
W-181 5.100 
W-185 1.102 
W-187 1.10-1 
W-188*  1. 100 
Re-184 8.10-2 
Re-184m*  7.10-2 
Re-186 4. 100 
Re-187 UL 
Re-188 1. 100 
Re-189 1. 100 
Os-185 1.10-1 
Os-191 2. 100 
Os-191m*  1. 100 
Os-193 1. 100 
Os-194*  7.10-1 
Ir-189 1. 100 
Ir-190 5.10-2 
Ir-192 8.10-2 
Ir-194 7.10-1 
Pt-188*  4.10-2 
Pt-191 3.10-1 
Pt-193 3.103 
Pt-193m  1. 101 
Pt-195m  2. 100 
Pt-197 4. 100 
Pt-197m*  9.10-1 
Au-193 6.10-1 
Au-194 7.10-2 
Au-195 2. 100 
Au-198 2.10-1 
Au-199 9.10-1 
Hg-194*  7.10-2 Radionuclide  D-value 
[TBq]  
Hg-195m*  2.10-1 
Hg-197 2. 100 
Hg-197m*  7.10-1 
Hg-203 3.10-1 
Tl-200 5.10-2 
Tl-201 1. 100 
Tl-202 2.10-1 
Tl-204 2. 101 
Pb-201*  9.10-2 
Pb-202*  2.10-1 
Pb-203 2.10-1 
Pb-205 UL 
Pb-210*  3.10-1 
Pb-212*  5.10-2 
Bi-205 4.10-2 
Bi-206 2.10-2 
Bi-207 5.10-2 
Bi-210*  8. 100 
Bi-210m  3.10-1 
Bi-212*  5.10-2 
Po-210 6.10-2 
At-211 5.10-1 
Rn-222 4.10-2 
Ra-223*  1.10-1 
Ra-224*  5.10-2 
Ra-225*  1.10-1 
Ra-226*  4.10-2 
Ra-228*  3.10-2 
Ac-225 9.10-2 
Ac-227*  4.10-2 
Ac-228 3.10-2 
Th-227*  8.10-2 
Th-228*  4.10-2 
Th-229*  1.10-2 
Th-230*  7.10-2 
Th-231 1. 101 
Th-232*  UL - 83 - 
 
 Radionuclide  D-value 
[TBq]  
Th-234*  2. 100 
Pa-230*  1.10-1 
Pa-231*  6.10-2 
Pa-233 4.10-1 
U-230*  4.10-2 
U-232*  6.10-2 
U-233 7.10-2 
U-234*  1.10-1 
U-235* 8.10-5 
U-236 2.10-1 
U-238*  UL 
UNatural  UL 
UDepleted  UL 
UEnriched 10 -20% 8.10-4 
UEnriched 20% a 
více 8.10-5 
Np-235 1.102 
Np-236b*  7.10-3 
Np-236a  8.10-1 
Np-237*  7.10-2 
Np-239 5.10-1 
Pu-236 1.10-1 
Pu-237 2. 100 
Pu-238 6.10-2 
Pu-239 6.10-2 
Pu-240 6.10-2 
Pu-241*  3. 100 
Pu-242 7.10-2 
Pu-244*  3.10-4 
Am-241 6.10-2 
Am-242m*  3.10-1 
Am-243*  2.10-1 
Am-244 9.10-2 
Cm-240 3.10-1 
Cm-241*  1.10-1 
Cm-242 4.10-2 
Cm-243 2.10-1 Radionuclide  D-value 
[TBq]  
Cm-244 5.10-2 
Cm-245 9.10-2 
Cm-246 2.10-1 
Cm-247 1.10-3 
Cm-248 5.10-3 
Bk-247 8.10-2 
Bk-249 1. 101 
Cf-248*  1.10-1 
Cf-249 1.10-1 
Cf-250 1.10-1 
Cf-251 1.10-1 
Cf-252 2.10-2 
Cf-253 4.10-1 
Cf-254 3.10-4 
239Pu/9Be(1) 6.10-2 
241Am/9Be(1) 6.10-2 
 - 84 - 
 
  
Legend:  
 
‘UL’ - unlimited amount  
‘*’ - the daughter radionuclide contrib utes significantly to the total dose within the scope of the scenario under 
consideration  
(1) - activity is the activity of the radionuclide emitting alpha radiation  
‘a’ - short half -life 
‘b’ - long half -life - 85 - 
 
 Annex  2 to Decree No  .../…Sb.  
 
Radiation weight ing factors, tissue weighting factors, quality factors  
 
Radiation weighting factors  
 
Type of radiation  Radiation weighting factor  
wR 
photons  1 
electrons and muons  1 
protons and charged pions  2 
alpha particles, fission fragments, heavy ions  20 
neutrons : the following 
continuous neutron energy 
functions:  En < 1 Mev  
 
1 MeV ≤ En ≤ 50 MeV  
 
En > 50 MeV  
 
 
 
Legend:  
 
En – neutron energy  
 
 
Tissue weighting factors  
 
Organ/tissue  Tissue weighting factor  
wt 
lungs, stomach, colon, breast, bone marrow, the adrenal glands, the 
upper respiratory tract, gall bladder, heart, kid ney, lymph nodes, 
muscle, oral mucosa, pancreas, prostate/uterus, small intestine, 
spleen, thymus  0.12 
gonads  0.08 
thyroid gland, oesophagus, bladder, liver  0.04 
bone surface, skin, brain, salivary glands  0.01 
 
 
Quality factors Q  
 
Linear energy transfe r L [keV/µm]  Quality factor Q (L)  
less than 10  1 
10 to 100  0.32.L -2.2 
more than  100 300.L -0.5 
 
 
CELEX:32013L0059  - 86 - 
 
 Annex  3 to Decree No  .../…Sb.  
 
Conversion factors  
 
Conversion factors for the conversion of the specific activity of radioactive noble ga ses 
to the effective dose for a radiation worker and an adult individual from the population  
 
Nuclide  T½ Conversion factor  
[Sv.d-1/Bq.m-3] 
Ar-37 35.02 d  4.1.10-15 
Ar-39 269 y  1.1.10-11 
Ar-41 1.827 h  5.3.10-9 
Kr-74 11.50 min  4.5.10-9 
Kr-76 14.8 h  1.6.1 0-9 
Kr-77 74.7 min  3.9.10-9 
Kr-79 35.04 h  9.7.10-10 
Kr-81 210.000 y  2.1.10-11 
Kr-81m 13 s 4.8.10-10 
Kr-83m 1.83 h  2.1.10-13 
Kr-85 10.72 y  2.2.10-11 
Kr-85m 4.48 h  5.9.10-10 
Kr-87 76.3 min  3.4.10-9 
Kr-88 2.84 h  8.4.10-9 
Xe-120 40 min  1.5.10-9 
Xe-121 40.1 min  7.5.10-9 
Xe-122 20.1 h  1.9.10-10 
Xe-123 2.08 h  2.4.10-9 
Xe-125 17.0 h  9.3.10-10 
Xe-127 36.41 d  9.7.10-10 
Xe-129m  8.0 d  8.1.10-11 
Xe-131m  11.9 d  3.2.10-11 
Xe-133 5.245 d  1.2.10-10 
Xe-133m  2.188 d  1.1.10-10 
Xe-135m  9.09 h  1.6.10-9 
Xe-135 15.29 min  9.6.10-10 
Xe-138 14.17 min  4.7.10-9 - 87 - 
 
 The type of absorption in the digestive tract for various chemical substances and 
compounds  
 
Element  Chemical substance, compound  f1 
hydrogen  tritiated water (used as a fluid)  1.00 
 organically bound trit ium 1.00 
beryllium  all compounds  0.005  
carbon  marked organic compounds  1.00 
fluorine  all compounds  1.00 
sodium  all compounds  1.00 
magnesium  all compounds  0.50 
aluminium  all compounds  0.01 
silicon  all compounds  0.01 
phosphorus  all compounds  0.80 
sulphur  inorganic compounds  0.80 
 elemental sulphur  0.10 
 organic sulphur compounds (in foods)  1.00 
chlorine  all compounds  1.00 
potassium  all compounds  1.00 
calcium  all compounds  0.30 
scandium  all compounds  0.0001  
titanium  all compounds  0.01 
vanadium  all compounds  0.01 
chromium  hexavalent chromium compounds  0.10 
 trivalent chromium compounds  0.01 
manganese  all compounds  0.10 
iron all compounds  0.10 
cobalt  all unspecified compounds  0.10 
nickel  all compounds  0.05 
copper  all compounds  0.50 
zinc all compounds  0.50 
gallium  all compounds  0.001  
germanium  all compounds  1.00 
arsenic  all compounds  0.50 
selenium  all unspecified compounds  0.80 
 elemental selenium and selenates  0.05 
bromine  all compounds  1.00 
rubidium  all compounds  1.00 
strontium  all unspecified compounds  0.30 
 strontium titanate (SrTiO 3) 0.01 - 88 - 
 
 Element  Chemical substance, compound  f1 
yttrium  all compounds  0.0001  
zirconium  all compounds  0.002  
niobium  all compounds  0.01 
molybdenum  all unspecified compounds  0.80 
 molybdenum trisulphide  0.05 
technetium  all compounds  0.80 
ruthenium  all compounds  0.05 
rhodium  all compounds  0.05 
palladium  all compounds  0.005  
silver  all compounds  0.05 
cadmium  all inorganic compounds  0.05 
indium  all compounds  0.02 
tin all compounds  0.02 
antimony  all compounds  0.10 
tellurium  all compou nds 0.30 
iodine  all compounds  1.00 
caesium  all compounds  1.00 
barium  all compounds  0.10 
lanthanum  all compounds  0.0005  
cerium  all compounds  0.0005  
praseodymium  all compounds  0.0005  
neodymium  all compounds  0.0005  
promethium  all compounds  0.0005  
samarium  all compounds  0.0005  
europium  all compounds  0.0005  
gadolinium  all compounds  0.0005  
terbium  all compounds  0.0005  
dysprosium  all compounds  0.0005  
holmium  all compounds  0.0005  
erbium  all compounds  0.0005  
thulium  all compounds  0.0005  
ytterbium  all compounds  0.0005  
lutetium  all compounds  0.0005  
hafnium  all compounds  0.002  
tantalum  all compounds  0.001  
wolfram  all unspecified compounds  0.30 
 wolframic acid  0.01 
rhenium  all compounds  0.80 - 89 - 
 
 Element  Chemical substance, compound  f1 
osmium  all compounds  0.01 
iridium  all compounds  0.01 
platinum  all compounds  0.01 
gold all compounds  0.10 
mercury  all inorganic compounds  0.02 
 methyl mercury  1.00 
 all unspecified organic compounds  0.40 
thallium  all compounds  1.00 
lead all compounds  0.20 
bismuth  all compounds  0.05 
polonium  all compoun ds 0.10 
astatine  all compounds  1.00 
francium  all compounds  1.00 
radium  all compounds  0.20 
actinium  all compounds  0.0005  
thorium  all unspecified compounds  0.0005  
 oxides and hydroxides  0.0002  
protactinium  all compounds  0.0005  
uranium  all unspecified  compounds  0.02 
 most quadrivalent uranium compounds, e.g. UO 2, U3O 8, UF 4 0.002  
neptunium  all compounds  0.0005  
plutonium  all unspecified compounds  0.0005  
 nitrates  0.0001  
 insoluble oxides  0.00001  
americium  all compounds  0.0005  
curium  all compounds  0.0005  
berkelium  all compounds  0.0005  
californium  all compounds  0.0005  
einsteinium  all compounds  0.0005  
fermium  all compounds  0.0005  
mendelevium  all compounds  0.0005  
 
Legend:  
 
Absorption in the digestive tract is expressed by the coefficient f, chara cterising in model calculations the 
fraction that is transferred to body fluids in the digestive tract.  
Values of the coefficient f 1 are used to calculate the conversion factors for intake via ingestion by a radiation 
worker.  - 90 - 
 
 The type of absorption in the lungs for various chemical substances and compounds  
 
Element  Chemical substance, compound  type f1 
beryllium  all unspecified compounds  
oxides, halides, and nitrates  M 
S 0.005  
0.005  
fluorine  determined by the compounding cation  
determined by the compoundin g cation  
determined by the compounding cation  F 
M 
S 1.00 
1.00 
1.00 
sodium  all compounds  F 1.00 
magnesium  all unspecified compounds  
oxides, hydroxides, carbides, halides, and nitrates  F 
M 0.50 
0.50 
aluminium  all unspecified compounds  F 0.01 
 oxides, hyd roxides, carbides, halides, nitrates, and metallic aluminium  M 0.01 
silicon  all unspecified compounds  F 0.01 
 oxides, hydroxides, carbides, and nitrates  M 0.01 
 aluminosilicate glass aerosol  S 0.01 
phosphorus  all unspecified compounds  F 0.80 
 phosphat es: determined by the compounding cation  M 0.80 
sulphur  sulphides and sulphates: determined by the compounding cation  F 0.80 
 elementary sulphur; sulphides and sulphates: determined by the 
compounding cation  M 0.80 
chlorine  determined by the compounding  cation  F 1.00 
 determined by the compounding cation  M 1.00 
potassium  all compounds  F 1.00 
calcium  all compounds  M 0.30 
scandium  all compounds  S 0.0001  
titanium  all unspecified compounds  F 0.01 
 oxides, hydroxides, carbides, halides, and nitrates  M 0.01 
 strontium titanate (SrTiO 3) S 0.01 
vanadium  all unspecified compounds  F 0.01 
 oxides, hydroxides, carbides, and halides  M 0.01 
chromium  all unspecified compounds  F 0.10 
 halides and nitrates  M 0.10 
 oxides and hydroxides  S 0.10 
manganese  all un specified compounds  F 0.10 
 oxides, hydroxides, halides, and nitrates  M 0.10 
iron all unspecified compounds  F 0.10 
 oxides, hydroxides, and halides  M 0.10 
cobalt  all unspecified compounds  M 0.10 
 oxides, hydroxides, halides, and nitrates  S 0.05 - 91 - 
 
 Element  Chemical substance, compound  type f1 
nicke l all unspecified compounds  F 0.05 
 oxides, hydroxides, and carbides  M 0.05 
copper  all unspecified inorganic compounds  F 0.50 
 sulphides, halides, and nitrates  M 0.50 
 oxides and hydroxides  S 0.50 
zinc all compounds  S 0.50 
gallium  all unspecified com pounds  F 0.001  
 oxides, hydroxides, carbides, halides, and nitrates  M 0.001  
germanium  all unspecified compounds  F 1.00 
 oxides, sulphides, and halides  M 1.00 
arsenic  all compounds  M 0.50 
selenium  all unspecified inorganic compounds  F 0.80 
 elemental selenium, oxides, hydroxides, and carbides  M 0.80 
bromine  determined by the compounding cation  F 1.00 
 determined by the compounding cation  M 1.00 
rubidium  all compounds  F 1.00 
strontium  all unspecified compounds  F 0.30 
 strontium titanate (SrTiO 3) S 0.01 
yttrium  all unspecified compounds  M 0.0001  
 oxides and hydroxides  S 0.0001  
zirconium  all unspecified compounds  F 0.002  
 oxides, hydroxides, halides, and nitrates  M 0.002  
 zirconium carbide  S 0.002  
niobium  all unspecified compounds  M 0.01 
 oxide s and hydroxides  S 0.01 
molybdenum  all unspecified compounds  F 0.80 
 molybdenum sulphide, oxides, and hydroxides  S 0.05 
technetium  all unspecified compounds  F 0.80 
 oxides, hydroxides, halides, and nitrates  M 0.80 
ruthenium  all unspecified compounds  F 0.05 
 halides  M 0.05 
 oxides and hydroxides  S 0.05 
rhodium  all unspecified compounds  F 0.05 
 halides  M 0.05 
 oxides and hydroxides  S 0.05 
palladium  all unspecified compounds  F 0.005  
 halides and nitrates  M 0.005  - 92 - 
 
 Element  Chemical substance, compound  type f1 
 oxides and hydroxides  S 0.005  
silver all unspecified compounds and metallic silver  F 0.05 
 nitrates and sulphites  M 0.05 
 oxides, hydroxides, and carbides  S 0.05 
cadmium  all unspecified compounds  F 0.05 
 sulphides, halides, and nitrates  M 0.05 
 oxides and hydroxides  S 0.05 
indium  all unspecified compounds  F 0.02 
 oxides, hydroxides, halides, and nitrates  M 0.02 
tin all unspecified compounds  F 0.02 
 stannic phosphate, sulphides, oxides, hydroxides, halides, and nitrates  M 0.02 
antimony  all unspecified compounds  F 0.10 
 oxides, hy droxides, halides, sulphides, sulphates, and nitrates  M 0.01 
tellurium  all unspecified compounds  F 0.30 
 oxides, hydroxides, and nitrates  M 0.30 
iodine  all compounds  F 1.00 
caesium  all compounds  F 1.00 
barium  all compounds  F 0.10 
lanthanum  all unspec ified compounds  F 0.0005  
 oxides and hydroxides  M 0.0005  
cerium  all unspecified compounds  M 0.0005  
 oxides, hydroxides, and fluoride  S 0.0005  
praseodymium  all unspecified compounds  M 0.0005  
 oxides, hydroxides, carbides, and fluorides  S 0.0005  
neodym ium all unspecified compounds  M 0.0005  
 oxides, hydroxides, carbides, and fluorides  S 0.0005  
promethium  all unspecified compounds  M 0.0005  
 oxides, hydroxides, carbides, and fluorides  S 0.0005  
samarium  all compounds  M 0.0005  
europium  all compounds  M 0.0005  
gadolinium  all unspecified compounds  F 0.0005  
 oxides, hydroxides, and fluoride  M 0.0005  
terbium  all compounds  M 0.0005  
dysprosium  all compounds  M 0.0005  
holmium  all unspecified compounds  M 0.0005  
erbium  all compounds  M 0.0005  
thulium  all comp ounds  M 0.0005  - 93 - 
 
 Element  Chemical substance, compound  type f1 
ytterbium  all unspecified compounds  M 0.0005  
 oxides, hydroxides, and fluoride  S 0.0005  
lutetium  all unspecified compounds  M 0.0005  
 oxides, hydroxides, and fluoride  S 0.0005  
hafnium  all unspecified compounds  F 0.002  
 oxides, hydroxide s, halides, carbides, and nitrates  M 0.002  
tantalum  all unspecified compounds  M 0.001  
 elemental tantalum oxides, hydroxides, halides, carbides, nitrates, and 
nitrides  S 0.001  
wolfram  all compounds  F 0.30 
rhenium  all unspecified compounds  F 0.80 
 oxides, hydroxides, halides, and nitrates  M 0.80 
osmium  all unspecified compounds  F 0.01 
 halides and nitrates  M 0.01 
 oxides and hydroxides  S 0.01 
iridium  all unspecified compounds  F 0.01 
 metal iridium, halides, and nitrates  M 0.01 
 oxides and hydroxid es S 0.01 
platinum  all compounds  F 0.01 
gold all unspecified compounds  F 0.10 
 halides and nitrates  M 0.10 
 oxides and hydroxides  S 0.10 
mercury  sulphates  F 0.02 
 oxides, hydroxides, halides, nitrates, and sulphites  M 0.02 
 all organic compounds  F 0.40 
thallium  all compounds  F 1.00 
lead all compounds  F 0.20 
bismuth  bismuth nitrate  F 0.05 
 all unspecified compounds  M 0.05 
polonium  all unspecified compounds  F 0.10 
 oxides, hydroxides, and nitrates  M 0.10 
astatine  determined by the compounding ca tion F 1.00 
 determined by the compounding cation  M 1.00 
francium  all compounds  F 1.00 
radium  all compounds  M 0.20 
actinium  all unspecified compounds  F 0.0005  
 halides and nitrates  M 0.0005  
 oxides and hydroxides  S 0.0005  - 94 - 
 
 Element  Chemical substance, compound  type f1 
thorium  all unspecified com pounds  M 0.0005  
 oxides and hydroxides  S 0.0002  
protactinium  all unspecified compounds  M 0.0005  
 oxides and hydroxides  S 0.0005  
uranium  most hexavalent compounds, e.g. UF 6 , UO 2F2 and UO 2(NO 3)2 F 0.02 
 poorly soluble compounds, e.g. UO 3, UF 4, UCl 4 and most other 
hexavalent compounds  M 0.02 
 highly insoluble compounds, e.g. UO 2 and U 3O8 S 0.002  
neptunium  all compounds  M 0.0005  
plutonium  all unspecified compounds  M 0.0005  
 insoluble oxides  S 0.00001  
americium  all compounds  M 0.0005  
curium  all compo unds  M 0.0005  
berkelium  all compounds  M 0.0005  
californium  all compounds  M 0.0005  
einsteinium  all compounds  M 0.0005  
fermium  all compounds  M 0.0005  
mendelevium  all compounds  M 0.0005  
 
Legend:  
 
Absorption in the lungs is represented by type F, M, or S  characterising in model calculations the rate at which a 
substance passes from the lungs to body fluids (F – fast, M - medium, S - slow), and the coefficient f 1 
characterising the fraction that passes from the lungs into the digestive tract.  
Values of the  coefficient f 1 are used to calculate the conversion factors for intake via inhalation by a radiation 
worker.  - 95 - 
 
 Conversion factors h inh for intake via inhalation of radioactive aerosols and h ing for 
intake via ingestion by a radiation worker  
 
Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
hydrogen         
H-3 (tritiated 
water)  12.35 y      1 1.8.10-11 
(organically 
bound tritium)       1 4.2.10-11 
beryllium         
Be-7 53.3 d  M 0.005  4.8.10-11 4.3.10-11 0.005  2.8.10-11 
  S 0.005  5.2.10-11 4.6.10-11   
Be-10 1.6 x 106 y M 0.005  9.1.10-9 6.7.10-9 0.005  1.1.10-9 
  S 0.005  3.2.10-8 1.9.10-8   
carbon         
C-11 20.38 min      1 2.4.10-11 
C-14 5730 y      1 5.8.10-10 
fluorine         
F-18 109.77 mi n F 1 3.0.10-11 5.4.10-11 1 4.9.10-11 
  M 1 5.7.10-11 8.9.10-11   
  S 1 6.0.10-11 9.3.10-11   
sodium         
Na-22 2.602 y  F 1 1.3.10-9 2.0.10-9 1 3.2.10-9 
Na-24 15.00 h  F 1 2.9.10-10 5.3.10-10 1 4.3.10-10 
magnesium         
Mg-28 20.91 h  F 0.5 6.4.10-10 1.1.10-9 0.5 2.2.10-9 
  M 0.5 1.2.10-9 1.7.10-9   
aluminium         
Al-26 7.16.105 y F 0.01 1.1.10-8 1.4.10-8 0.01 3.5.10-9 
  M 0.01 1.8.10-8 1.2.10-8   
silicon         
Si-31 157.3 min  F 0.01 2.9.10-11 5.1.10-11 0.01 1.6.10-10 
  M 0.01 7.5.10-11 1.1.10-10   
  S 0.01 8.0.10-11 1.1.10-10   
Si-32 450 y  F 0.01 3.2.10-9 3.7.10-9 0.01 5.6.10-10 
  M 0.01 1.5.10-8 9.6.10-9   
  S 0.01 1.1.10-7 5.5.10-8   - 96 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
phosphorus         
P-32 14.29 d  F 0.8 8.0.10-10 1.1.10-9 0.8 2.4.10-9 
  M 0.8 3.2.10-9 2.9.10-9   
P-33 25.4 d  F 0.8 9.6.10-11 1.4.10-10 0.8 2.4.10-10 
  M 0.8 1.4.10-9 1.3.10-9   
sulphur         
S-35 inorg.  87.44 d  F 0.8 5.3.10-11 8.0.10-11 0.8 1.4.10-10 
  M 0.8 1.3.10-9 1.1.10-9 0.1 1.9.10-10 
S-35 org.       1 7.7.10-10 
chlorine         
Cl-36 3.01 x 105 y F 1 3.4.10-10 4.9.10-10 1 9.3.10-10 
  M 1 6.9.10-9 5.1.10-9   
Cl-38 37.21 min  F 1 2.7.10-11 4.6.10-11 1 1.2.10-10 
  M 1 4.7.10-11 7.3.10-11   
Cl-39 55.6 min  F 1 2.7.10-11 4.8.10-11 1 8.5.10-11 
  M 1 4.8.10-11 7.6.10-11   
potassium         
K-40 1.28 x 109 y F 1 2.1.10-9 3.0.10-9 1 6.2.10-9 
K-42 12.36 h  F 1 1.3.10-10 2.0.10-10 1 4.3.10-10 
K-43 22.6 h  F 1 1.5.10-10 2.6.10-10 1 2.5.10-10 
K-44 22.13 min  F 1 2.1.10-11 3.7.10-11 1 8.4.10-11 
K-45 20 min  F 1 1.6.10-11 2.8.10-11 1 5.4.10-11 
calcium         
Ca-41 1.4 x 105 y M 0.3 1.7.10-10 1.9.10-10 0.3 2.9.10-10 
Ca-45 163 d  M 0.3 2.7.10-9 2.3.10-9 0.3 7.6.10-10 
Ca-47 4.53 d  M 0.3 1.8.10-9 2.1.10-9 0.3 1.6.10-9 
scandium         
Sc-43 3.891 h  S 1.0.10-4 1.2.10-10 1.8.10-10 1.0.10-4 1.9.10-10 
Sc-44 3.927 h  S 1.0.10-4 1.9.10-10 3.0.10-10 1.0.10-4 3.5.10-10 
Sc-44m 58.6 h  S 1.0.10-4 1.5.10-9 2.0.10-9 1.0.10-4 2.4.10-9 
Sc-46 83.83 d  S 1.0.10-4 6.4.10-9 4.8.10-9 1.0.10-4 1.5.10-9 
Sc-47 3.351 d  S 1.0.10-4 7.0.10-10 7.3.10-10 1.0.10-4 5.4.10-10 
Sc-48 43.7 h  S 1.0.10-4 1.1.10-9 1.6.10-9 1.0.10-4 1.7.10-9 
Sc-49 57.4 min  S 1.0.10-4 4.1.10-11 6.1.10-11 1.0.10-4 8.2.10-11 - 97 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
titanium         
Ti-44 47.3 y  F 0.01 6.1.10-8 7.2.10-8 0.01 5.8.10-9 
  M 0.01 4.0.10-8 2.7.10-8   
  S 0.01 1.2.10-7 6.2.10-8   
Ti-45 3.08 h  F 0.01 4.6.10-11 8.3.10-11 0.01 1.5.10-10 
  M 0.01 9.1.10-11 1.4.10-10   
  S 0.01 9.6.10-11 1.5.10-10   
vanadium         
V-47 32.6 min  F 0.01 1.9.10-11 3.2.10-11 0.01 6.3.10-11 
  M 0.01 3.1.10-11 5.0.10-11   
V-48 16.238 d  F 0.01 1.1.10-9 1.7.1 0-9 0.01 2.0.10-9 
  M 0.01 2.3.10-9 2.7.10-9   
V-49 330 d  F 0.01 2.1.10-11 2.6.10-11 0.01 1.8.10-11 
  M 0.01 3.2.10-11 2.3.10-11   
chromium         
Cr-48 22.96 h  F 0.1 1.0.10-10 1.7.10-10 0.1 2.0.10-10 
  M 0.1 2.0.10-10 2.3.10-10 0.01 2.0.10-10 
  S 0.1 2.2.10-10 2.5.10-10   
Cr-49 42.09 min  F 0.1 2.0.10-11 3.5.10-11 0.1 6.1.10-11 
  M 0.1 3.5.10-11 5.6.10-11 0.01 6.1.10-11 
  S 0.1 3.7.10-11 5.9.10-11   
Cr-51 27.704 d  F 0.1 2.1.10-11 3.0.10-11 0.1 3.8.10-11 
  M 0.1 3.1.10-11 3.4.10-11 0.01 3.7.10-11 
  S 0.1 3.6.10-11 3.6.10-11   
manganese         
Mn-51 46.2 min  F 0.1 2.4.10-11 4.2.10-11 0.1 9.3.10-11 
  M 0.1 4.3.10-11 6.8.10-11   
Mn-52 5.591 d  F 0.1 9.9.10-10 1.6.10-9 0.1 1.8.10-9 
  M 0.1 1.4.10-9 1.8.10-9   
Mn-52m 21.1 min  F 0.1 2.0.10-11 3.5.10-11 0.1 6.9.10-11 
  M 0.1 3.0.10-11 5.0.10-11   
Mn-53 3.7 x 106 y F 0.1 2.9.10-11 3.6.10-11 0.1 3.0.10-11 
  M 0.1 5.2.10-11 3.6.10-11   
Mn-54 312.5 d  F 0.1 8.7.10-10 1.1.10-9 0.1 7.1.10-10 
  M 0.1 1.5.10-9 1.2.10-9   - 98 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Mn-56 2.5785 h  F 0.1 6.9.10-11 1.2.10-10 0.1 2.5.10-10 
  M 0.1 1.3.10-10 2.0.10-10   
iron        
Fe-52 8.275 h  F 0.1 4.1.10-10 6.9.10-10 0.1 1.4.10-9 
  M 0.1 6.3.10-10 9.5.10-10   
Fe-55 2.7 y  F 0.1 7.7.10-10 9.2.10-10 0.1 3.3.10-10 
  M 0.1 3.7.10-10 3.3.10-10   
Fe-59 44.529 d  F 0.1 2.2.10-9 3.0.10-9 0.1 1.8.10-9 
  M 0.1 3.5.10-9 3.2.10-9   
Fe-60 1 x 105 y F 0.1 2.8.10-7 3.3.10-7 0.1 1.1.10-7 
  M 0.1 1.3.10-7 1.2.10-7   
cobalt         
Co-55 17.54 h  M 0.1 5.1.10-10 7.8.10-10 0.1 1.0.10-9 
  S 0.05 5.5.10-10 8.3.10-10 0.05 1.1.10-9 
Co-56 78.76 d  M 0.1 4.6.10-9 4.0.10-9 0.1 2.5.10-9 
  S 0.05 6.3.10-9 4.9.10-9 0.05 2.3.10-9 
Co-57 270.9 d  M 0.1 5.2.10-10 3.9.10-10 0.1 2.1.10-10 
  S 0.05 9.4.10-10 6.0.10-10 0.05 1.9.10-10 
Co-58 70.80 d  M 0.1 1.5.10-9 1.4.10-9 0.1 7.4.10-10 
  S 0.05 2.0.10-9 1.7.10-9 0.05 7.0.10-10 
Co-58m 9.15 h  M 0.1 1.3.10-11 1.5.10-11 0.1 2.4.10-11 
  S 0.05 1.6.10-11 1.7.10-11 0.05 2.4.10-11 
Co-60 5.271 y  M 0.1 9.6.10-9 7.1.10-9 0.1 3.4.10-9 
  S 0.05 2.9.10-8 1.7.10-8 0.05 2.5.10-9 
Co-60m 10.47 min  M 0.1 1.1.10-12 1.2.10-12 0.1 1.7.10-12 
  S 0.05 1.3.10-12 1.2.10-12 0.05 1.7.10-12 
Co-61 1.65 h  M 0.1 4.8.10-11 7.1.10-11 0.1 7.4.10-11 
  S 0.05 5.1.10-11 7.5.10-11 0.05 7.4.10-11 
Co-62m 13.91 min  M 0.1 2.1.10-11 3.6.10-11 0.1 4.7.10-11 
  S 0.05 2.2.10-11 3.7.10-11 0.05 4.7.10-11 
nickel         
Ni-56 6.10 d  F 0.05 5.1.10-10 7.9.10-10 0.05 8.6.10-10 
  M 0.05 8.6.10-10 9.6.10-10   
Ni-57 36.08 h  F 0.05 2.8.10-10 5.0.10-10 0.05 8.7.10-10 
  M 0.05 5.1.10-10 7.6.10-10   - 99 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Ni-59 7.5 x 104 y F 0.05 1.8.10-10 2.2.10-10 0.05 6.3.10-11 
  M 0.05 1.3.10-10 9.4.10-11   
Ni-63 96 y F 0.05 4.4.10-10 5.2.10-10 0.05 1.5.10-10 
  M 0.05 4.4.10-10 3.1.10-10   
Ni-65 2.520 h  F 0.05 4.4.10-11 7.5.10-11 0.05 1.8.10-10 
  M 0.05 8.7.10-11 1.3.10-10   
Ni-66 54.6 h  F 0.05 4.5.10-10 7.6.10-10 0.05 3.0.10-9 
  M 0.05 1.6.10-9 1.9.10-9   
copper         
Cu-60 23.2 min  F 0.5 2.4.10-11 4.4.10-11 0.5 7.0.10-11 
  M 0.5 3.5.10-11 6.0.10-11   
  S 0.5 3.6.10-11 6.2.10-11   
Cu-61 3.408 h  F 0.5 4.0.10-11 7.3.10-11 0.5 1.2.10-10 
  M 0.5 7.6.10-11 1.2.10-10   
  S 0.5 8.0.10-11 1.2.10-10   
Cu-64 12.701 h  F 0.5 3.8.10-11 6.8.10-11 0.5 1.2.10-10 
  M 0.5 1.1.10-10 1.5.10-10   
  S 0.5 1.2.10-10 1.5.10-10   
Cu-67 61.86 h  F 0.5 1.1.10-10 1.8.10-10 0.5 3.4.10-10 
  M 0.5 5.2.10-10 5.3.10-10   
  S 0.5 5.8.10-10 5.8.10-10   
zinc        
Zn-62 9.26 h  S 0.5 4.7.10-10 6.6.10-10 0.5 9.4.10-10 
Zn-63 38.1 min  S 0.5 3.8.10-11 6.1.10-11 0.5 7.9.10-11 
Zn-65 243.9 d  S 0.5 2.9.10-9 2.8.10-9 0.5 3.9.10-9 
Zn-69 57 min  S 0.5 2.8.10-11 4.3.10-11 0.5 3.1.10-11 
Zn-69m 13.76 h  S 0.5 2.6.10-10 3.3.10-10 0.5 3.3.10-10 
Zn-71m 3.92 h  S 0.5 1.6.10-10 2.4.10-10 0.5 2.4.10-10 
Zn-72 46.5 h  S 0.5 1.2.10-9 1.5.10-9 0.5 1.4.10-9 
gallium         
Ga-65 15.2 min  F 0.001  1.2.10-11 2.0.10-11 0.001  3.7.10-11 
  M 0.001  1.8.10-11 2.9.10-11   
Ga-66 9.40 h  F 0.001  2.7.10-10 4.7.10-10 0.001  1.2.10-9 
  M 0.001  4.6.10-10 7.1.10-10   
Ga-67 78.26 h  F 0.001  6.8.10-11 1.1.10-10 0.001  1.9.10-10 - 100 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.001  2.3.10-10 2.8.10-10   
Ga-68 68.0 min  F 0.001  2.8.10-11 4.9.10-11 0.001  1.0.10-10 
  M 0.001  5.1.10-11 8.1.10-11   
Ga-70 21.15 min  F 0.001  9.3.10-12 1.6.10-11 0.001  3.1.10-11 
  M 0.001  1.6.10-11 2.6.10-11   
Ga-72 14.1 h  F 0.001  3.1.10-10 5.6.10-10 0.001  1.1.10-9 
  M 0.001  5.5.10-10 8.4.10-10   
Ga-73 4.91 h  F 0.001  5.8.10-11 1.0.10-10 0.001  2.6.10-10 
  M 0.001  1.5.10-10 2.0.10-10   
germanium         
Ge-66 2.27 h  F 1 5.7.10-11 9.9.10-11 1 1.0.10-10 
  M 1 9.2.10-11 1.3.10-10   
Ge-67 18.7 min  F 1 1.6.10-11 2.8.10-11 1 6.5.10-11 
  M 1 2.6.10-11 4.2.10-11   
Ge-68 288 d  F 1 5.4.1 0-10 8.3.10-10 1 1.3.10-9 
  M 1 1.3.10-8 7.9.10-9   
Ge-69 39.05 h  F 1 1.4.10-10 2.5.10-10 1 2.4.10-10 
  M 1 2.9.10-10 3.7.10-10   
Ge-71 11.8 d  F 1 5.0.10-12 7.8.10-12 1 1.2.10-11 
  M 1 1.0.10-11 1.1.10-11   
Ge-75 82.78 min  F 1 1.6.10-11 2.7.10-11 1 4.6.10-11 
  M 1 3.7.10-11 5.4.10-11   
Ge-77 11.30 h  F 1 1.5.10-10 2.5.10-10 1 3.3.10-10 
  M 1 3.6.10-10 4.5.10-10   
Ge-78 87 min  F 1 4.8.10-11 8.1.10-11 1 1.2.10-10 
  M 1 9.7.10-11 1.4.10-10   
arsenic         
As-69 15.2 min  M 0.5 2.2.10-11 3.5.10-11 0.5 5.7.10-11 
As-70 52.6 min  M 0.5 7.2.10-11 1.2.10-10 0.5 1.3.10-10 
As-71 64.8 h  M 0.5 4.0.10-10 5.0.10-10 0.5 4.6.10-10 
As-72 26.0 h  M 0.5 9.2.10-10 1.3.10-9 0.5 1.8.10-9 
As-73 80.30 d  M 0.5 9.3.10-10 6.5.10-10 0.5 2.6.10-10 
As-74 17.76 d  M 0.5 2.1.1 0-9 1.8.10-9 0.5 1.3.10-9 
As-76 26.32 h  M 0.5 7.4.10-10 9.2.10-10 0.5 1.6.10-9 
As-77 38.8 h  M 0.5 3.8.10-10 4.2.10-10 0.5 4.0.10-10 - 101 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
As-78 90.7 min  M 0.5 9.2.10-11 1.4.10-10 0.5 2.1.10-10 
selenium         
Se-70 41.0 min  F 0.8 4.5.10-11 8.2.10-11 0.8 1.2.10-10 
  M 0.8 7.3.10-11 1.2.10-10 0.05 1.4.10-10 
Se-73 7.15 h  F 0.8 8.6.10-11 1.5.10-10 0.8 2.1.10-10 
  M 0.8 1.6.10-10 2.4.10-10 0.05 3.9.10-10 
Se-73m 39 min  F 0.8 9.9.10-12 1.7.10-11 0.8 2.8.10-11 
  M 0.8 1.8.10-11 2.7.10-11 0.05 4.1.10-11 
Se-75 119.8 d  F 0.8 1.0.10-9 1.4.10-9 0.8 2.6.10-9 
  M 0.8 1.4.10-9 1.7.10-9 0.05 4.1.10-10 
Se-79 65000 y  F 0.8 1.2.10-9 1.6.10-9 0.8 2.9.10-9 
  M 0.8 2.9.10-9 3.1.10-9 0.05 3.9.10-10 
Se-81 18.5 min  F 0.8 8.6.10-12 1.4.10-11 0.8 2.7.10-11 
  M 0.8 1.5.10-11 2.4.10-11 0.05 2.7.10-11 
Se-81m 57.25 min  F 0.8 1.7.10-11 3.0.10-11 0.8 5.3.10-11 
  M 0.8 4.7.10-11 6.8.10-11 0.05 5.9.10-11 
Se-83 22.5 min  F 0.8 1.9.10-11 3.4.10-11 0.8 4.7.10-11 
  M 0.8 3.3.10-11 5.3.10-11 0.05 5.1.10-11 
bromine         
Br-74 25.3 mi n F 1 2.8.10-11 5.0.10-11 1 8.4.10-11 
  M 1 4.1.10-11 6.8.10-11   
Br-74m 41.5 min  F 1 4.2.10-11 7.5.10-11 1 1.4.10-10 
  M 1 6.5.10-11 1.1.10-10   
Br-75 98 min  F 1 3.1.10-11 5.6.10-11 1 7.9.10-11 
  M 1 5.5.10-11 8.5.10-11   
Br-76 16.2 h  F 1 2.6.10-10 4.5.10-10 1 4.6.10-10 
  M 1 4.2.10-10 5.8.10-10   
Br-77 56 h F 1 6.7.10-11 1.2.10-10 1 9.6.10-11 
  M 1 8.7.10-11 1.3.10-10   
Br-80 17.4 min  F 1 6.3.10-12 1.1.10-11 1 3.1.10-11 
  M 1 1.0.10-11 1.7.10-11   
Br-80m 4.42 h  F 1 3.5.10-11 5.8.10-11 1 1.1.10-10 
  M 1 7.6.10-11 1.0.10-10   
Br-82 35.30 h  F 1 3.7.10-10 6.4.10-10 1 5.4.10-10 
  M 1 6.4.10-10 8.8.10-10   - 102 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Br-83 2.39 h  F 1 1.7.10-11 2.9.10-11 1 4.3.10-11 
  M 1 4.8.10-11 6.7.10-11   
Br-84 31.80 min  F 1 2.3.10-11 4.0.10-11 1 8.8.10-11 
  M 1 3.9.10-11 6.2.10-11   
rubidium         
Rb-79 22.9 min  F 1 1.7.10-11 3.0.10-11 1 5.0.10-11 
Rb-81 4.58 h  F 1 3.7.10-11 6.8.10-11 1 5.4.10-11 
Rb-81m 32 min  F 1 7.3.10-12 1.3.10-11 1 9.7.10-12 
Rb-82m 6.2 h  F 1 1.2.10-10 2.2.10-10 1 1.3.10-10 
Rb-83 86.2 d  F 1 7.1.10-10 1.0.10-9 1 1.9.10-9 
Rb-84 32.77 d  F 1 1.1.10-9 1.5.10-9 1 2.8.10-9 
Rb-86 18.66 d  F 1 9.6.10-10 1.3.10-9 1 2.8.10-9 
Rb-87 4.7 x 1010 y F 1 5.1.10-10 7.6.10-10 1 1.5.10-9 
Rb-88 17.8 min  F 1 1.7.10-11 2.8.10-11 1 9.0.10-11 
Rb-89 15.2 min  F 1 1.4.10-11 2.5.10-11 1 4.7.10-11 
strontium         
Sr-80 100 min  F 0.3 7.6.10-11 1.3.10-10 0.3 3.4.10-10 
  S 0.01 1.4.10-10 2.1.10-10 0.01 3.5.10-10 
Sr-81 25.5 min  F 0.3 2.2.10-11 3.9.10-11 0.3 7.7.10-11 
  S 0.01 3.8.10-11 6.1.10-11 0.01 7.8.10-11 
Sr-82 25.0 d  F 0.3 2.2.10-9 3.3.10-9 0.3 6.1.10-9 
  S 0.01 1.0.10-8 7.7.10-9 0.01 6.0.10-9 
Sr-83 32.4 h  F 0.3 1.7.10-10 3.0.10-10 0.3 4.9.10-10 
  S 0.01 3.4.10-10 4.9.10-10 0.01 5.8.10-10 
Sr-85 64.84 d  F 0.3 3.9.10-10 5.6.10-10 0.3 5.6.10-10 
  S 0.01 7.7.10-10 6.4.10-10 0.01 3.3.10-10 
Sr-85m 69.5 min  F 0.3 3.1.10-12 5.6.10-12 0.3 6.1.10-12 
  S 0.01 4.5.10-12 7.4.10-12 0.01 6.1.10-12 
Sr-87m 2.805 h  F 0.3 1.2.10-11 2.2.10-11 0.3 3.0.10-11 
  S 0.01 2.2.10-11 3.5.10-11 0.01 3.3.10-11 
Sr-89 50.5 d  F 0.3 1.0.10-9 1.4.10-9 0.3 2.6.10-9 
  S 0.01 7.5.10-9 5.6.10-9 0.01 2.3.10-9 
Sr-90 29.12 y  F 0.3 2.4.10-8 3.0.10-8 0.3 2.8.10-8 
  S 0.01 1.5.10-7 7.7.10-8 0.01 2.7.10-9 
Sr-91 9.5 h  F 0.3 1.7.10-10 2.9.10-10 0.3 6.5.10-10 - 103 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 0.01 4.1.10-10 5.7.10-10 0.01 7.6.1 0-10 
Sr-92 2.71 h  F 0.3 1.1.10-10 1.8.10-10 0.3 4.3.10-10 
  S 0.01 2.3.10-10 3.4.10-10 0.01 4.9.10-10 
yttrium         
Y-86 14.74 h  M 1.0.10-4 4.8.10-10 8.0.10-10 1.0.10-4 9.6.10-10 
  S 1.0.10-4 4.9.10-10 8.1.10-10   
Y-86m 48 min  M 1.0.10-4 2.9.10-11 4.8.10-11 1.0.10-4 5.6.10-11 
  S 1.0.10-4 3.0.10-11 4.9.10-11   
Y-87 80.3 h  M 1.0.10-4 3.8.10-10 5.2.10-10 1.0.10-4 5.5.10-10 
  S 1.0.10-4 4.0.10-10 5.3.10-10   
Y-88 106.64 d  M 1.0.10-4 3.9.10-9 3.3.10-9 1.0.10-4 1.3.10-9 
  S 1.0.10-4 4.1.10-9 3.0.10-9   
Y-90 64.0 h  M 1.0.10-4 1.4.10-9 1.6.10-9 1.0.10-4 2.7.10-9 
  S 1.0.10-4 1.5.10-9 1.7.10-9   
Y-90m 3.19 h  M 1.0.10-4 9.6.10-11 1.3.10-10 1.0.10-4 1.7.10-10 
  S 1.0.10-4 1.0.10-10 1.3.10-10   
Y-91 58.51 d  M 1.0.10-4 6.7.10-9 5.2.10-9 1.0.10-4 2.4.10-9 
  S 1.0.10-4 8.4.10-9 6.1.10-9   
Y-91m 49.71 min  M 1.0.10-4 1.0.10-11 1.4.10-11 1.0.10-4 1.1.10-11 
  S 1.0.10-4 1.1.10-11 1.5.10-11   
Y-92 3.54 h  M 1.0.10-4 1.9.10-10 2.7.10-10 1.0.10-4 4.9.10-10 
  S 1.0.10-4 2.0.10-10 2.8.10-10   
Y-93 10.1 h  M 1.0.10-4 4.1.10-10 5.7.10-10 1.0.10-4 1.2.10-9 
  S 1.0.10-4 4.3.10-10 6.0.10-10   
Y-94 19.1 min  M 1.0.10-4 2.8.10-11 4.4.10-11 1.0.10-4 8.1.10-11 
  S 1.0.10-4 2.9.10-11 4.6.10-11   
Y-95 10.7 min  M 1.0.10-4 1.6.10-11 2.5.10-11 1.0.10-4 4.6.10-11 
  S 1.0.1 0-4 1.7.10-11 2.6.10-11   
zirconium         
Zr-86 16.5 h  F 0.002  3.0.10-10 5.2.10-10 0.002  8.6.10-10 
  M 0.002  4.3.10-10 6.8.10-10   
  S 0.002  4.5.10-10 7.0.10-10   
Zr-88 83.4 d  F 0.002  3.5.10-9 4.1.10-9 0.002  3.3.10-10 
  M 0.002  2.5.10-9 1.7.10-9   
  S 0.002  3.3.10-9 1.8.10-9   - 104 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Zr-89 78.43 h  F 0.002  3.1.10-10 5.2.10-10 0.002  7.9.10-10 
  M 0.002  5.3.10-10 7.2.10-10   
  S 0.002  5.5.10-10 7.5.10-10   
Zr-93 1.53 x 106 y F 0.002  2.5.10-8 2.9.10-8 0.002  2.8.10-10 
  M 0.002  9.6.10-9 6.6.10-9   
  S 0.002 3.1.10-9 1.7.10-9   
Zr-95 63.98 d  F 0.002  2.5.10-9 3.0.10-9 0.002  8.8.10-10 
  M 0.002  4.5.10-9 3.6.10-9   
  S 0.002  5.5.10-9 4.2.10-9   
Zr-97 16.90 h  F 0.002  4.2.10-10 7.4.10-10 0.002  2.1.10-9 
  M 0.002  9.4.10-10 1.3.10-9   
  S 0.002  1.0.10-9 1.4.10-9   
niobium         
Nb-88 14.3 min  M 0.01 2.9.10-11 4.8.10-11 0.01 6.3.10-11 
  S 0.01 3.0.10-11 5.0.10-11   
Nb-89 122 min  M 0.01 1.2.10-10 1.8.10-10 0.01 3.0.10-10 
  S 0.01 1.3.10-10 1.9.10-10   
Nb-89m 66 min  M 0.01 7.1.10-11 1.1.10-10 0.01 1.4.10-10 
  S 0.01 7.4.10-11 1.2.10-10   
Nb-90 14.60 h  M 0.01 6.6.10-10 1.0.10-9 0.01 1.2.10-9 
  S 0.01 6.9.10-10 1.1.10-9   
Nb-93m 13.6 y  M 0.01 4.6.10-10 2.9.10-10 0.01 1.2.10-10 
  S 0.01 1.6.10-9 8.6.10-10   
Nb-94 2.03 x 104 y M 0.01 1.0.10-8 7.2.10-9 0.01 1.7.10-9 
  S 0.01 4.5.10-8 2.5.10-8   
Nb-95 35.15 d  M 0.01 1.4.10-9 1.3.10-9 0.01 5.8.10-10 
  S 0.01 1.6.10-9 1.3.10-9   
Nb-95m 86.6 h  M 0.01 7.6.10-10 7.7.10-10 0.01 5.6.10-10 
  S 0.01 8.5.10-10 8.5.10-10   
Nb-96 23.35 h  M 0.01 6.5.10-10 9.7.10-10 0.01 1.1.10-9 
  S 0.01 6.8.10-10 1.0.10-9   
Nb-97 72.1 min  M 0.01 4.4.10-11 6.9.10-11 0.01 6.8.10-11 
  S 0.01 4.7.10-11 7.2.10-11   
Nb-98m 51.5 min  M 0.01 5.9.10-11 9.6.10-11 0.01 1.1.10-10 
  S 0.01 6.1.10-11 9.9.10-11   - 105 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
molybdenum         
Mo-90 5.67 h F 0.8 1.7.10-10 2.9.10-10 0.8 3.1.10-10 
  S 0.05 3.7.10-10 5.6.10-10 0.05 6.2.10-10 
Mo-93 3.5 x 103 y F 0.8 1.0.10-9 1.4.10-9 0.8 2.6.10-9 
  S 0.05 2.2.10-9 1.2.10-9 0.05 2.0.10-10 
Mo-93m 6.85 h  F 0.8 1.0.10-10 1.9.10-10 0.8 1.6.10-10 
  S 0.05 1.8.10-10 3.0.10-10 0.05 2.8.10-10 
Mo-99 66.0 h  F 0.8 2.3.10-10 3.6.10-10 0.8 7.4.10-10 
  S 0.05 9.7.10-10 1.1.10-9 0.05 1.2.10-9 
Mo-101 14.62 min  F 0.8 1.5.10-11 2.7.10-11 0.8 4.2.10-11 
  S 0.05 2.7.10-11 4.5.10-11 0.05 4.2.10-11 
technetium         
Tc-93 2.75 h  F 0.8 3.4.10-11 6.2.10-11 0.8 4.9.10-11 
  M 0.8 3.6.10-11 6.5.10-11   
Tc-93m 43.5 min  F 0.8 1.5.10-11 2.6.10-11 0.8 2.4.10-11 
  M 0.8 1.7.10-11 3.1.10-11   
Tc-94 293 min  F 0.8 1.2.10-10 2.1.10-10 0.8 1.8.10-10 
  M 0.8 1.3.10-10 2.2.10-10   
Tc-94m 52 min  F 0.8 4.3.10-11 6.9.10-11 0.8 1.1.10-10 
  M 0.8 4.9.10-11 8.0.10-11   
Tc-95 20.0 h  F 0.8 1.0.10-10 1.8.10-10 0.8 1.6.10-10 
  M 0.8 1.0.10-10 1.8.10-10   
Tc-95m 61 d F 0.8 3.1.10-10 4.8.10-10 0.8 6.2.10-10 
  M 0.8 8.7.10-10 8.6.10-10   
Tc-96 4.28 d  F 0.8 6.0.10-10 9.8.10-10 0.8 1.1.10-9 
  M 0.8 7.1.10-10 1.0.10-9   
Tc-96m 51.5 min  F 0.8 6.5.10-12 1.1.10-11 0.8 1.3.10-11 
  M 0.8 7.7.10-12 1.1.10-11   
Tc-97 2.6 x 106 y F 0.8 4.5.10-11 7.2.10-11 0.8 8.3.10-11 
  M 0.8 2.1.10-10 1.6.10-10   
Tc-97m 87 d F 0.8 2.8.10-10 4.0.10-10 0.8 6.6.10-10 
  M 0.8 3.1.10-9 2.7.10-9   
Tc-98 4.2 x 106 y F 0.8 1.0.10-9 1.5.10-9 0.8 2.3.10-9 
  M 0.8 8.1.10-9 6.1.10-9   
Tc-99 2.13 x 105 y F 0.8 2.9.10-10 4.0.10-10 0.8 7.8.10-10 - 106 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.8 3.9.10-9 3.2.10-9   
Tc-99m 6.02 h  F 0.8 1.2.10-11 2.0.10-11 0.8 2.2.10-11 
  M 0.8 1.9.10-11 2.9.10-11   
Tc-101 14.2 min  F 0.8 8.7.10-12 1.5.10-11 0.8 1.9.10-11 
  M 0.8 1.3.10-11 2.1.10-11   
Tc-104 18.2 min  F 0.8 2.4.10-11 3.9.10-11 0.8 8.1.10-11 
  M 0.8 3.0.10-11 4.8.10-11   
ruthenium         
Ru-94 51.8 min  F 0.05 2.7.10-11 4.9.10-11 0.05 9.4.10-11 
  M 0.05 4.4.10-11 7.2.10-11   
  S 0.05 4.6.10-11 7.4.10-11   
Ru-97 2.9 d  F 0.05 6.7.10-11 1.2.10-10 0.05 1.5.10-10 
  M 0.05 1.1.10-10 1.6.10-10   
  S 0.05 1.1.10-10 1.6.10-10   
Ru-103 39.28 d  F 0.05 4.9.10-10 6.8.10-10 0.05 7.3.10-10 
  M 0.05 2.3.10-9 1.9.10-9   
  S 0.05 2.8.10-9 2.2.10-9   
Ru-105 4.44 h  F 0.05 7.1.10-11 1.3.10-10 0.05 2.6.10-10 
  M 0.05 1.7.10-10 2.4.10-10   
  S 0.05 1.8.10-10 2.5.10-10   
Ru-106 368.2 d  F 0.05 8.0.10-9 9.8.10-9 0.05 7.0.10-9 
  M 0.05 2.6.10-8 1.7.10-8   
  S 0.05 6.2.10-8 3.5.10-8   
rhodium         
Rh-99 16 d F 0.05 3.3.10-10 4.9.10-10 0.05 5.1.10-10 
  M 0.05 7.3.10-10 8.2.10-10   
  S 0.05 8.3.10-10 8.9.10-10   
Rh-99m 4.7 h F 0.05 3.0.10-11 5.7.10-11 0.05 6.6.10-11 
  M 0.05 4.1.10-11 7.2.10-11   
  S 0.05 4.3.10-11 7.3.10-11   
Rh-100 2.08 h  F 0.05 2.8.10-10 5.1.10-10 0.05 7.1.10-10 
  M 0.05 3.6.10-10 6.2.10-10   
  S 0.05 3.7.10-10 6.3.10-10   
Rh-101 3.2 y  F 0.05 1.4.10-9 1.7.10-9 0.05 5.5.10-10 
  M 0.05 2.2.10-9 1.7.10-9   - 107 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 0.05 5.0.10-9 3.1.10-9   
Rh-101m  4.34 d  F 0.05 1.0.10-10 1.7.10-10 0.05 2.2.10-10 
  M 0.05 2.0.10-10 2.5.10-10   
  S 0.05 2.1.10-10 2.7.10-10   
Rh-102m  2.9 y  F 0.05 7.3.10-9 8.9.10-9 0.05 2.6.10-9 
  M 0.05 6.5.10-9 5.0.10-9   
  S 0.05 1.6.10-8 9.0.10-9   
Rh-102 207 d  F 0.05 1.5.10-9 1.9.10-9 0.05 1.2.10-9 
  M 0.05 3.8.10-9 2.7.10-9   
  S 0.05 6.7.10-9 4.2.10-9   
Rh-103m  56.12 min  F 0.05 8.6.10-13 1.2.10-12 0.05 3.8.10-12 
  M 0.05 2.3.1 0-12 2.4.10-12   
  S 0.05 2.5.10-12 2.5.10-12   
Rh-105 35.36 h  F 0.05 8.7.10-11 1.5.10-10 0.05 3.7.10-10 
  M 0.05 3.1.10-10 4.1.10-10   
  S 0.05 3.4.10-10 4.4.10-10   
Rh-106m  132 min  F 0.05 7.0.10-11 1.3.10-10 0.05 1.6.10-10 
  M 0.05 1.1.10-10 1.8.10-10   
  S 0.05 1.2.10-10 1.9.10-10   
Rh-107 21.7 min  F 0.05 9.6.10-12 1.6.10-11 0.05 2.4.10-11 
  M 0.05 1.7.10-11 2.7.10-11   
  S 0.05 1.7.10-11 2.8.10-11   
palladium         
Pd-100 3.63 d  F 0.005  4.9.10-10 7.6.10-10 0.005  9.4.10-10 
  M 0.005  7.9.10-10 9.5.10-10   
  S 0.005  8.3.10-10 9.7.10-10   
Pd-101 8.27 h  F 0.005  4.2.10-11 7.5.10-11 0.005  9.4.10-11 
  M 0.005  6.2.10-11 9.8.10-11   
  S 0.005  6.4.10-11 1.0.10-10   
Pd-103 16.96 d  F 0.005  9.0.10-11 1.2.10-10 0.005  1.9.10-10 
  M 0.005  3.5.10-10 3.0.10-10   
  S 0.005  4.0.10-10 2.9.10-10   
Pd-107 6.5 x 106 y F 0.005  2.6.10-11 3.3.10-11 0.005  3.7.10-11 
  M 0.005  8.0.10-11 5.2.10-11   
  S 0.005  5.5.10-10 2.9.10-10   - 108 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Pd-109 13.427 h  F 0.005  1.2.10-10 2.1.10-10 0.005  5.5.10-10 
  M 0.005  3.4.10-10 4.7.10-10   
  S 0.005  3.6.10-10 5.0.10-10   
silver         
Ag-102 12.9 min  F 0.05 1.4.10-11 2.4.10-11 0.05 4.0.10-11 
  M 0.05 1.8.10-11 3.2.10-11   
  S 0.05 1.9.10-11 3.2.10-11   
Ag-103 65.7 min  F 0.05 1.6.10-11 2.8.10-11 0.05 4.3.10-11 
  M 0.05 2.7.1 0-11 4.3.10-11   
  S 0.05 2.8.10-11 4.5.10-11   
Ag-104 69.2 min  F 0.05 3.0.10-11 5.7.10-11 0.05 6.0.10-11 
  M 0.05 3.9.10-11 6.9.10-11   
  S 0.05 4.0.10-11 7.1.10-11   
Ag-104m  33.5 min  F 0.05 1.7.10-11 3.1.10-11 0.05 5.4.10-11 
  M 0.05 2.6.10-11 4.4.10-11   
  S 0.05 2.7.10-11 4.5.10-11   
Ag-105 41.0 d  F 0.05 5.4.10-10 8.0.10-10 0.05 4.7.10-10 
  M 0.05 6.9.10-10 7.0.10-10   
  S 0.05 7.8.10-10 7.3.10-10   
Ag-106 23.96 min  F 0.05 9.8.10-12 1.7.10-11 0.05 3.2.10-11 
  M 0.05 1.6.10-11 2.6.10-11   
  S 0.05 1.6.10-11 2.7.10-11   
Ag-106m  8.41 d  F 0.05 1.1.10-9 1.6.10-9 0.05 1.5.10-9 
  M 0.05 1.1.10-9 1.5.10-9   
  S 0.05 1.1.10-9 1.4.10-9   
Ag-108m  127 y  F 0.05 6.1.10-9 7.3.10-9 0.05 2.3.10-9 
  M 0.05 7.0.10-9 5.2.10-9   
  S 0.05 3.5.10-8 1.9.10-8   
Ag-110m  249.9 d  F 0.05 5.5.10-9 6.7.10-9 0.05 2.8.10-9 
  M 0.05 7.2.10-9 5.9.10-9   
  S 0.05 1.2.10-8 7.3.10-9   
Ag-111 7.45 d  F 0.05 4.1.10-10 5.7.10-10 0.05 1.3.10-9 
  M 0.05 1.5.10-9 1.5.10-9   
  S 0.05 1.7.10-9 1.6.10-9   
Ag-112 3.12 h  F 0.05 8.2.10-11 1.4.10-10 0.05 4.3.10-10 - 109 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.05 1.7.10-10 2.5.10-10   
  S 0.05 1.8.10-10 2.6.10-10   
Ag-115 20.0 min  F 0.05 1.6.10-11 2.6.10-11 0.05 6.0.10-11 
  M 0.05 2.8.10-11 4.3.10-11   
  S 0.05 3.0.10-11 4.4.10-11   
cadmium         
Cd-104 57.7 min  F 0.05 2.7.10-11 5.0.10-11 0.05 5.8.10-11 
  M 0.05 3.6.10-11 6.2.10-11   
  S 0.05 3.7.10-11 6.3.10-11   
Cd-107 6.49 h  F 0.05 2.3.10-11 4.2.10-11 0.05 6.2.10-11 
  M 0.05 8.1.10-11 1.0.10-10   
  S 0.05 8.7.10-11 1.1.10-10   
Cd-109 464 d  F 0.05 8.1.10-9 9.6.10-9 0.05 2.0.10-9 
  M 0.05 6.2.10-9 5.1.10-9   
  S 0.05 5.8.10-9 4.4.10-9   
Cd-113 9.3 x 1015 y F 0.05 1.2.10-7 1.4.10-7 0.05 2.5.10-8 
  M 0.05 5.3.10-8 4.3.10-8   
  S 0.05 2.5.10-8 2.1.10-8   
Cd-113m  13.6 y  F 0.05 1.1.10-7 1.3.10-7 0.05 2.3.10-8 
  M 0.05 5.0.10-8 4.0.10-8   
  S 0.05 3.0.10-8 2.4.10-8   
Cd-115 53.46 h  F 0.05 3.7.10-10 5.4.10-10 0.05 1.4.10-9 
  M 0.05 9.7.10-10 1.2.10-9   
  S 0.05 1.1.10-9 1.3.10-9   
Cd-115m  44.6 d  F 0.05 5.3.10-9 6.4.10-9 0.05 3.3.10-9 
  M 0.05 5.9.10-9 5.5.10-9   
  S 0.05 7.3.10-9 5.5.10-9   
Cd-117 2.49 h  F 0.05 7.3.10-11 1.3.10-10 0.05 2.8.10-10 
  M 0.05 1.6.10-10 2.4.10-10   
  S 0.05 1.7.10-10 2.5.10-10   
Cd-117m  3.36 h  F 0.05 1.0.10-10 1.9.10-10 0.05 2.8.10-10 
  M 0.05 2.0.10-10 3.1.10-10   
  S 0.05 2.1.10-10 3.2.10-10   
indium         
In-109 4.2 h  F 0.02 3.2.10-11 5.7.10-11 0.02 6.6.10-11 - 110 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.02 4.4.10-11 7.3.10-11   
In-110 4.9 h  F 0.02 1.2.10-10 2.2.10-10 0.02 2.4.10-10 
  M 0.02 1.4.10-10 2.5.10-10   
In-110m  69.1 min  F 0.02 3.1.10-11 5.5.10-11 0.02 1.0.10-10 
  M 0.02 5.0.10-11 8.1.10-11   
In-111 2.83 d  F 0.02 1.3.10-10 2.2.10-10 0.02 2.9.10-10 
  M 0.02 2.3.10-10 3.1.10-10   
In-112 14.4 min  F 0.02 5.0.10-12 8.6.10-12 0.02 1.0.10-11 
  M 0.02 7.8.10-12 1.3.10-11   
In-113m  1.658 h  F 0.02 1.0.10-11 1.9.10-11 0.02 2.8.10-11 
  M 0.02 2.0.10-11 3.2.10-11   
In-114m  49.51 d  F 0.02 9.3.10-9 1.1.10-8 0.02 4.1.10-9 
  M 0.02 5.9.10-9 5.9.10-9   
In-115 5.1 x 1015 y F 0.02 3.9.10-7 4.5.10-7 0.02 3.2.10-8 
  M 0.02 1.5.10-7 1.1.10-7   
In-115m  4.486 h F 0.02 2.5.10-11 4.5.10-11 0.02 8.6.10-11 
  M 0.02 6.0.10-11 8.7.10-11   
In-116m  54.15 min  F 0.02 3.0.10-11 5.5.10-11 0.02 6.4.10-11 
  M 0.02 4.8.10-11 8.0.10-11   
In-117 43.8 min  F 0.02 1.6.10-11 2.8.10-11 0.02 3.1.10-11 
  M 0.02 3.0.10-11 4.8.1 0-11   
In-117m  116.5 min  F 0.02 3.1.10-11 5.5.10-11 0.02 1.2.10-10 
  M 0.02 7.3.10-11 1.1.10-10   
In-119m  18.0 min  F 0.02 1.1.10-11 1.8.10-11 0.02 4.7.10-11 
  M 0.02 1.8.10-11 2.9.10-11   
tin        
Sn-110 4.0 h  F 0.02 1.1.10-10 1.9.10-10 0.02 3.5.10-10 
  M 0.02 1.6.10-10 2.6.10-10   
Sn-111 35.3 min  F 0.02 8.3.10-12 1.5.10-11 0.02 2.3.10-11 
  M 0.02 1.4.10-11 2.2.10-11   
Sn-113 115.1 d  F 0.02 5.4.10-10 7.9.10-10 0.02 7.3.10-10 
  M 0.02 2.5.10-9 1.9.10-9   
Sn-117m  13.61 d  F 0.02 2.9.10-10 3.9.10-10 0.02 7.1.10-10 
  M 0.02 2.3.10-9 2.2.10-9   
Sn-119m  293.0 d  F 0.02 2.9.10-10 3.6.10-10 0.02 3.4.10-10 - 111 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.02 2.0.10-9 1.5.10-9   
Sn-121 27.06 h  F 0.02 6.4.10-11 1.0.10-10 0.02 2.3.10-10 
  M 0.02 2.2.10-10 2.8.10-10   
Sn-121m  55 y F 0.02 8.0.10-10 9.7.10-10 0.02 3.8.10-10 
  M 0.02 4.2.10-9 3.3.10-9   
Sn-123 129.2 d  F 0.02 1.2.10-9 1.6.10-9 0.02 2.1.10-9 
  M 0.02 7.7.10-9 5.6.10-9   
Sn-123m  40.08 min  F 0.02 1.4.10-11 2.4.10-11 0.02 3.8.10-11 
  M 0.02 2.8.10-11 4.4.10-11   
Sn-125 9.64 d  F 0.02 9.2.10-10 1.3.10-9 0.02 3.1.10-9 
  M 0.02 3.0.10-9 2.8.10-9   
Sn-126 1.0 x 105 y F 0.02 1.1.10-8 1.4.10-8 0.02 4.7.10-9 
  M 0.02 2.7.10-8 1.8.10-8   
Sn-127 2.10 h  F 0.02 6.9.10-11 1.2.10-10 0.02 2.0.10-10 
  M 0.02 1.3.10-10 2.0.10-10   
Sn-128 59.1 m in F 0.02 5.4.10-11 9.5.10-11 0.02 1.5.10-10 
  M 0.02 9.6.10-11 1.5.10-10   
antimony         
Sb-115 31.8 min  F 0.1 9.2.10-12 1.7.10-11 0.1 2.4.10-11 
  M 0.01 1.4.10-11 2.3.10-11   
Sb-116 15.8 min  F 0.1 9.9.10-12 1.8.10-11 0.1 2.6.10-11 
  M 0.01 1.4.10-11 2.3.10-11   
Sb-116m  60.3 min  F 0.1 3.5.10-11 6.4.10-11 0.1 6.7.10-11 
  M 0.01 5.0.10-11 8.5.10-11   
Sb-117 2.80 h  F 0.1 9.3.10-12 1.7.10-11 0.1 1.8.10-11 
  M 0.01 1.7.10-11 2.7.10-11   
Sb-118m  5.00 h  F 0.1 1.0.10-10 1.9.10-10 0.1 2.1.10-10 
  M 0.01 1.3.10-10 2.3.10-10   
Sb-119 38.1 h  F 0.1 2.5.10-11 4.5.10-11 0.1 8.1.10-11 
  M 0.01 3.7.10-11 5.9.10-11   
Sb-120m  5.76 d  F 0.1 5.9.10-10 9.8.10-10 0.1 1.2.10-9 
  M 0.01 1.0.10-9 1.3.10-9   
Sb-120 15.89 min  F 0.1 4.9.10-12 8.5.10-12 0.1 1.4.10-11 
  M 0.01 7.4.10-12 1.2.10-11   
Sb-122 2.70 d  F 0.1 3.9.10-10 6.3.10-10 0.1 1.7.10-9 - 112 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.01 1.0.10-9 1.2.10-9   
Sb-124 60.20 d  F 0.1 1.3.10-9 1.9.10-9 0.1 2.5.10-9 
  M 0.01 6.1.10-9 4.7.10-9   
Sb-124m  20.2 min  F 0.1 3.0.10-12 5.3.10-12 0.1 8.0.10-12 
  M 0.01 5.5.10-12 8.3.10-12   
Sb-125 2.77 y  F 0.1 1.4.10-9 1.7.10-9 0.1 1.1.10-9 
  M 0.01 4.5.10-9 3.3.10-9   
Sb-126 12.4 d  F 0.1 1.1.10-9 1.7.10-9 0.1 2.4.10-9 
  M 0.01 2.7.10-9 3.2.10-9   
Sb-126m  19.0 min  F 0.1 1.3.10-11 2.3.10-11 0.1 3.6.10-11 
  M 0.01 2.0.10-11 3.3.10-11   
Sb-127 3.85 d  F 0.1 4.6.10-10 7.4.10-10 0.1 1.7.10-9 
  M 0.01 1.6.10-9 1.7.10-9   
Sb-128 9.01 h  F 0.1 2.5.10-10 4.6.10-10 0.1 7.6.10-10 
  M 0.01 4.2.10-10 6.7.10-10   
Sb-128m  10.4 min  F 0.1 1.1.10-11 1.9.10-11 0.1 3.3.10-11 
  M 0.01 1.5.10-11 2.6.10-11   
Sb-129 4.32 h  F 0.1 1.1.10-10 2.0.10-10 0.1 4.2.10-10 
  M 0.01 2.4.10-10 3.5.10-10   
Sb-130 40 min  F 0.1 3.5.10-11 6.3.10-11 0.1 9.1.10-11 
  M 0.01 5.4.10-11 9.1.10-11   
Sb-131 23 min  F 0.1 3.7.10-11 5.9.10-11 0.1 1.0.10-10 
  M 0.01 5.2.10-11 8.3.10-11   
tellurium         
Te-116 2.49 h  F 0.3 6.3.10-11 1.2.10-10 0.3 1.7.10-10 
  M 0.3 1.1.10-10 1.7.10-10   
Te-121 17 d F 0.3 2.5.10-10 3.9.10-10 0.3 4.3.10-10 
  M 0.3 3.9.10-10 4.4.10-10   
Te-121m  154 d  F 0.3 1.8.10-9 2.3.10-9 0.3 2.3.10-9 
  M 0.3 4.2.10-9 3.6.10-9   
Te-123 1 x 1013 y F 0.3 4.0.10-9 5.0.10-9 0.3 4.4.10-9 
  M 0.3 2.6.10-9 2.8.10-9   
Te-123m  119.7 d  F 0.3 9.7.10-10 1.2.10-9 0.3 1.4.10-9 
  M 0.3 3.9.10-9 3.4.10-9   
Te-125m  58 d F 0.3 5.1.10-10 6.7.10-10 0.3 8.7.10-10 - 113 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.3 3.3.10-9 2.9.10-9   
Te-127 9.35 h  F 0.3 4.2.10-11 7.2.10-11 0.3 1.7.10-10 
  M 0.3 1.2.10-10 1.8.10-10   
Te-127m  109 d  F 0.3 1.6.10-9 2.0.10-9 0.3 2.3.10-9 
  M 0.3 7.2.10-9 6.2.10-9   
Te-129 69.6 min  F 0.3 1.7.10-11 2.9.10-11 0.3 6.3.10-11 
  M 0.3 3.8.10-11 5.7.10-11   
Te-129m  33.6 d  F 0.3 1.3.10-9 1.8.10-9 0.3 3.0.10-9 
  M 0.3 6.3.10-9 5.4.10-9   
Te-131 25.0 min  F 0.3 2.3.10-11 4.6.10-11 0.3 8.7.10-11 
  M 0.3 3.8.10-11 6.1.10-11   
Te-131m  30 h F 0.3 8.7.10-10 1.2.10-9 0.3 1.9.10-9 
  M 0.3 1.1.10-9 1.6.10-9   
Te-132 78.2 h  F 0.3 1.8.10-9 2.4.10-9 0.3 3.7.10-9 
  M 0.3 2.2.10-9 3.0.10-9   
Te-133 12.45 min  F 0.3 2.0.10-11 3.8.10-11 0.3 7.2.10-11 
  M 0.3 2.7.10-11 4.4.10-11   
Te-133m  55.4 min  F 0.3 8.4.10-11 1.2.10-10 0.3 2.8.10-10 
  M 0.3 1.2.10-10 1.9.10-10   
Te-134 41.8 min  F 0.3 5.0.10-11 8.3.10-11 0.3 1.1.10-10 
  M 0.3 7.1.10-11 1.1.10-10   
iodine         
I-120 81.0 min  F 1 1.0.10-10 1.9.10-10 1 3.4.10-10 
I-120m  53 min  F 1 8.7.10-11 1.4.10-10 1 2.1.10-10 
I-121 2.12 h  F 1 2.8.10-11 3.9.10-11 1 8.2.10-11 
I-123 13.2 h  F 1 7.6.10-11 1.1.10-10 1 2.1.10-10 
I-124 4.18 d  F 1 4.5.10-9 6.3.10-9 1 1.3.10-8 
I-125 60.14 d  F 1 5.3.10-9 7.3.10-9 1 1.5.10-8 
I-126 13.02 d  F 1 1.0.10-8 1.4.10-8 1 2.9.10-8 
I-128 24.99 min  F 1 1.4.10-11 2.2.10-11 1 4.6.10-11 
I-129 1.57 x 107 y F 1 3.7.10-8 5.1.10-8 1 1.1.10-7 
I-130 12.36 h  F 1 6.9.10-10 9.6.10-10 1 2.0.10-9 
I-131 8.04 d  F 1 7.6.10-9 1.1.10-8 1 2.2.10-8 
I-132 2.30 h  F 1 9.6.10-11 2.0.10-10 1 2.9.10-10 
I-132m  83.6 min  F 1 8.1.10-11 1.1.10-10 1 2.2.10-10 - 114 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
I-133 2.08 h  F 1 1.5.10-9 2.1.10-9 1 4.3.10-9 
I-134 52.6 min  F 1 4.8.10-11 7.9.10-11 1 1.1.10-10 
I-135 6.61 h  F 1 3.3.10-10 4.6.10-10 1 9.3.10-10 
caesium         
Cs-125 45 min  F 1 1.3.10-11 2.3.10-11 1 3.5.10-11 
Cs-127 6.25 h  F 1 2.2.10-11 4.0.10-11 1 2.4.10-11 
Cs-129 32.06 h  F 1 4.5.10-11 8.1.10-11 1 6.0.10-11 
Cs-130 29.9 min  F 1 8.4.10-12 1.5.10-11 1 2.8.10-11 
Cs-131 9.69 d  F 1 2.8.10-11 4.5.10-11 1 5.8.10-11 
Cs-132 6.475 d  F 1 2.4.10-10 3.8.10-10 1 5.0.10-10 
Cs-134 2.062 y  F 1 6.8.10-9 9.6.10-9 1 1.9.10-8 
Cs-134m  2.90 h  F 1 1.5.10-11 2.6.10-11 1 2.0.10-11 
Cs-135 2.3 x 10 6 y F 1 7.1.10-10 9.9.10-10 1 2.0.10-9 
Cs-135m  53 min  F 1 1.3.10-11 2.4.10-11 1 1.9.10-11 
Cs-136 13.1 d  F 1 1.3.10-9 1.9.10-9 1 3.0.10-9 
Cs-137 30.0 y  F 1 4.8.10-9 6.7.10-9 1 1.3.10-8 
Cs-138 32.2 min  F 1 2.6.10-11 4.6.10-11 1 9.2.10-11 
barium         
Ba-126 96.5 min  F 0.1 7.8.10-11 1.2.10-10 0.1 2.6.10-10 
Ba-128 2.43 d  F 0.1 8.0.10-10 1.3.10-9 0.1 2.7.10-9 
Ba-131 11.8 d  F 0.1 2.3.10-10 3.5.10-10 0.1 4.5.10-10 
Ba-131m  14.6 min  F 0.1 4.1.10-12 6.4.10-12 0.1 4.9.10-12 
Ba-133 10.74 y  F 0.1 1.5.10-9 1.8.10-9 0.1 1.0.10-9 
Ba-133m  38.9 h  F 0.1 1.9.10-10 2.8.10-10 0.1 5.5.10-10 
Ba-135m  28.7 h  F 0.1 1.5.10-10 2.3.10-10 0.1 4.5.10-10 
Ba-139 82.7 min  F 0.1 3.5.10-11 5.5.10-11 0.1 1.2.10-10 
Ba-140 12.74 d  F 0.1 1.0.10-9 1.6.10-9 0.1 2.5.10-9 
Ba-141 18.27 min  F 0.1 2.2.10-11 3.5.10-11 0.1 7.0.10-11 
Ba-142 10.6 min  F 0.1 1.6.10-11 2.7.10-11 0.1 3.5.10-11 
lanthanum         
La-131 59 min  F 5.0.10-4 1.4.10-11 2.4.10-11 5.0.10-4 3.5.10-11 
  M 5.0.10-4 2.3.10-11 3.6.10-11   
La-132 4.8 h  F 5.0.10-4 1.1.10-10 2.0.10-10 5.0.10-4 3.9.10-10 
  M 5.0.10-4 1.7.10-10 2.8.10-10   
La-135 19.5 h  F 5.0.10-4 1.1.10-11 2.0.10-11 5.0.10-4 3.0.10-11 - 115 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 5.0.10-4 1.5.10-11 2.5.10-11   
La-137 6 x 104 y F 5.0.10-4 8.6.10-9 1.0.10-8 5.0.10-4 8.1.10-11 
  M 5.0.10-4 3.4.10-9 2.3.10-9   
La-138 1.35 x 1011 y F 5.0.10-4 1.5.10-7 1.8.10-7 5.0.10-4 1.1.10-9 
  M 5.0.10-4 6.1.10-8 4.2.10-8   
La-140 40.272 h  F 5.0.10-4 6.0.10-10 1.0.10-9 5.0.10-4 2.0.10-9 
  M 5.0.10-4 1.1.10-9 1.5.10-9   
La-141 3.93 h  F 5.0.10-4 6.7.10-11 1.1.10-10 5.0.10-4 3.6.10-10 
  M 5.0.10-4 1.5.10-10 2.2.10-10   
La-142 92.5 min  F 5.0.10-4 5.6.10-11 1.0.10-10 5.0.10-4 1.8.10-10 
  M 5.0.10-4 9.3.10-11 1.5.10-10   
La-143 14.23 min  F 5.0.10-4 1.2.10-11 2.0.10-11 5.0.10-4 5.6.10-11 
  M 5.0.10-4 2.2.10-11 3.3.10-11   
cerium         
Ce-134 72.0 h  M 5.0.10-4 1.3.10-9 1.5.10-9 5.0.10-4 2.5.10-9 
  S 5.0.10-4 1.3.10-9 1.6.10-9   
Ce-135 17.6 h  M 5.0.10-4 4.9.10-10 7.3.10-10 5.0.10-4 7.9.10-10 
  S 5.0.10-4 5.1.10-10 7.6.10-10   
Ce-137 9.0 h  M 5.0.10-4 1.0.10-11 1.8.10-11 5.0.10-4 2.5.10-11 
  S 5.0.10-4 1.1.10-11 1.9.10-11   
Ce-137m  34.4 h  M 5.0.10-4 4.0.10-10 5.5.10-10 5.0.10-4 5.4.10-10 
  S 5.0.10-4 4.3.10-10 5.9.10-10   
Ce-139 137.66 d  M 5.0.10-4 1.6.10-9 1.3.10-9 5.0.10-4 2.6.10-10 
  S 5.0.10-4 1.8.10-9 1.4.10-9   
Ce-141 32.501 d  M 5.0.10-4 3.1.10-9 2.7.10-9 5.0.10-4 7.1.10-10 
  S 5.0.10-4 3.6.10-9 3.1.10-9   
Ce-143 33.0 h  M 5.0.10-4 7.4.10-10 9.5.10-10 5.0.10-4 1.1.10-9 
  S 5.0.10-4 8.1.10-10 1.0.10-9   
Ce-144 284.3 d  M 5.0.10-4 3.4.10-8 2.3.10-8 5.0.10-4 5.2.10-9 
  S 5.0.10-4 4.9.10-8 2.9.10-8   
praseodymiu
m        
Pr-136 13.1 min  M 5.0.10-4 1.4.10-11 2.4.10-11 5.0.10-4 3.3.10-11 
  S 5.0.10-4 1.5.10-11 2.5.10-11   
Pr-137 76.6 min  M 5.0.10-4 2.1.10-11 3.4.10-11 5.0.10-4 4.0.10-11 
  S 5.0.10-4 2.2.10-11 3.5.10-11   - 116 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Pr-138m  2.1 h  M 5.0.10-4 7.6.10-11 1.3.10-10 5.0.10-4 1.3.10-10 
  S 5.0.10-4 7.9.10-11 1.3.10-10   
Pr-139 4.51 h  M 5.0.10-4 1.9.10-11 2.9.10-11 5.0.10-4 3.1.10-11 
  S 5.0.10-4 2.0.10-11 3.0.10-11   
Pr-142 19.13 h  M 5.0.10-4 5.3.10-10 7.0.10-10 5.0.10-4 1.3.10-9 
  S 5.0.10-4 5.6.10-10 7.4.10-10   
Pr-142m  14.6 min  M 5.0.10-4 6.7.10-12 8.9.10-12 5.0.10-4 1.7.10-11 
  S 5.0.1 0-4 7.1.10-12 9.4.10-12   
Pr-143 13.56 d  M 5.0.10-4 2.1.10-9 1.9.10-9 5.0.10-4 1.2.10-9 
  S 5.0.10-4 2.3.10-9 2.2.10-9   
Pr-144 17.28 min  M 5.0.10-4 1.8.10-11 2.9.10-11 5.0.10-4 5.0.10-11 
  S 5.0.10-4 1.9.10-11 3.0.10-11   
Pr-145 5.98 h  M 5.0.10-4 1.6.10-10 2.5.10-10 5.0.10-4 3.9.10-10 
  S 5.0.10-4 1.7.10-10 2.6.10-10   
Pr-147 13.6 min  M 5.0.10-4 1.8.10-11 2.9.10-11 5.0.10-4 3.3.10-11 
  S 5.0.10-4 1.9.10-11 3.0.10-11   
neodymium         
Nd-136 50.65 min  M 5.0.10-4 5.3.10-11 8.5.10-11 5.0.10-4 9.9.1 0-11 
  S 5.0.10-4 5.6.10-11 8.9.10-11   
Nd-138 5.04 h  M 5.0.10-4 2.4.10-10 3.7.10-10 5.0.10-4 6.4.10-10 
  S 5.0.10-4 2.6.10-10 3.8.10-10   
Nd-139 29.7 min  M 5.0.10-4 1.0.10-11 1.7.10-11 5.0.10-4 2.0.10-11 
  S 5.0.10-4 1.1.10-11 1.7.10-11   
Nd-139m  5.5 h M 5.0.10-4 1.5.10-10 2.5.10-10 5.0.10-4 2.5.10-10 
  S 5.0.10-4 1.6.10-10 2.5.10-10   
Nd-141 2.49 h  M 5.0.10-4 5.1.10-12 8.5.10-12 5.0.10-4 8.3.10-12 
  S 5.0.10-4 5.3.10-12 8.8.10-12   
Nd-147 10.98 d  M 5.0.10-4 2.0.10-9 1.9.10-9 5.0.10-4 1.1.10-9 
  S 5.0.10-4 2.3.10-9 2.1.10-9   
Nd-149 1.73 h  M 5.0.10-4 8.5.10-11 1.2.10-10 5.0.10-4 1.2.10-10 
  S 5.0.10-4 9.0.10-11 1.3.10-10   
Nd-151 12.44 min  M 5.0.10-4 1.7.10-11 2.8.10-11 5.0.10-4 3.0.10-11 
  S 5.0.10-4 1.8.10-11 2.9.10-11   
promethium         
Pm-141 20.90 min  M 5.0.10-4 1.5.10-11 2.4.10-11 5.0.10-4 3.6.10-11 - 117 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 5.0.10-4 1.6.10-11 2.5.10-11   
Pm-143 265 d  M 5.0.10-4 1.4.10-9 9.6.10-10 5.0.10-4 2.3.10-10 
  S 5.0.10-4 1.3.10-9 8.3.10-10   
Pm-144 363 d  M 5.0.10-4 7.8.10-9 5.4.10-9 5.0.10-4 9.7.10-10 
  S 5.0.10-4 7.0.10-9 3.9.10-9   
Pm-145 17.7 y  M 5.0.10-4 3.4.10-9 2.4.10-9 5.0.10-4 1.1.10-10 
  S 5.0.10-4 2.1.10-9 1.2.10-9   
Pm-146 2020 d  M 5.0.10-4 1.9.10-8 1.3.10-8 5.0.10-4 9.0.10-10 
  S 5.0.10-4 1.6.10-8 9.0.10-9   
Pm-147 2.6234 y  M 5.0.10-4 4.7.10-9 3.5.10-9 5.0.10-4 2.6.10-10 
  S 5.0.10-4 4.6.10-9 3.2.10-9   
Pm-148 5.37 d  M 5.0.10-4 2.0.10-9 2.1.10-9 5.0.10-4 2.7.10-9 
  S 5.0.10-4 2.1.10-9 2.2.10-9   
Pm-148m  41.3 d  M 5.0.10-4 4.9.10-9 4.1.10-9 5.0.10-4 1.8.10-9 
  S 5.0.10-4 5.4.10-9 4.3.10-9   
Pm-149 53.08 h  M 5.0.10-4 6.6.10-10 7.6.10-10 5.0.10-4 9.9.10-10 
  S 5.0.10-4 7.2.10-10 8.2.10-10   
Pm-150 2.68 h  M 5.0.10-4 1.3.10-10 2.0.10-10 5.0.10-4 2.6.10-10 
  S 5.0.10-4 1.4.10-10 2.1.10-10   
Pm-151 28.40 h  M 5.0.10-4 4.2.10-10 6.1.10-10 5.0.10-4 7.3.10-10 
  S 5.0.10-4 4.5.10-10 6.4.10-10   
samarium         
Sm-141 10.2 min  M 5.0.10-4 1.6.10-11 2.7.10-11 5.0.10-4 3.9.10-11 
Sm-141m  22.6 min  M 5.0.10-4 3.4.10-11 5.6.10-11 5.0.10-4 6.5.10-11 
Sm-142 72.49 min  M 5.0.10-4 7.4.10-11 1.1.10-10 5.0.10-4 1.9.10-10 
Sm-145 340 d  M 5.0.10-4 1.5.10-9 1.1.10-9 5.0.10-4 2.1.10-10 
Sm-146 1.03 x 108 y M 5.0.10-4 9.9.10-6 6.7.10-6 5.0.10-4 5.4.10-8 
Sm-147 1.06 x 1011 y M 5.0.10-4 8.9.10-6 6.1.10-6 5.0.10-4 4.9.10-8 
Sm-151 90 y M 5.0.10-4 3.7.10-9 2.6.10-9 5.0.10-4 9.8.10-11 
Sm-153 46.7 h  M 5.0.10-4 6.1.10-10 6.8.10-10 5.0.10-4 7.4.10-10 
Sm-155 22.1 min  M 5.0.10-4 1.7.10-11 2.8.10-11 5.0.10-4 2.9.10-11 
Sm-156 9.4 h  M 5.0.10-4 2.1.10-10 2.8.10-10 5.0.10-4 2.5.10-10 
europium         
Eu-145 5.94 d M 5.0.10-4 5.6.10-10 7.3.10-10 5.0.10-4 7.5.10-10 
Eu-146 4.61 d  M 5.0.10-4 8.2.10-10 1.2.10-9 5.0.10-4 1.3.10-9 - 118 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Eu-147 24 d M 5.0.10-4 1.0.10-9 1.0.10-9 5.0.10-4 4.4.10-10 
Eu-148 54.5 d  M 5.0.10-4 2.7.10-9 2.3.10-9 5.0.10-4 1.3.10-9 
Eu-149 93.1 d  M 5.0.10-4 2.7.10-10 2.3.10-10 5.0.10-4 1.0.10-10 
Eu-150 34.2 y  M 5.0.10-4 5.0.10-8 3.4.10-8 5.0.10-4 1.3.10-9 
Eu-150m  12.62 h  M 5.0.10-4 1.9.10-10 2.8.10-10 5.0.10-4 3.8.10-10 
Eu-152 13.33 y  M 5.0.10-4 3.9.10-8 2.7.10-8 5.0.10-4 1.4.10-9 
Eu-152m  9.32 h M 5.0.10-4 2.2.10-10 3.2.10-10 5.0.10-4 5.0.10-10 
Eu-154 8.8 y  M 5.0.10-4 5.0.10-8 3.5.10-8 5.0.10-4 2.0.10-9 
Eu-155 4.96 y  M 5.0.10-4 6.5.10-9 4.7.10-9 5.0.10-4 3.2.10-10 
Eu-156 15.19 d  M 5.0.10-4 3.3.10-9 3.0.10-9 5.0.10-4 2.2.10-9 
Eu-157 15.15 h  M 5.0.10-4 3.2.10-10 4.4.10-10 5.0.10-4 6.0.10-10 
Eu-158 45.9 min  M 5.0.10-4 4.8.10-11 7.5.10-11 5.0.10-4 9.4.10-11 
gadolinium         
Gd-145 22.9 min  F 5.0.10-4 1.5.10-11 2.6.10-11 5.0.10-4 4.4.10-11 
  M 5.0.10-4 2.1.10-11 3.5.10-11   
Gd-146 48.3 d  F 5.0.10-4 4.4.10-9 5.2.10-9 5.0.10-4 9.6.10-10 
  M 5.0.10-4 6.0.10-9 4.6.10-9   
Gd-147 38.1 h  F 5.0.10-4 2.7.10-10 4.5.10-10 5.0.10-4 6.1.10-10 
  M 5.0.10-4 4.1.10-10 5.9.10-10   
Gd-148 93 y F 5.0.10-4 2.5.10-5 3.0.10-5 5.0.10-4 5.5.10-8 
  M 5.0.10-4 1.1.10-5 7.2.10-6   
Gd-149 9.4 d  F 5.0.10-4 2.6.10-10 4.5.10-10 5.0.10-4 4.5.10-10 
  M 5.0.10-4 7.0.10-10 7.9.10-10   
Gd-151 120 d  F 5.0.10-4 7.8.10-10 9.3.10-10 5.0.10-4 2.0.10-10 
  M 5.0.10-4 8.1.10-10 6.5.10-10   
Gd-152 1.08 x 1014 y F 5.0.10-4 1.9.1 0-5 2.2.10-5 5.0.10-4 4.1.10-8 
  M 5.0.10-4 7.4.10-6 5.0.10-6   
Gd-153 242 d  F 5.0.10-4 2.1.10-9 2.5.10-9 5.0.10-4 2.7.10-10 
  M 5.0.10-4 1.9.10-9 1.4.10-9   
Gd-159 18.56 h  F 5.0.10-4 1.1.10-10 1.8.10-10 5.0.10-4 4.9.10-10 
  M 5.0.10-4 2.7.10-10 3.9.1 0-10   
terbium         
Tb-147 1.65 h  M 5.0.10-4 7.9.10-11 1.2.10-10 5.0.10-4 1.6.10-10 
Tb-149 4.15 h  M 5.0.10-4 4.3.10-9 3.1.10-9 5.0.10-4 2.5.10-10 
Tb-150 3.27 h  M 5.0.10-4 1.1.10-10 1.8.10-10 5.0.10-4 2.5.10-10 - 119 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Tb-151 17.6 h  M 5.0.10-4 2.3.10-10 3.3.10-10 5.0.10-4 3.4.10-10 
Tb-153 2.34 d  M 5.0.10-4 2.0.10-10 2.4.10-10 5.0.10-4 2.5.10-10 
Tb-154 21.4 h  M 5.0.10-4 3.8.10-10 6.0.10-10 5.0.10-4 6.5.10-10 
Tb-155 5.32 d  M 5.0.10-4 2.1.10-10 2.5.10-10 5.0.10-4 2.1.10-10 
Tb-156 5.34 d  M 5.0.10-4 1.2.10-9 1.4.10-9 5.0.10-4 1.2.10-9 
Tb-156m’  5.0 h  M 5.0.10-4 9.2.10-11 1.3.10-10 5.0.10-4 8.1.10-11 
Tb-156m  24.4 h  M 5.0.10-4 2.0.10-10 2.3.10-10 5.0.10-4 1.7.10-10 
Tb-157 150 y  M 5.0.10-4 1.1.10-9 7.9.10-10 5.0.10-4 3.4.10-11 
Tb-158 150 y  M 5.0.10-4 4.3.10-8 3.0.10-8 5.0.10-4 1.1.10-9 
Tb-160 72.3 d  M 5.0.10-4 6.6.10-9 5.4.10-9 5.0.10-4 1.6.10-9 
Tb-161 6.91 d  M 5.0.10-4 1.2.10-9 1.2.10-9 5.0.10-4 7.2.10-10 
dysprosium         
Dy-155 10.0 h  M 5.0.10-4 8.0.10-11 1.2.10-10 5.0.10-4 1.3.10-10 
Dy-157 8.1 h  M 5.0.1 0-4 3.2.10-11 5.5.10-11 5.0.10-4 6.1.10-11 
Dy-159 144.4 d  M 5.0.10-4 3.5.10-10 2.5.10-10 5.0.10-4 1.0.10-10 
Dy-165 2.334 h  M 5.0.10-4 6.1.10-11 8.7.10-11 5.0.10-4 1.1.10-10 
Dy-166 81.6 h  M 5.0.10-4 1.8.10-9 1.8.10-9 5.0.10-4 1.6.10-9 
holmium         
Ho-155 48 min  M 5.0.10-4 2.0.10-11 3.2.10-11 5.0.10-4 3.7.10-11 
Ho-157 12.6 min  M 5.0.10-4 4.5.10-12 7.6.10-12 5.0.10-4 6.5.10-12 
Ho-159 33 min  M 5.0.10-4 6.3.10-12 1.0.10-11 5.0.10-4 7.9.10-12 
Ho-161 2.5 h  M 5.0.10-4 6.3.10-12 1.0.10-11 5.0.10-4 1.3.10-11 
Ho-162 15 min  M 5.0.10-4 2.9.10-12 4.5.10-12 5.0.10-4 3.3.10-12 
Ho-162m  68 min  M 5.0.10-4 2.2.10-11 3.3.10-11 5.0.10-4 2.6.10-11 
Ho-164 29 min  M 5.0.10-4 8.6.10-12 1.3.10-11 5.0.10-4 9.5.10-12 
Ho-164m  37.5 min  M 5.0.10-4 1.2.10-11 1.6.10-11 5.0.10-4 1.6.10-11 
Ho-166 26.80 h  M 5.0.10-4 6.6.10-10 8.3.10-10 5.0.10-4 1.4.10-9 
Ho-166m  1.20 x 103 y M 5.0.10-4 1.1.10-7 7.8.10-8 5.0.10-4 2.0.10-9 
Ho-167 3.1 h  M 5.0.10-4 7.1.10-11 1.0.10-10 5.0.10-4 8.3.10-11 
erbium         
Er-161 3.24 h  M 5.0.10-4 5.1.10-11 8.5.10-11 5.0.10-4 8.0.10-11 
Er-165 10.36 h  M 5.0.10-4 8.3.10-12 1.4.10-11 5.0.10-4 1.9.10-11 
Er-169 9.3 d  M 5.0.10-4 9.8.10-10 9.2.10-10 5.0.10-4 3.7.10-10 
Er-171 7.52 h  M 5.0.10-4 2.2.10-10 3.0.10-10 5.0.10-4 3.6.10-10 
Er-172 49.3 h  M 5.0.10-4 1.1.10-9 1.2.10-9 5.0.10-4 1.0.10-9 - 120 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
thulium         
Tm-162 21.7 min  M 5.0.10-4 1.6.10-11 2.7.10-11 5.0.10-4 2.9.10-11 
Tm-166 7.70 h  M 5.0.10-4 1.8.10-10 2.8.10-10 5.0.10-4 2.8.10-10 
Tm-167 9.24 d  M 5.0.10-4 1.1.10-9 1.0.10-9 5.0.10-4 5.6.10-10 
Tm-170 128.6 d M 5.0.10-4 6.6.10-9 5.2.10-9 5.0.10-4 1.3.10-9 
Tm-171 1.92 y  M 5.0.10-4 1.3.10-9 9.1.10-10 5.0.10-4 1.1.10-10 
Tm-172 63.6 h  M 5.0.10-4 1.1.10-9 1.4.10-9 5.0.10-4 1.7.10-9 
Tm-173 8.24 h  M 5.0.10-4 1.8.10-10 2.6.10-10 5.0.10-4 3.1.10-10 
Tm-175 15.2 m in M 5.0.10-4 1.9.10-11 3.1.10-11 5.0.10-4 2.7.10-11 
ytterbium         
Yb-162 18.9 min  M 5.0.10-4 1.4.10-11 2.2.10-11 5.0.10-4 2.3.10-11 
  S 5.0.10-4 1.4.10-11 2.3.10-11   
Yb-166 56.7 h  M 5.0.10-4 7.2.10-10 9.1.10-10 5.0.10-4 9.5.10-10 
  S 5.0.10-4 7.6.10-10 9.5.10-10   
Yb-167 17.5 min  M 5.0.10-4 6.5.10-12 9.0.10-12 5.0.10-4 6.7.10-12 
  S 5.0.10-4 6.9.10-12 9.5.10-12   
Yb-169 32.01 d  M 5.0.10-4 2.4.10-9 2.1.10-9 5.0.10-4 7.1.10-10 
  S 5.0.10-4 2.8.10-9 2.4.10-9   
Yb-175 4.19 d  M 5.0.10-4 6.3.10-10 6.4.10-10 5.0.10-4 4.4.10-10 
  S 5.0.10-4 7.0.10-10 7.0.10-10   
Yb-177 1.9 h  M 5.0.10-4 6.4.10-11 8.8.10-11 5.0.10-4 9.7.10-11 
  S 5.0.10-4 6.9.10-11 9.4.10-11   
Yb-178 74 min  M 5.0.10-4 7.1.10-11 1.0.10-10 5.0.10-4 1.2.10-10 
  S 5.0.10-4 7.6.10-11 1.1.10-10   
lutetium         
Lu-169 34.06 h  M 5.0.10-4 3.5.10-10 4.7.10-10 5.0.10-4 4.6.10-10 
  S 5.0.10-4 3.8.10-10 4.9.10-10   
Lu-170 2.00 d  M 5.0.10-4 6.4.10-10 9.3.10-10 5.0.10-4 9.9.10-10 
  S 5.0.10-4 6.7.10-10 9.5.10-10   
Lu-171 8.22 d  M 5.0.10-4 7.6.10-10 8.8.10-10 5.0.10-4 6.7.10-10 
  S 5.0.10-4 8.3.10-10 9.3.10-10   
Lu-172 6.70 d  M 5.0.10-4 1.4.10-9 1.7.10-9 5.0.10-4 1.3.10-9 
  S 5.0.10-4 1.5.10-9 1.8.10-9   
Lu-173 1.37 y  M 5.0.10-4 2.0.10-9 1.5.10-9 5.0.10-4 2.6.10-10 
  S 5.0.10-4 2.3.10-9 1.4.10-9   - 121 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Lu-174 3.31 y  M 5.0.10-4 4.0.10-9 2.9.10-9 5.0.10-4 2.7.10-10 
  S 5.0.10-4 3.9.10-9 2.5.10-9   
Lu-174m  142 d  M 5.0.10-4 3.4.10-9 2.4.10-9 5.0.10-4 5.3.10-10 
  S 5.0.10-4 3.8.10-9 2.6.10-9   
Lu-176 3.60 x 1010 y M 5.0.10-4 6.6.10-8 4.6.10-8 5.0.10-4 1.8.10-9 
  S 5.0.10-4 5.2.10-8 3.0.10-8   
Lu-176m  3.68 h  M 5.0.10-4 1.1.10-10 1.5.10-10 5.0.10-4 1.7.10-10 
  S 5.0.10-4 1.2.10-10 1.6.10-10   
Lu-177 6.71 d  M 5.0.10-4 1.0.10-9 1.0.10-9 5.0.10-4 5.3.10-10 
  S 5.0.10-4 1.1.10-9 1.1.10-9   
Lu-177m  160,9 d  M 5.0.10-4 1.2.10-8 1.0.10-8 5.0.10-4 1.7.10-9 
  S 5.0.10-4 1.5.10-8 1.2.10-8   
Lu-178 28.4 min  M 5.0.10-4 2.5.10-11 3.9.10-11 5.0.10-4 4.7.10-11 
  S 5.0.10-4 2.6.10-11 4.1.10-11   
Lu-178m  22.7 min  M 5.0.10-4 3.3.10-11 5.4.10-11 5.0.10-4 3.8.10-11 
  S 5.0.10-4 3.5.10-11 5.6.10-11   
Lu-179 4.59 h  M 5.0.10-4 1.1.10-10 1.6.10-10 5.0.10-4 2.1.10-10 
  S 5.0.10-4 1.2.10-10 1.6.10-10   
hafnium         
Hf-170 16.01 h  F 0.002  1.7.10-10 2.9.10-10 0.002  4.8.10-10 
  M 0.002  3.2.10-10 4.3.10-10   
Hf-172 1.87 y  F 0.002  3.2.10-8 3.7.10-8 0.002  1.0.10-9 
  M 0.002  1.9.10-8 1.3.10-8   
Hf-173 24.0 h  F 0.002  7.9.10-11 1.3.10-10 0.002  2.3.10-10 
  M 0.002  1.6.10-10 2.2.10-10   
Hf-175 70 d F 0.002  7.2.10-10 8.7.10-10 0.002  4.1.10-10 
  M 0.002  1.1.10-9 8.8.10-10   
Hf-177m  51.4 min  F 0.002  4.7.10-11 8.4.10-11 0.002  8.1.10-11 
  M 0.002  9.2.10-11 1.5.10-10   
Hf-178m  31 y F 0.002  2.6.10-7 3.1.10-7 0.002  4.7.10-9 
  M 0.002  1.1.10-7 7.8.10-8   
Hf-179m  25.1 d  F 0.002  1.1.10-9 1.4.10-9 0.002  1.2.10-9 
  M 0.002 3.6.10-9 3.2.10-9   
Hf-180m  5.5 h  F 0.002  6.4.10-11 1.2.10-10 0.002  1.7.10-10 
  M 0.002  1.4.10-10 2.0.10-10   - 122 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Hf-181 42.4 d  F 0.002  1.4.10-9 1.8.10-9 0.002  1.1.10-9 
  M 0.002  4.7.10-9 4.1.10-9   
Hf-182 9 x 106 y F 0.002  3.0.10-7 3.6.10-7 0.002  3.0.10-9 
  M 0.002  1.2.10-7 8.3.10-8   
Hf-182m  61.5 min  F 0.002  2.3.10-11 4.0.10-11 0.002  4.2.10-11 
  M 0.002  4.7.10-11 7.1.10-11   
Hf-183 64 min  F 0.002  2.6.10-11 4.4.10-11 0.002  7.3.10-11 
  M 0.002  5.8.10-11 8.3.10-11   
Hf-184 4.12 h  F 0.002  1.3.10-10 2.3.10-10 0.002  5.2.10-10 
  M 0.002  3.3.10-10 4.5.10-10   
tantalum         
Ta-172 36.8 min  M 0.001  3.4.10-11 5.5.10-11 0.001  5.3.10-11 
  S 0.001  3.6.10-11 5.7.10-11   
Ta-173 3.65 h  M 0.001  1.1.10-10 1.6.10-10 0.001  1.9.10-10 
  S 0.001  1.2.10-10 1.6.1 0-10   
Ta-174 1.2 h  M 0.001  4.2.10-11 6.3.10-11 0.001  5.7.10-11 
  S 0.001  4.4.10-11 6.6.10-11   
Ta-175 10,5 h  M 0.001  1.3.10-10 2.0.10-10 0.001  2.1.10-10 
  S 0.001  1.4.10-10 2.0.10-10   
Ta-176 8.08 h  M 0.001  2.0.10-10 3.2.10-10 0.001  3.1.10-10 
  S 0.001 2.1.10-10 3.3.10-10   
Ta-177 56.6 h  M 0.001  9.3.10-11 1.2.10-10 0.001  1.1.10-10 
  S 0.001  1.0.10-10 1.3.10-10   
Ta-178m  2.2 h  M 0.001  6.6.10-11 1.0.10-10 0.001  7.8.10-11 
  S 0.001  6.9.10-11 1.1.10-10   
Ta-179 664.9 d  M 0.001  2.0.10-10 1.3.10-10 0.001 6.5.10-11 
  S 0.001  5.2.10-10 2.9.10-10   
Ta-180 8.1 h  M 0.001  4.4.10-11 5.8.10-11 0.001  5.4.10-11 
  S 0.001  4.7.10-11 6.2.10-11   
Ta-182 115.0 d  M 0.001  7.2.10-9 5.8.10-9 0.001  1.5.10-9 
  S 0.001  9.7.10-9 7.4.10-9   
Ta-182m  15.84 min  M 0.001  2.1.10-11 3.4.10-11 0.001  1.2.10-11 
  S 0.001  2.2.10-11 3.6.10-11   
Ta-183 5.1 d  M 0.001  1.8.10-9 1.8.10-9 0.001  1.3.10-9 
  S 0.001  2.0.10-9 2.0.10-9   - 123 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Ta-184 8.7 h  M 0.001  4.1.10-10 6.0.10-10 0.001  6.8.10-10 
  S 0.001  4.4.10-10 6.3.10-10   
Ta-185 49 mi n M 0.001  4.6.10-11 6.8.10-11 0.001  6.8.10-11 
  S 0.001  4.9.10-11 7.2.10-11   
Ta-186 10.5 min  M 0.001  1.8.10-11 3.0.10-11 0.001  3.3.10-11 
  S 0.001  1.9.10-11 3.1.10-11   
wolfram         
W-176 2.3 h  F 0.3 4.4.10-11 7.6.10-11 0.3 1.0.10-10 
      0.01 1.1.10-10 
W-177 135 min  F 0.3 2.6.10-11 4.6.10-11 0.3 5.8.10-11 
      0.01 6.1.10-11 
W-178 21.7 d  F 0.3 7.6.10-11 1.2.10-10 0.3 2.2.10-10 
      0.01 2.5.10-10 
W-179 37.5 min  F 0.3 9.9.10-13 1.8.10-12 0.3 3.3.10-12 
      0.01 3.3.10-12 
W-181 121.2 d  F 0.3 2.8.10-11 4.3.10-11 0.3 7.6.10-11 
      0.01 8.2.10-11 
W-185 75.1 d  F 0.3 1.4.10-10 2.2.10-10 0.3 4.4.10-10 
      0.01 5.0.10-10 
W-187 23.9 h  F 0.3 2.0.10-10 3.3.10-10 0.3 6.3.10-10 
      0.01 7.1.10-10 
W-188 69.4 d  F 0.3 5.9.10-10 8.4.10-10 0.3 2.1.10-9 
      0.01 2.3.10-9 
rhenium         
Re-177 14.0 min  F 0.8 1.0.10-11 1.7.10-11 0.8 2.2.10-11 
  M 0.8 1.4.10-11 2.2.10-11   
Re-178 13.2 min  F 0.8 1.1.10-11 1.8.10-11 0.8 2.5.10-11 
  M 0.8 1.5.10-11 2.4.10-11   
Re-181 20 h F 0.8 1.9.10-10 3.0.1 0-10 0.8 4.2.10-10 
  M 0.8 2.5.10-10 3.7.10-10   
Re-182 64.0 h  F 0.8 6.8.10-10 1.1.10-9 0.8 1.4.10-9 
  M 0.8 1.3.10-9 1.7.10-9   
Re-182m  12.7 h  F 0.8 1.5.10-10 2.4.10-10 0.8 2.7.10-10 
  M 0.8 2.0.10-10 3.0.10-10   
Re-184 38.0 d  F 0.8 4.6.10-10 7.0.10-10 0.8 1.0.10-9 - 124 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.8 1.8.10-9 1.8.10-9   
Re-184m  165 d  F 0.8 6.1.10-10 8.8.10-10 0.8 1.5.10-9 
  M 0.8 6.1.10-9 4.8.10-9   
Re-186 90,64 h  F 0.8 5.3.10-10 7.3.10-10 0.8 1.5.10-9 
  M 0.8 1.1.10-9 1.2.10-9   
Re-186m  2.0 x 105 y F 0.8 8.5.10-10 1.2.10-9 0.8 2.2.10-9 
  M 0.8 1.1.10-8 7.9.10-9   
Re-187 5 x 1010 y F 0.8 1.9.10-12 2.6.10-12 0.8 5.1.10-12 
  M 0.8 6.0.10-12 4.6.10-12   
Re-188 16.98 h  F 0.8 4.7.10-10 6.6.10-10 0.8 1.4.10-9 
  M 0.8 5.5.10-10 7.4.10-10   
Re-188m  18.6 min  F 0.8 1.0.10-11 1.6.10-11 0.8 3.0.10-11 
  M 0.8 1.4.10-11 2.0.10-11   
Re-189 24.3 h  F 0.8 2.7.10-10 4.3.10-10 0.8 7.8.10-10 
  M 0.8 4.3.10-10 6.0.10-10   
osmium         
Os-180 22 min  F 0.01 8.8.10-12 1.6.10-11 0.01 1.7.10-11 
  M 0.01 1.4.10-11 2.4.10-11   
  S 0.01 1.5.10-11 2.5.10-11   
Os-181 105 min  F 0.01 3.6.10-11 6.4.10-11 0.01 8.9.10-11 
  M 0.01 6.3.10-11 9.6.10-11   
  S 0.01 6.6.10-11 1.0.10-10   
Os-182 22 h F 0.01 1.9.10-10 3.2.10-10 0.01 5.6.10-10 
  M 0.01 3.7.10-10 5.0.10-10   
  S 0.01 3.9.10-10 5.2.10-10   
Os-185 94 d F 0.01 1.1.10-9 1.4.10-9 0.01 5.1.10-10 
  M 0.01 1.2.10-9 1.0.10-9   
  S 0.01 1.5.10-9 1.1.10-9   
Os-189m  6.0 h  F 0.01 2.7.10-12 5.2.10-12 0.01 1.8.10-11 
  M 0.01 5.1.10-12 7.6.10-12   
  S 0.01 5.4.10-12 7.9.10-12   
Os-191 15.4 d  F 0.01 2.5.10-10 3.5.10-10 0.01 5.7.10-10 
  M 0.01 1.5.10-9 1.3.10-9   
  S 0.01 1.8.10-9 1.5.10-9   
Os-191m  13.03 h  F 0.01 2.6.10-11 4.1.10-11 0.01 9.6.10-11 - 125 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.01 1.3.10-10 1.3.10-10   
  S 0.01 1.5.10-10 1.4.10-10   
Os-193 30.0 h  F 0.01 1.7.10-10 2.8.10-10 0.01 8.1.10-10 
  M 0.01 4.7.10-10 6.4.10-10   
  S 0.01 5.1.10-10 6.8.10-10   
Os-194 6.0 y  F 0.01 1.1.10-8 1.3.10-8 0.01 2.4.10-9 
  M 0.01 2.0.10-8 1.3.10-8   
  S 0.01 7.9.10-8 4.2.10-8   
iridium         
Ir-182 15 min  F 0.01 1.5.10-11 2.6.10-11 0.01 4.8.10-11 
  M 0.01 2.4.10-11 3.9.10-11   
  S 0.01 2.5.10-11 4.0.10-11   
Ir-184 3.02 h  F 0.01 6.7.10-11 1.2.10-10 0.01 1.7.10-10 
  M 0.01 1.1.10-10 1.8.10-10   
  S 0.01 1.2.10-10 1.9.10-10   
Ir-185 14.0 h  F 0.01 8.8.10-11 1.5.10-10 0.01 2.6.10-10 
  M 0.01 1.8.10-10 2.5.10-10   
  S 0.01 1.9.10-10 2.6.10-10   
Ir-186 15.8 h  F 0.01 1.8.10-10 3.3.10-10 0.01 4.9.10-10 
  M 0.01 3.2.10-10 4.8.10-10   
  S 0.01 3.3.10-10 5.0.10-10   
Ir-186m  1.75 h  F 0.01 2.5.10-11 4.5.10-11 0.01 6.1.10-11 
  M 0.01 4.3.10-11 6.9.10-11   
  S 0.01 4.5.10-11 7.1.10-11   
Ir-187 10,5 h  F 0.01 4.0.10-11 7.2.10-11 0.01 1.2.10-10 
  M 0.01 7.5.10-11 1.1.10-10   
  S 0.01 7.9.10-11 1.2.10-10   
Ir-188 41.5 h  F 0.01 2.6.10-10 4.4.10-10 0.01 6.3.10-10 
  M 0.01 4.1.10-10 6.0.10-10   
  S 0.01 4.3.10-10 6.2.10-10   
Ir-189 13.3 d  F 0.01 1.1.10-10 1.7.10-10 0.01 2.4.10-10 
  M 0.01 4.8.10-10 4.1.10-10   
  S 0.01 5.5.10-10 4.6.10-10   
Ir-190 12.1 d  F 0.01 7.9.10-10 1.2.10-9 0.01 1.2.10-9 
  M 0.01 2.0.10-9 2.3.10-9   - 126 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 0.01 2.3.10-9 2.5.10-9   
Ir-190m’  3.1 h  F 0.01 5.3.10-11 9.7.10-11 0.01 1.2.10-10 
  M 0.01 8.3.10-11 1.4.10-10   
  S 0.01 8.6.10-11 1.4.10-10   
Ir-190m  1.2 h  F 0.01 3.7.10-12 5.6.10-12 0.01 8.0.10-12 
  M 0.01 9.0.10-12 1.0.10-11   
  S 0.01 1.0.10-11 1.1.10-11   
Ir-192 74.02 d  F 0.01 1.8.10-9 2.2.10-9 0.01 1.4.10-9 
  M 0.01 4.9.10-9 4.1.10-9   
  S 0.01 6.2.10-9 4.9.10-9   
Ir-192m’  241 y  F 0.01 4.8.10-9 5.6.10-9 0.01 3.1.10-10 
  M 0.01 5.4.10-9 3.4.10-9   
  S 0.01 3.6.10-8 1.9.10-8   
Ir-193m  11.9 d  F 0.01 1.0.10-10 1.6.10-10 0.01 2.7.10-10 
  M 0.01 1.0.10-9 9.1.10-10   
  S 0.01 1.2.10-9 1.0.10-9   
Ir-194 19.15 h  F 0.01 2.2.10-10 3.6.10-10 0.01 1.3.10-9 
  M 0.01 5.3.10-10 7.1.10-10   
  S 0.01 5.6.10-10 7.5.10-10   
Ir-194m  171 d  F 0.01 5.4.10-9 6.5.10-9 0.01 2.1.10-9 
  M 0.01 8.5.10-9 6.5.10-9   
  S 0.01 1.2.10-8 8.2.10-9   
Ir-195 2.5 h  F 0.01 2.6.10-11 4.5.10-11 0.01 1.0.10-10 
  M 0.01 6.7.10-11 9.6.10-11   
  S 0.01 7.2.10-11 1.0.10-10   
Ir-195m  3.8 h  F 0.01 6.5.10-11 1.1.10-10 0.01 2.1.10-10 
  M 0.01 1.6.10-10 2.3.10-10   
  S 0.01 1.7.10-10 2.4.10-10   
platinum         
Pt-186 2.0 h  F 0.01 3.6.10-11 6.6.10-11 0.01 9.3.10-11 
Pt-188 10,2 d  F 0.01 4.3.10-10 6.3.10-10 0.01 7.6.10-10 
Pt-189 10,87 h  F 0.01 4.1.10-11 7.3.10-11 0.01 1.2.10-10 
Pt-191 2,8 d  F 0.01 1.1.10-10 1.9.10-10 0.01 3.4.10-10 
Pt-193 50 y F 0.01 2.1.10-11 2.7.10-11 0.01 3.1.10-11 
Pt-193m  4.33 d  F 0.01 1.3.10-10 2.1.10-10 0.01 4.5.10-10 - 127 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Pt-195m  4.02 d  F 0.01 1.9.10-10 3.1.10-10 0.01 6.3.10-10 
Pt-197 18.3 h  F 0.01 9.1.10-11 1.6.10-10 0.01 4.0.10-10 
Pt-197m  94.4 min  F 0.01 2.5.10-11 4.3.10-11 0.01 8.4.10-11 
Pt-199 30.8 min  F 0.01 1.3.10-11 2.2.10-11 0.01 3.9.10-11 
Pt-200 12.5 h  F 0.01 2.4.10-10 4.0.10-10 0.01 1.2.10-9 
gold        
Au-193 17.65 h  F 0.1 3.9.10-11 7.1.10-11 0.1 1.3.10-10 
  M 0.1 1.1.10-10 1.5.10-10   
  S 0.1 1.2.10-10 1.6.10-10   
Au-194 39.5 h  F 0.1 1.5.10-10 2.8.10-10 0.1 4.2.10-10 
  M 0.1 2.4.10-10 3.7.10-10   
  S 0.1 2.5.10-10 3.8.10-10   
Au-195 183 d  F 0.1 7.1.10-11 1.2.10-10 0.1 2.5.10-10 
  M 0.1 1.0.10-9 8.0.10-10   
  S 0.1 1.6.10-9 1.2.10-9   
Au-198 2.696 d  F 0.1 2.3.10-10 3.9.10-10 0.1 1.0.10-9 
  M 0.1 7.6.10-10 9.8.10-10   
  S 0.1 8.4.10-10 1.1.10-9   
Au-198m  2.30 d  F 0.1 3.4.10-10 5.9.10-10 0.1 1.3.10-9 
  M 0.1 1.7.10-9 2.0.10-9   
  S 0.1 1.9.10-9 1.9.10-9   
Au-199 3.139 d  F 0.1 1.1.10-10 1.9.10-10 0.1 4.4.10-10 
  M 0.1 6.8.10-10 6.8.10-10   
  S 0.1 7.5.10-10 7.6.10-10   
Au-200 48.4 min  F 0.1 1.7.10-11 3.0.10-11 0.1 6.8.10-11 
  M 0.1 3.5.10-11 5.3.10-11   
  S 0.1 3.6.10-11 5.6.10-11   
Au-200m  18.7 h  F 0.1 3.2.10-10 5.7.10-10 0.1 1.1.10-9 
  M 0.1 6.9.10-10 9.8.10-10   
  S 0.1 7.3.10-10 1.0.10-9   
Au-201 26.4 min  F 0.1 9.2.10-12 1.6.10-11 0.1 2.4.10-11 
  M 0.1 1.7.10-11 2.8.10-11   
  S 0.1 1.8.10-11 2.9.10-11   
mercury         
Hg-193 inorg.  3.5 h  F 0.02 2.8.10-11 5.0.10-11 0.02 8.2.10-11 - 128 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.02 7.5.10-11 1.0.10-10   
Hg-193 org.   F 0.4 2.6.10-11 4.7.10-11 1 3.1.10-11 
      0.4 6.6.10-11 
Hg-193m inorg.  11.1 h  F 0.02 1.2.10-10 2.3.10-10 0.02 4.0.10-10 
  M 0.02 2.6.10-10 3.8.10-10   
Hg-193m org.   F 0.4 1.1.10-10 2.0.10-10 1 1.3.10-10 
      0.4 3.0.10-10 
Hg-194 inorg.  260 y  F 0.02 1.3.10-8 1.5.10-8 0.02 1.4.10-9 
  M 0.02 7.8.10-9 5.3.10-9   
Hg-194 org.   F 0.4 1.5.10-8 1.9.10-8 1 5.1.10-8 
      0.4 2.1.10-8 
Hg-195 inorg.  9.9 h  F 0.02 2.7.10-11 4.8.10-11 0.02 9.7.10-11 
  M 0.02 7.2.10-11 9.2.10-11   
Hg-195 org.   F 0.4 2.4.10-11 4.4.10-11 1 3.4.10-11 
      0.4 7.5.10-11 
Hg-195m inorg.  41.6 h  F 0.02 1.5.10-10 2.6.10-10 0.02 5.6.10-10 
  M 0.02 5.1.10-10 6.5.10-10   
Hg-195m org.   F 0.4 1.3.10-10 2.2.10-10 1 2.2.10-10 
      0.4 4.1.10-10 
Hg-197 inorg.  64.1 h  F 0.02 6.0.10-11 1.0.10-10 0.02 2.3.10-10 
  M 0.02 2.9.10-10 2.8.10-10   
Hg-197 org.   F 0.4 5.0.10-11 8.5.10-11 1 9.9.10-11 
      0.4 1.7.10-10 
Hg-197m inorg.  23.8 h F 0.02 1.2.10-10 2.1.10-10 0.02 4.7.10-10 
  M 0.02 5.1.10-10 6.6.10-10   
Hg-197m org.   F 0.4 1.0.10-10 1.8.10-10 1 1.5.10-10 
      0.4 3.4.10-10 
Hg-199m inorg.  42.6 min  F 0.02 1.6.10-11 2.7.10-11 0.02 3.1.10-11 
  M 0.02 3.3.10-11 5.2.10-11   
Hg-199m org.   F 0.4 1.6.10-11 2.7.10-11 1 2.8.10-11 
      0.4 3.1.10-11 
Hg-203 inorg.  46.60 d  F 0.02 4.7.10-10 5.9.10-10 0.02 5.4.10-10 
  M 0.02 2.3.10-9 1.9.10-9   
Hg-203 org.   F 0.4 5.7.10-10 7.5.10-10 1 1.9.10-9 
      0.4 1.1.10-9 - 129 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
thallium         
Tl-194 33 min  F 1 4.8.10-12 8.9.10-12 1 8.1.10-12 
Tl-194m  32.8 min  F 1 2.0.10-11 3.6.10-11 1 4.0.10-11 
Tl-195 1.16 h  F 1 1.6.10-11 3.0.10-11 1 2.7.10-11 
Tl-197 2,84 h  F 1 1.5.10-11 2.7.10-11 1 2.3.10-11 
Tl-198 5.3 h  F 1 6.6.10-11 1.2.10-10 1 7.3.10-11 
Tl-198m  1.87 h  F 1 4.0.10-11 7.3.10-11 1 5.4.10-11 
Tl-199 7.42 h  F 1 2.0.10-11 3.7.10-11 1 2.6.10-11 
Tl-200 26.1 h  F 1 1.4.10-10 2.5.10-10 1 2.0.10-10 
Tl-201 3.044 d  F 1 4.7.10-11 7.6.10-11 1 9.5.10-11 
Tl-202 12.23 d  F 1 2.0.10-10 3.1.10-10 1 4.5.10-10 
Tl-204 3.779 y  F 1 4.4.10-10 6.2.10-10 1 1.3.10-9 
lead        
Pb-195m  15.8 min  F 0.2 1.7.10-11 3.0.10-11 0.2 2.9.10-11 
Pb-198 2.4 h  F 0.2 4.7.10-11 8.7.10-11 0.2 1.0.10-10 
Pb-199 90 min  F 0.2 2.6.10-11 4.8.10-11 0.2 5.4.10-11 
Pb-200 21.5 h  F 0.2 1.5.1 0-10 2.6.10-10 0.2 4.0.10-10 
Pb-201 9.4 h  F 0.2 6.5.10-11 1.2.10-10 0.2 1.6.10-10 
Pb-202 3 x 105 y F 0.2 1.1.10-8 1.4.10-8 0.2 8.7.10-9 
Pb-202m  3.62 h  F 0.2 6.7.10-11 1.2.10-10 0.2 1.3.10-10 
Pb-203 52.05 h  F 0.2 9.1.10-11 1.6.10-10 0.2 2.4.10-10 
Pb-205 1.43 x 107 y F 0.2 3.4.10-10 4.1.10-10 0.2 2.8.10-10 
Pb-209 3.253 h  F 0.2 1.8.10-11 3.2.10-11 0.2 5.7.10-11 
Pb-210 22.3 y  F 0.2 8.9.10-7 1.1.10-6 0.2 6.8.10-7 
Pb-211 36.1 min  F 0.2 3.9.10-9 5.6.10-9 0.2 1.8.10-10 
Pb-212 10,64 h  F 0.2 1.9.10-8 3.3.10-8 0.2 5.9.10-9 
Pb-214 26.8 min  F 0.2 2.9.10-9 4.8.10-9 0.2 1.4.10-10 
bismuth         
Bi-200 36.4 min  F 0.05 2.4.10-11 4.2.10-11 0.05 5.1.10-11 
  M 0.05 3.4.10-11 5.6.10-11   
Bi-201 108 min  F 0.05 4.7.10-11 8.3.10-11 0.05 1.2.10-10 
  M 0.05 7.0.10-11 1.1.10-10   
Bi-202 1.67 h  F 0.05 4.6.10-11 8.4.10-11 0.05 8.9.10-11 
  M 0.05 5.8.10-11 1.0.10-10   
Bi-203 11.76 h  F 0.05 2.0.10-10 3.6.10-10 0.05 4.8.10-10 - 130 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  M 0.05 2.8.10-10 4.5.10-10   
Bi-205 15.31 d  F 0.05 4.0.10-10 6.8.10-10 0.05 9.0.10-10 
  M 0.05 9.2.10-10 1.0.10-9   
Bi-206 6.243 d  F 0.05 7.9.10-10 1.3.10-9 0.05 1.9.10-9 
  M 0.05 1.7.10-9 2.1.10-9   
Bi-207 38 y F 0.05 5.2.10-10 8.4.10-10 0.05 1.3.10-9 
  M 0.05 5.2.10-9 3.2.10-9   
Bi-210 5.012 d  F 0.05 1.1.10-9 1.4.10-9 0.05 1.3.10-9 
  M 0.05 8.4.10-8 6.0.10-8   
Bi-210m  3.0 x 106 y F 0.05 4.5.10-8 5.3.10-8 0.05 1.5.10-8 
  M 0.05 3.1.10-6 2.1.10-6   
Bi-212 60.55 min  F 0.05 9.3.10-9 1.5.10-8 0.05 2.6.10-10 
  M 0.05 3.0.10-8 3.9.10-8   
Bi-213 45.65 min  F 0.05 1.1.10-8 1.8.10-8 0.05 2.0.10-10 
  M 0.05 2.9.10-8 4.1.10-8   
Bi-214 19.9 min  F 0.05 7.2.10-9 1.2.10-8 0.05 1.1.10-10 
  M 0.05 1.4.10-8 2.1.10-8   
polonium         
Po-203 36.7 min  F 0.1 2.5.10-11 4.5.10-11 0.1 5.2.10-11 
  M 0.1 3.6.10-11 6.1.10-11   
Po-205 1.80 h  F 0.1 3.5.10-11 6.0.10-11 0.1 5.9.10-11 
  M 0.1 6.4.10-11 8.9.10-11   
Po-207 350 min  F 0.1 6.3.10-11 1.2.10-10 0.1 1.4.10-10 
  M 0.1 8.4.10-11 1.5.10-10   
Po-210 138.38 d  F 0.1 6.0.10-7 7.1.10-7 0.1 2.4.10-7 
  M 0.1 3.0.10-6 2.2.10-6   
astatine         
At-207 1.80 h  F 1 3.5.10-10 4.4.10-10 1 2.3.10-10 
  M 1 2.1.10-9 1.9.10-9   
At-211 7.214 h  F 1 1.6.10-8 2.7.10-8 1 1.1.10-8 
  M 1 9.8.10-8 1.1.10-7   
francium         
Fr-222 14.4 min  F 1 1.4.10-8 2.1.10-8 1 7.1.10-10 
Fr-223 21.8 min  F 1 9.1.10-10 1.3.10-9 1 2.3.10-9 - 131 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
radium         
Ra-223 11.434 d  M 0.2 6.9.10-6 5.7.10-6 0.2 1.0.10-7 
Ra-224 3.66 d  M 0.2 2.9.10-6 2.4.10-6 0.2 6.5.10-8 
Ra-225 14.8 d  M 0.2 5.8.10-6 4.8.10-6 0.2 9.5.10-8 
Ra-226 1600 y  M 0.2 3.2.10-6 2.2.10-6 0.2 2.8.10-7 
Ra-227 42.2 min  M 0.2 2.8.10-10 2.1.10-10 0.2 8.4.10-11 
Ra-228 5.75 y  M 0.2 2.6.10-6 1.7.10-6 0.2 6.7.10-7 
actinium         
Ac-224 2.9 h  F 5.0.10-4 1.1.10-8 1.3.10-8 5.0.10-4 7.0.10-10 
  M 5.0.10-4 1.0.10-7 8.9.10-8   
  S 5.0.10-4 1.2.10-7 9.9.10-8   
Ac-225 10.0 d  F 5.0.10-4 8.7.10-7 1.0.10-6 5.0.10-4 2.4.10-8 
  M 5.0.10-4 6.9.10-6 5.7.10-6   
  S 5.0.10-4 7.9.10-6 6.5.10-6   
Ac-226 29 h F 5.0.10-4 9.5.10-8 2.2.10-7 5.0.10-4 1.0.10-8 
  M 5.0.10-4 1.1.10-6 9.2.10-7   
  S 5.0.10-4 1.2.10-6 1.0.10-6   
Ac-227 21.773 y  F 5.0.10-4 5.4.10-4 6.3.10-4 5.0.10-4 1.1.10-6 
  M 5.0.10-4 2.1.10-4 1.5.10-4   
  S 5.0.10-4 6.6.10-5 4.7.10-5   
Ac-228 6.13 h  F 5.0.10-4 2.5.10-8 2.9.10-8 5.0.10-4 4.3.10-10 
  M 5.0.10-4 1.6.10-8 1.2.10-8   
  S 5.0.10-4 1.4.10-8 1.2.10-8   
thorium         
Th-226 30.9 min  M 5.0.10-4 5.5.10-8 7.4.10-8 5.0.10-4 3.5.10-10 
  S 2.0.10-4 5.9.10-8 7.8.10-8 2.0.10-4 3.6.10-10 
Th-227 18.718 d  M 5.0.10-4 7.8.10-6 6.2.10-6 5.0.10-4 8.9.10-9 
  S 2.0.10-4 9.6.10-6 7.6.10-6 2.0.10-4 8.4.10-9 
Th-228 1.9131 y  M 5.0.10-4 3.0.10-5 2.2.10-5 5.0.10-4 7.2.10-8 
  S 2.0.10-4 3.7.10-5 2.5.10-5 2.0.10-4 3.5.10-8 
Th-229 7340 y  M 5.0.10-4 9.9.10-5 6.9.10-5 5.0.10-4 4.8.10-7 
  S 2.0.10-4 6.5.10-5 4.8.10-5 2.0.10-4 2.0.10-7 
Th-230 7.7.104 y M 5.0.10-4 4.0.10-5 2.8.10-5 5.0.10-4 2.1.10-7 
  S 2.0.10-4 1.3.10-5 7.2.10-6 2.0.10-4 8.7.10-8 
Th-231 25.52 h  M 5.0.10-4 2.9.10-10 3.7.10-10 5.0.10-4 3.4.10-10 - 132 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 2.0.10-4 3.2.10-10 4.0.10-10 2.0.10-4 3.4.10-10 
Th-232 1.405.1010 y M 5.0.10-4 4.2.10-5 2.9.10-5 5.0.10-4 2.2.10-7 
  S 2.0.10-4 2.3.10-5 1.2.10-5 2.0.10-4 9.2.10-8 
Th-234 24.10 d  M 5.0.10-4 6.3.10-9 5.3.10-9 5.0.10-4 3.4.10-9 
  S 2.0.10-4 7.3.10-9 5.8.10-9 2.0.10-4 3.4.10-9 
protactinium         
Pa-227 38.3 min  M 5.0.10-4 7.0.10-8 9.0.10-8 5.0.10-4 4.5.10-10 
  S 5.0.10-4 7.6.10-8 9.7.10-8   
Pa-228 22 h M 5.0.10-4 5.9.10-8 4.6.10-8 5.0.10-4 7.8.10-10 
  S 5.0.10-4 6.9.10-8 5.1.10-8   
Pa-230 17.4 d  M 5.0.10-4 5.6.10-7 4.6.10-7 5.0.10-4 9.2.10-10 
  S 5.0.10-4 7.1.10-7 5.7.10-7   
Pa-231 3.276.104 r M 5.0.10-4 1.3.10-4 8.9.10-5 5.0.10-4 7.1.10-7 
  S 5.0.10-4 3.2.10-5 1.7.10-5   
Pa-232 1.31 d  M 5.0.10-4 9.5.10-9 6.8.10-9 5.0.10-4 7.2.10-10 
  S 5.0.10-4 3.2.10-9 2.0.10-9   
Pa-233 27.0 d  M 5.0.10-4 3.1.10-9 2.8.10-9 5.0.10-4 8.7.10-10 
  S 5.0.10-4 3.7.10-9 3.2.10-9   
Pa-234 6.70 h M 5.0.10-4 3.8.10-10 5.5.10-10 5.0.10-4 5.1.10-10 
  S 5.0.10-4 4.0.10-10 5.8.10-10   
uranium         
U-230 20,8 d  F 0.02 3.6.10-7 4.2.10-7 0.02 5.5.10-8 
  M 0.02 1.2.10-5 1.0.10-5 0.002  2.8.10-8 
  S 0.002  1.5.10-5 1.2.10-5   
U-231 4.2 d  F 0.02 6.7.10-11 1.610-10 0.02 2.8.10-10 
  M 0.02 4.3.10-10 4.5.10-10 0.002  2.8.10-10 
  S 0.002  4.8.10-10 4.9.10-10   
U-232 72 y F 0.02 4.0.10-6 4.7.10-6 0.02 3.3.10-7 
  M 0.02 7.2.10-6 4.8.10-6 0.002  3.7.10-8 
  S 0.002  3.5.10-5 2.6.10-5   
U-233 1.585.105 y F 0.02 5.7.10-7 6.6.10-7 0.02 5.0.10-8 
  M 0.02 3.2.10-6 2.2.10-6 0.002  8.5.10-9 
  S 0.002  8.7.10-6 6.9.10-6   
U-234 2.445.105 y F 0.02 5.5.10-7 6.4.10-7 0.02 4.9.10-8 
  M 0.02 3.1.10-6 2.1.10-6 0.002  8.3.10-9 - 133 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 0.002  8.5.10-6 6.8.10-6   
U-235 703.8.1 06 y F 0.02 5.1.10-7 6.0.10-7 0.02 4.6.10-8 
  M 0.02 2.8.10-6 1.8.10-6 0.002  8.3.10-9 
  S 0.002  7.7.10-6 6.1.10-6   
U-236 2.3415.107 y F 0.02 5.2.10-7 6.1.10-7 0.02 4.6.10-8 
  M 0.02 2.9.10-6 1.9.10-6 0.002  7.9.10-9 
  S 0.002  7.9.10-6 6.3.10-6   
U-237 6.75 d  F 0.02 1.9.10-10 3.3.10-10 0.02 7.6.10-10 
  M 0.02 1.6.10-9 1.5.10-9 0.002  7.7.10-10 
  S 0.002  1.8.10-9 1.7.10-9   
U-238 4.468.109 y F 0.02 4.9.10-7 5.8.10-7 0.02 4.4.10-8 
  M 0.02 2.6.10-6 1.6.10-6 0.002  7.6.10-9 
  S 0.002  7.3.10-6 5.7.10-6   
U-239 23.54 min  F 0.02 1.1.10-11 1.8.10-11 0.02 2.7.10-11 
  M 0.02 2.3.10-11 3.3.10-11 0.002  2.8.10-11 
  S 0.002  2.4.10-11 3.5.10-11   
U-240 14.1 h  F 0.02 2.1.10-10 3.7.10-10 0.02 1.1.10-9 
  M 0.02 5.3.10-10 7.9.10-10 0.002  1.1.10-9 
  S 0.002  5.7.1 0-10 8.4.10-10   
neptunium         
Np-232 14.7 min  M 5.0.10-4 4.7.10-11 3.5.10-11 5.0.10-4 9.7.10-12 
Np-233 36.2 min  M 5.0.10-4 1.7.10-12 3.0.10-12 5.0.10-4 2.2.10-12 
Np-234 4.4 d  M 5.0.10-4 5.4.10-10 7.3.10-10 5.0.10-4 8.1.10-10 
Np-235 396.1 d  M 5.0.1 0-4 4.0.10-10 2.7.10-10 5.0.10-4 5.3.10-11 
Np-236 115.103 y M 5.0.10-4 3.0.10-6 2.0.10-6 5.0.10-4 1.7.10-8 
Np-236m  22.5 h  M 5.0.10-4 5.0.10-9 3.6.10-9 5.0.10-4 1.9.10-10 
Np-237 2.14.106 y M 5.0.10-4 2.1.10-5 1.5.10-5 5.0.10-4 1.1.10-7 
Np-238 2.117 d  M 5.0.10-4 2.0.10-9 1.7.10-9 5.0.10-4 9.1.10-10 
Np-239 2.355 d  M 5.0.10-4 9.0.10-10 1.1.10-9 5.0.10-4 8.0.10-10 
Np-240 65 min  M 5.0.10-4 8.7.10-11 1.3.10-10 5.0.10-4 8.2.10-11 
plutonium         
Pu-234 8.8 h  M 5.0.10-4 1.9.10-8 1.6.10-8 5.0.10-4 1.6.10-10 
  S 1.0.10-5 2.2.10-8 1.8.10-8 1.0.10-4 1.6.10-10 
      1.0.10-5 1.5.10-10 
Pu-235 25.3 min  M 5.0.10-4 1.5.10-12 2.5.10-12 5.0.10-4 2.1.10-12 - 134 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
  S 1.0.10-5 1.6.10-12 2.6.10-12 1.0.10-4 2.1.10-12 
      1.0.10-5 2.1.10-12 
Pu-236 2,851 y  M 5.0.10-4 1.8.10-5 1.3.10-5 5.0.10-4 8.6.10-8 
  S 1.0.10-5 9.6.10-6 7.4.10-6 1.0.10-4 2.1.10-8 
      1.0.10-5 6.3.10-9 
Pu-237 45.3 d  M 5.0.10-4 3.3.10-10 2.9.10-10 5.0.10-4 1.0.10-10 
  S 1.0.10-5 3.6.10-10 3.0.10-10 1.0.10-4 1.0.10-10 
      1.0.10-5 1.0.10-10 
Pu-238 87.74 y  M 5.0.10-4 4.3.10-5 3.0.10-5 5.0.10-4 2.3.10-7 
  S 1.0.10-5 1.5.10-5 1.1.10-5 1.0.10-4 4.9.10-8 
      1.0.10-5 8.8.10-9 
Pu-239 24065 y  M 5.0.10-4 4.7.10-5 3.2.10-5 5.0.10-4 2.5.10-7 
  S 1.0.10-5 1.5.10-5 8.3.10-6 1.0.10-4 5.3.10-8 
      1.0.1 0-5 9.0.10-9 
Pu-240 6537 y  M 5.0.10-4 4.7.10-5 3.2.10-5 5.0.10-4 2.5.10-7 
  S 1.0.10-5 1.5.10-5 8.3.10-6 1.0.10-4 5.3.10-8 
      1.0.10-5 9.0.10-9 
Pu-241 14.4 y  M 5.0.10-4 8.5.10-7 5.8.10-7 5.0.10-4 4.7.10-9 
  S 1.0.10-5 1.6.10-7 8.4.10-8 1.0.10-4 9.6.10-10 
      1.0.10-5 1.1.10-10 
Pu-242 3.763.105 y M 5.0.10-4 4.4.10-5 3.1.10-5 5.0.10-4 2.4.10-7 
  S 1.0.10-5 1.4.10-5 7.7.10-6 1.0.10-4 5.0.10-8 
      1.0.10-5 8.6.10-9 
Pu-243 4.956 h  M 5.0.10-4 8.2.10-11 1.1.10-10 5.0.10-4 8.5.10-11 
  S 1.0.10-5 8.5.10-11 1.1.10-10 1.0.10-4 8.5.10-11 
      1.0.10-5 8.5.10-11 
Pu-244 8.26.107 y M 5.0.10-4 4.4.10-5 3.0.10-5 5.0.10-4 2.4.10-7 
  S 1.0.10-5 1.3.10-5 7.4.10-6 1.0.10-4 5.2.10-8 
      1.0.10-5 1.1.10-8 
Pu-245 10,5 h  M 5.0.10-4 4.5.10-10 6.1.10-10 5.0.1 0-4 7.2.10-10 
  S 1.0.10-5 4.8.10-10 6.5.10-10 1.0.10-4 7.2.10-10 
      1.0.10-5 7.2.10-10 
Pu-246 10,85 d  M 5.0.10-4 7.0.10-9 6.5.10-9 5.0.10-4 3.3.10-9 
  S 1.0.10-5 7.6.10-9 7.0.10-9 1.0.10-4 3.3.10-9 
      1.0.10-5 3.3.10-9 - 135 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
americium         
Am-237 73.0 min  M 5.0.10-4 2.5.10-11 3.6.10-11 5.0.10-4 1.8.10-11 
Am-238 98 min  M 5.0.10-4 8.5.10-11 6.6.10-11 5.0.10-4 3.2.10-11 
Am-239 11.9 h  M 5.0.10-4 2.2.10-10 2.9.10-10 5.0.10-4 2.4.10-10 
Am-240 50,8 h  M 5.0.10-4 4.4.10-10 5.9.10-10 5.0.10-4 5.8.10-10 
Am-241 432.2 y  M 5.0.10-4 3.9.10-5 2.7.10-5 5.0.10-4 2.0.10-7 
Am-242 16.02 h  M 5.0.10-4 1.6.10-8 1.2.10-8 5.0.10-4 3.0.10-10 
Am-242m  152 y  M 5.0.10-4 3.5.10-5 2.4.10-5 5.0.10-4 1.9.10-7 
Am-243 7380 y  M 5.0.10-4 3.9.10-5 2.7.10-5 5.0.10-4 2.0.10-7 
Am-244 10.1 h  M 5.0.10-4 1.9.10-9 1.5.10-9 5.0.10-4 4.6.10-10 
Am-244m  26 min  M 5.0.10-4 7.9.10-11 6.2.10-11 5.0.10-4 2.9.10-11 
Am-245 2.05 h  M 5.0.10-4 5.3.10-11 7.6.10-11 5.0.10-4 6.2.10-11 
Am-246 39 min  M 5.0.10-4 6.8.10-11 1.1.10-10 5.0.10-4 5.8.10-11 
Am-246m  25.0 min  M 5.0.10-4 2.3.10-11 3.8.10-11 5.0.10-4 3.4.10-11 
curium         
Cm-238 2.4 h  M 5.0.10-4 4.1.10-9 4.8.10-9 5.0.10-4 8.0.10-11 
Cm-240 27 d M 5.0.10-4 2.9.10-6 2.3.10-6 5.0.10-4 7.6.10-9 
Cm-241 32,8 d  M 5.0.10-4 3.4.10-8 2.6.10-8 5.0.10-4 9.1.10-10 
Cm-242 162,8 d  M 5.0.10-4 4.8.10-6 3.7.10-6 5.0.10-4 1.2.10-8 
Cm-243 28.5 y  M 5.0.10-4 2.9.10-5 2.0.10-5 5.0.10-4 1.5.10-7 
Cm-244 18.11 y  M 5.0.10-4 2.5.10-5 1.7.10-5 5.0.10-4 1.2.10-7 
Cm-245 8500 y  M 5.0.10-4 4.0.10-5 2.7.10-5 5.0.10-4 2.1.10-7 
Cm-246 4730 y  M 5.0.10-4 4.0.10-5 2.7.10-5 5.0.10-4 2.1.10-7 
Cm-247 1.56.107 y M 5.0.10-4 3.6.10-5 2.5.10-5 5.0.10-4 1.9.10-7 
Cm-248 3.39.105 y M 5.0.10-4 1.4.10-4 9.5.10-5 5.0.10-4 7.7.10-7 
Cm-249 64.15 min  M 5.0.10-4 3.2.10-11 5.1.10-11 5.0.10-4 3.1.10-11 
Cm-250 6900 y  M 5.0.10-4 7.9.10-4 5.4.10-4 5.0.10-4 4.4.10-6 
berkelium         
Bk-245 4.94 d  M 5.0.10-4 2.0.10-9 1.8.10-9 5.0.10-4 5.7.10-10 
Bk-246 1.83 d  M 5.0.10-4 3.4.10-10 4.6.10-10 5.0.10-4 4.8.10-10 
Bk-247 1380 y  M 5.0.10-4 6.5.10-5 4.5.10-5 5.0.10-4 3.5.10-7 
Bk-249 320 d  M 5.0.10-4 1.5.10-7 1.0.10-7 5.0.10-4 9.7.10-10 
Bk-250 3.222 h  M 5.0.10-4 9.6.10-10 7.1.10-10 5.0.10-4 1.4.10-10 
californium         
Cf-244 19.4 min  M 5.0.10-4 1.3.10-8 1.8.10-8 5.0.10-4 7.0.10-11 - 136 - 
 
 Element   Inhala tion Ingestion  
nuclide  T½ typ
e f1 hinh [Sv/Bq]  
f1 hing 
[Sv/Bq]  dama = 1 µm  dama = 5 µm  
Cf-246 35.7 h  M 5.0.10-4 4.2.10-7 3.5.10-7 5.0.10-4 3.3.10-9 
Cf-248 333.5 d  M 5.0.10-4 8.2.10-6 6.1.10-6 5.0.10-4 2.8.10-8 
Cf-249 350,6 y  M 5.0.10-4 6.6.10-5 4.5.10-5 5.0.10-4 3.5.10-7 
Cf-250 13.08 y  M 5.0.10-4 3.2.10-5 2.2.10-5 5.0.10-4 1.6.10-7 
Cf-251 898 y  M 5.0.10-4 6.7.10-5 4.6.10-5 5.0.10-4 3.6.10-7 
Cf-252 2.638 y  M 5.0.10-4 1.8.10-5 1.3.10-5 5.0.10-4 9.0.10-8 
Cf-253 17.81 d  M 5.0.10-4 1.2.10-6 1.0.10-6 5.0.10-4 1.4.10-9 
Cf-254 60,5 d  M 5.0.10-4 3.7.10-5 2.2.10-5 5.0.10-4 4.0.10-7 
einsteinium         
Es-250m  2.1 h M 5.0.10-4 5.9.10-10 4.2.10-10 5.0.10-4 2.1.10-11 
Es-251 33 h M 5.0.10-4 2.0.10-9 1.7.10-9 5.0.10-4 1.7.10-10 
Es-253 20,47 d  M 5.0.10-4 2.5.10-6 2.1.10-6 5.0.10-4 6.1.10-9 
Es-254 275.7 d  M 5.0.10-4 8.0.10-6 6.0.10-6 5.0.10-4 2.8.10-8 
Es-254m  39.3 h  M 5.0.10-4 4.4.10-7 3.7.10-7 5.0.10-4 4.2.10-9 
fermium         
Fm-252 22.7 h  M 5.0.10-4 3.0.10-7 2.6.10-7 5.0.10-4 2.7.10-9 
Fm-253 3.00 d  M 5.0.10-4 3.7.10-7 3.0.10-7 5.0.10-4 9.1.10-10 
Fm-254 3.240 h  M 5.0.10-4 5.6.10-8 7.7.10-8 5.0.10-4 4.4.10-10 
Fm-255 20.07 h  M 5.0.10-4 2.5.10-7 2.6.10-7 5.0.10-4 2.5.10-9 
Fm-257 100,5 d  M 5.0.10-4 6.6.10-6 5.2.10-6 5.0.10-4 1.5.10-8 
mendelevium         
Md-257 5.2 h  M 5.0.10-4 2.3.10-8 2.0.10-8 5.0.10-4 1.2.10-10 
Md-258 55 d M 5.0.10-4 5.5.10-6 4.4.10-6 5.0.10-4 1.3.10-8 
 
Legend:  
 
inorg. - inorganic compounds  
org.- organic compounds  
 
Conversion factors h inh for intake via inhalation of radioactive aerosols or h ing for intake via ingestion serve for 
conversion of radionuclide intake to the committed effective dose f or inhalation of radioactive aerosols or for 
ingestion of a radioactive substance by a radiation worker.  
Conversion factors h inh for intake via inhalation are provided for an aerosol with d ama=1 mm and for an aerosol 
with d ama=5 mm depending on the absorpt ion type in the lungs (F, M, S).  
Conversion factors h ing for intake via ingestion are provided depending on the absorption type in the digestive 
tract.  
For unidentified radionuclides and chemical forms of radioactive substances or characteristics of inhale d aerosol, 
activity is attributed to those radionuclides and their forms or such an aerosol for which the table stipulates the 
highest conversion factor.  - 137 - 
 
 Conversion factors h ing for intake via ingestion by an individual from the population  
 
Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
hydrogen           
H-3 tritiated 
water  1.0 6.4.10-11  1.0 4.8.10-11 3.1.10-11 2.3.10-11 1.8.10-11 1.8.10-11 
H-3 organically 
bound  1.0 1.2.10-10 1.0 1.2.10-10 7.3.10-11 5.7.10-11 4.2.10-11 4.2.10-11 
beryllium           
Be-7  0.02 1.8.10-10 0.005  1.3.10-10 7.7.10-11 5.3.10-11 3.5.10-11 2.8.10-11 
Be-10  0.02 1.4.10-8 0.005  8.0.10-9 4.1.10-9 2.4.10-9 1.4.10-9 1.1.10-9 
carbon    
       
C-11  1.0 2.6.10-10 1.0 1.5.10-10 7.3.10-11 4.3.10-11 3.0.10-11 2.4.10-11 
C-14  1.0 1.4.10-9 1.0 1.6.10-9 9.9.10-10 8.0.10-10 5.7.10-10 5.8.10-10 
fluorine    
       
F-18  1.0 5.2.10-10 1.0 3.0.10-10 1.5.10-10 9.1.10-11 6.2.10-11 4.9.10-11 
sodium    
       
Na-22  1.0 2.1.10-8 1.0 1.5.10-8 8.4.10-9 5.5.10-9 3.7.10-9 3.2.10-9 
Na-24  1.0 3.5.10-9 1.0 2.3.10-9 1.2.10-9 7.7.10-10 5.2.10-10 4.3.10-10 
magnesium    
       
Mg-28  1.0 1.2.10-8 0.5 1.4.10-8 7.4.10-9 4.5.10-9 2.7.10-9 2.2.10-9 
aluminium    
       
Al-26  0.02 3.4.10-8 0.01 2.1.10-8 1.1.10-8 7.1.10-9 4.3.10-9 3.5.10-9 
silicon    
       
Si-31  0.02 1.9.10-9 0.01 1.0.10-9 5.1.10-10 3.0.10-10 1.8.10-10 1.6.10-10 
Si-32  0.02 7.3.10-9 0.01 4.1.10-9 2.0.10-9 1.2.10-9 7.0.10-10 5.6.10-10 
phosphorus    
       
P-32  1.0 3.1.10-8 0.8 1.9.10-8 9.4.10-9 5.3.10-9 3.1.10-9 2.4.10-9 
P-33  1.0 2.7.10-9 0.8 1.8.10-9 9.1.10-10 5.3.10-10 3.1.10-10 2.4.10-10 
sulphur  
         
S-35 inorganic  1.0 1.3.10-9 1.0 8.7.10-10 4.4.10-10 2.7.10-10 1.6.10-10 1.3.10-10 
S-35 organic  1.0 7.7.10-9 1.0 5.4.1 0-9 2.7.10-9 1.6.10-9 9.5.10-10 7.7.10-10 
chlorine    
       
Cl-36  1.0 9.8.10-9 1.0 6.3.10-9 3.2.10-9 1.9.10-9 1.2.10-9 9.3.10-10 
Cl-38  1.0 1.4.10-9 1.0 7.7.10-10 3.8.10-10 2.2.10-10 1.5.10-10 1.2.10-10 
Cl-39  1.0 9.7.10-10 1.0 5.5.10-10 2.7.10-10 1.6.10-10 1.1.10-10 8.5.10-11 
potassium    
       
K-40  1.0 6.2.10-8 1.0 4.2.10-8 2.1.10-8 1.3.10-8 7.6.10-9 6.2.10-9 - 138 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
K-42  1.0 5.1.10-9 1.0 3.0.10-9 1.5.10-9 8.6.10-10 5.4.10-10 4.3.10-10 
K-43  1.0 2.3.10-9 1.0 1.4.10-9 7.6.10-10 4.7.10-10 3.0.10-10 2.5.1 0-10 
K-44  1.0 1.0.10-9 1.0 5.5.10-10 2.7.10-10 1.6.10-10 1.1.10-10 8.4.10-11 
K-45  1.0 6.2.10-10 1.0 3.5.10-10 1.7.10-10 9.9.10-11 6.8.10-11 5.4.10-11 
calcium    
       
Ca-41  0.6 1.2.10-9 0.4X 5.2.10-10 3.9.10-10 4.8.10-10 5.0.10-10 1.9.10-10 
Ca-45  0.6 1.1.10-8 0.4X 4.9.10-9 2.6.10-9 1.8.10-9 1.3.10-9 7.1.10-10 
Ca-47  0.6 1.3.10-8 0.4X 9.3.10-9 4.9.10-9 3.0.10-9 1.8.10-9 1.6.10-9 
scandium    
       
Sc-43  0.001  1.8.10-9 1.0.10-4 1.2.10-9 6.1.10-10 3.7.10-10 2.3.10-10 1.9.10-10 
Sc-44  0.001  3.5.10-9 1.0.10-4 2.2.10-9 1.2.10-9 7.1.10-10 4.4.10-10 3.5.10-10 
Sc-44m  0.001  2.4.10-8 1.0.10-4 1.6.10-8 8.3.10-9 5.1.10-9 3.1.10-9 2.4.10-9 
Sc-46  0.001  1.1.10-8 1.0.10-4 7.9.10-9 4.4.10-9 2.9.10-9 1.8.10-9 1.5.10-9 
Sc-47  0.001  6.1.10-9 1.0.10-4 3.9.10-9 2.0.10-9 1.2.10-9 6.8.10-10 5.4.10-10 
Sc-48  0.001  1.3.10-8 1.0.10-4 9.3.10-9 5.1.10-9 3.3.10-9 2.1.10-9 1.7.10-9 
Sc-49  0.001  1.0.10-9 1.0.10-4 5.7.10-10 2.8.10-10 1.6.10-10 1.0.10-10 8.2.10-11 
titanium    
       
Ti-44  0.02 5.5.10-8 0.01 3.1.10-8 1.7.1 0-8 1.1.10-8 6.9.10-9 5.8.10-9 
Ti-45  0.02 1.6.10-9 0.01 9.8.10-10 5.0.10-10 3.1.10-10 1.9.10-10 1.5.10-10 
vanadium    
       
V-47  0.02 7.3.10-10 0.01 4.1.10-10 2.0.10-10 1.2.10-10 8.0.10-11 6.3.10-11 
V-48  0.02 1.5.10-8 0.01 1.1.10-8 5.9.10-9 3.9.10-9 2.5.10-9 2.0.10-9 
V-49  0.02 2.2.10-10 0.01 1.4.10-10 6.9.10-11 4.0.10-11 2.3.10-11 1.8.10-11 
chromium    
       
Cr-48  0.2 1.4.10-9 0.1 9.9.10-10 5.7.10-10 3.8.10-10 2.5.10-10 2.0.10-10 
  0.02 1.4.10-9 0.01 9.9.10-10 5.7.10-10 3.8.10-10 2.5.10-10 2.0.10-10 
Cr-49  0.2 6.8.10-10 0.1 3.9.10-10 2.0.10-10 1.1.10-10 7.7.10-11 6.1.10-11 
  0.02 6.8.10-10 0.01 3.9.10-10 2.0.10-10 1.1.10-10 7.7.10-11 6.1.10-11 
Cr-51  0.2 3.5.10-10 0.1 2.3.10-10 1.2.10-10 7.8.10-11 4.8.10-11 3.8.10-11 
  0.02 3.3.10-10 0.01 2.2.10-10 1.2.10-10 7.5.10-11 4.6.10-11 3.7.10-11 
manganese    
       
Mn-51  0.2 1.1.10-9 0.1 6.1.10-10 3.0.10-10 1.8.10-10 1.2.10-10 9.3.10-11 
Mn-52  0.2 1.2.10-8 0.1 8.8.10-9 5.1.10-9 3.4.10-9 2.2.10-9 1.8.10-9 
Mn-52m  0.2 7.8.10-10 0.1 4.4.10-10 2.2.10-10 1.3.10-10 8.8.10-11 6.9.10-11 
Mn-53  0.2 4.1.10-10 0.1 2.2.10-10 1.1.10-10 6.5.10-11 3.7.10-11 3.0.10-11 
Mn-54  0.2 5.4.10-9 0.1 3.1.10-9 1.9.10-9 1.3.10-9 8.7.10-10 7.1.10-10 - 139 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Mn-56  0.2 2.7.10-9 0.1 1.7.10-9 8.5.10-10 5.1.10-10 3.2.10-10 2.5.10-10 
iron   
       
Fe-52  0.6 1.3.10-8 0.2* 9.1.10-9 4.6.10-9 2.8.10-9 1.7.10-9 1.4.10-9 
Fe-55  0.6 7.6.10-9 0.2* 2.4.10-9 1.7.10-9 1.1.10-9 7.7.10-10 3.3.10-10 
Fe-59  0.6 3.9.10-8 0.2* 1.3.10-8 7.5.10-9 4.7.10-9 3.1.10-9 1.8.10-9 
Fe-60  0.6 7.9.10-7 0.2* 2.7.10-7 2.7.10-7 2.5.10-7 2.3.10-7 1.1.10-7 
cobalt    
       
Co-55  0.6 6.0.10-9 0.3* 5.5.10-9 2.9.10-9 1.8.10-9 1.1.10-9 1.0.10-9 
Co-56  0.6 2.5.10-8 0.3* 1.5.10-8 8.8.10-9 5.8.10-9 3.8.10-9 2.5.10-9 
Co-57  0.6 2.9.10-9 0.3* 1.6.10-9 8.9.10-10 5.8.10-10 3.7.10-10 2.1.10-10 
Co-58  0.6 7.3.10-9 0.3* 4.4.10-9 2.6.10-9 1.7.10-9 1.1.10-9 7.4.10-10 
Co-58m  0.6 2.0.10-10 0.3* 1.5.10-10 7.8.10-11 4.7.10-11 2.8.10-11 2.4.10-11 
Co-60  0.6 5.4.10-8 0.3* 2.7.10-8 1.7.10-8 1.1.10-8 7.9.10-9 3.4.10-9 
Co-60m  0.6 2.2.10-11 0.3* 1.2.10-11 5.7.10-12 3.2.10-12 2.2.10-12 1.7.10-12 
Co-61  0.6 8.2.10-10 0.3* 5.1.10-10 2.5.10-10 1.4.10-10 9.2.10-11 7.4.10-11 
Co-62m  0.6 5.3.10-10 0.3* 3.0.10-10 1.5.10-10 8.7.10-11 6.0.10-11 4.7.10-11 
nickel    
       
Ni-56  0.1 5.3.10-9 0.05 4.0.10-9 2.3.10-9 1.6.10-9 1.1.10-9 8.6.10-10 
Ni-57  0.1 6.8.10-9 0.05 4.9.10-9 2.7.10-9 1.7.10-9 1.1.10-9 8.7.10-10 
Ni-59  0.1 6.4.10-10 0.05 3.4.10-10 1.9.10-10 1.1.10-10 7.3.10-11 6.3.10-11 
Ni-63  0.1 1.6.10-9 0.05 8.4.10-10 4.6.10-10 2.8.10-10 1.8.10-10 1.5.10-10 
Ni-65  0.1 2.1.10-9 0.05 1.3.10-9 6.3.10-10 3.8.10-10 2.3.10-10 1.8.10-10 
Ni-66  0.1 3.3.10-8 0.05 2.2.10-8 1.1.10-8 6.6.10-9 3.7.10-9 3.0.10-9 
copper    
       
Cu-60  1.0 7.0.10-10 0.5 4.2.10-10 2.2.10-10 1.3.10-10 8.9.10-11 7.0.10-11 
Cu-61  1.0 7.1.10-10 0.5 7.5.10-10 3.9.10-10 2.3.10-10 1.5.10-10 1.2.10-10 
Cu-64  1.0 5.2.10-10 0.5 8.3.10-10 4.2.10-10 2.5.10-10 1.5.10-10 1.2.10-10 
Cu-67  1.0 2.1.10-9 0.5 2.4.10-9 1.2.10-9 7.2.10-10 4.2.10-10 3.4.10-10 
zinc   
       
Zn-62  1.0 4.2.10-9 0.5 6.5.10-9 3.3.10-9 2.0.10-9 1.2.10-9 9.4.10-10 
Zn-63  1.0 8.7.10-10 0.5 5.2.10-10 2.6.10-10 1.5.10-10 1.0.10-10 7.9.10-11 
Zn-65  1.0 3.6.10-8 0.5 1.6.10-8 9.7.10-9 6.4.10-9 4.5.10-9 3.9.10-9 
Zn-69  1.0 3.5.10-10 0.5 2.2.10-10 1.1.10-10 6.0.10-11 3.9.10-11 3.1.10-11 
Zn-69m  1.0 1.3.10-9 0.5 2.3.10-9 1.2.10-9 7.0.10-10 4.1.10-10 3.3.10-10 
Zn-71m  1.0 1.4.10-9 0.5 1.5.10-9 7.8.10-10 4.8.10-10 3.0.10-10 2.4.10-10 
Zn-72  1.0 8.7.10-9 0.5 8.6.10-9 4.5.10-9 2.8.10-9 1.7.10-9 1.4.10-9 - 140 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
gallium    
       
Ga-65  0.01 4.3.10-10 0.001  2.4.10-10 1.2.10-10 6.9.10-11 4.7.10-11 3.7.10-11 
Ga-66  0.01 1.2.10-8 0.001  7.9.10-9 4.0.10-9 2.5.10-9 1.5.10-9 1.2.10-9 
Ga-67  0.01 1.8.10-9 0.001  1.2.10-9 6.4.10-10 4.0.10-10 2.4.10-10 1.9.10-10 
Ga-68  0.01 1.2.10-9 0.001  6.7.10-10 3.4.10-10 2.0.10-10 1.3.10-10 1.0.10-10 
Ga-70  0.01 3.9.10-10 0.001  2.2.10-10 1.0.10-10 5.9.10-11 4.0.10-11 3.1.10-11 
Ga-72  0.01 1.0.10-8 0.001  6.8.10-9 3.6.10-9 2.2.10-9 1.4.10-9 1.1.10-9 
Ga-73  0.01 3.0.10-9 0.001  1.9.10-9 9.3.10-10 5.5.10-10 3.3.10-10 2.6.10-10 
germanium    
       
Ge-66  1.0 8.3.10-10 1.0 5.3.10-10 2.9.10-10 1.9.10-10 1.3.10-10 1.0.10-10 
Ge-67  1.0 7.7.10-10 1.0 4.2.10-10 2.1.10-10 1.2.10-10 8.2.10-11 6.5.10-11 
Ge-68  1.0 1.2.10-8 1.0 8.0.10-9 4.2.10-9 2.6.10-9 1.6.10-9 1.3.10-9 
Ge-69  1.0 2.0.10-9 1.0 1.3.10-9 7.1.10-10 4.6.10-10 3.0.10-10 2.4.10-10 
Ge-71  1.0 1.2.10-10 1.0 7.8.10-11 4.0.10-11 2.4.10-11 1.5.10-11 1.2.10-11 
Ge-75  1.0 5.5.10-10 1.0 3.1.10-10 1.5.10-10 8.7.10-11 5.9.10-11 4.6.10-11 
Ge-77  1.0 3.0.10-9 1.0 1.8.10-9 9.9.10-10 6.2.10-10 4.1.10-10 3.3.10-10 
Ge-78  1.0 1.2.10-9 1.0 7.0.10-10 3.6.10-10 2.2.10-10 1.5.10-10 1.2.10-10 
arsenic    
       
As-69  1.0 6.6.10-10 0.5 3.7.10-10 1.8.10-10 1.1.10-10 7.2.10-11 5.7.10-11 
As-70  1.0 1.2.10-9 0.5 7.8.10-10 4.1.10-10 2.5.10-10 1.7.10-10 1.3.10-10 
As-71  1.0 2.8.10-9 0.5 2.8.10-9 1.5.10-9 9.3.10-10 5.7.10-10 4.6.10-10 
As-72  1.0 1.1.10-8 0.5 1.2.10-8 6.3.10-9 3.8.10-9 2.3.10-9 1.8.10-9 
As-73  1.0 2.6.10-9 0.5 1.9.10-9 9.3.10-10 5.6.10-10 3.2.10-10 2.6.10-10 
As-74  1.0 1.0.10-8 0.5 8.2.10-9 4.3.10-9 2.6.10-9 1.6.10-9 1.3.10-9 
As-76  1.0 1.0.10-8 0.5 1.1.10-8 5.8.10-9 3.4.10-9 2.0.10-9 1.6.10-9 
As-77  1.0 2.7.10-9 0.5 2.9.10-9 1.5.10-9 8.7.10-10 5.0.10-10 4.0.10-10 
As-78  1.0 2.0.10-9 0.5 1.4.10-9 7.0.10-10 4.1.10-10 2.7.10-10 2.1.10-10 
selenium    
       
Se-70  1.0 1.0.10-9 0.8 7.1.10-10 3.6.10-10 2.2.10-10 1.5.10-10 1.2.10-10 
Se-73  1.0 1.6.10-9 0.8 1.4.10-9 7.4.10-10 4.8.10-10 2.5.10-10 2.1.10-10 
Se-73m  1.0 2.6.10-10 0.8 1.8.10-10 9.5.10-11 5.9.10-11 3.5.10-11 2.8.10-11 
Se-75  1.0 2.0.10-8 0.8 1.3.10-8 8.3.10-9 6.0.10-9 3.1.10-9 2.6.10-9 
Se-79  1.0 4.1.10-8 0.8 2.8.10-8 1.9.10-8 1.4.10-8 4.1.10-9 2.9.10-9 
Se-81  1.0 3.4.10-10 0.8 1.9.10-10 9.0.10-11 5.1.10-11 3.4.10-11 2.7.10-11 
Se-81m  1.0 6.0.10-10 0.8 3.7.10-10 1.8.10-10 1.1.10-10 6.7.10-11 5.3.10-11 
Se-83  1.0 4.6.10-10 0.8 2.9.10-10 1.5.10-10 8.7.10-11 5.9.10-11 4.7.10-11 - 141 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
bromine    
       
Br-74  1.0 9.0.10-10 1.0 5.2.10-10 2.6.10-10 1.5.10-10 1.1.10-10 8.4.10-11 
Br-74m  1.0 1.5.1 0-9 1.0 8.5.10-10 4.3.10-10 2.5.10-10 1.7.10-10 1.4.10-10 
Br-75  1.0 8.5.10-10 1.0 4.9.10-10 2.5.10-10 1.5.10-10 9.9.10-11 7.9.10-11 
Br-76  1.0 4.2.10-9 1.0 2.7.10-9 1.4.10-9 8.7.10-10 5.6.10-10 4.6.10-10 
Br-77  1.0 6.3.10-10 1.0 4.4.10-10 2.5.10-10 1.7.10-10 1.1.10-10 9.6.10-11 
Br-80  1.0 3.9.10-10 1.0 2.1.10-10 1.0.10-10 5.8.10-11 3.9.10-11 3.1.10-11 
Br-80m  1.0 1.4.10-9 1.0 8.0.10-10 3.9.10-10 2.3.10-10 1.4.10-10 1.1.10-10 
Br-82  1.0 3.7.10-9 1.0 2.6.10-9 1.5.10-9 9.5.10-10 6.4.10-10 5.4.10-10 
Br-83  1.0 5.3.10-10 1.0 3.0.10-10 1.4.10-10 8.3.10-11 5.5.10-11 4.3.10-11 
Br-84  1.0 1.0.10-9 1.0 5.8.10-10 2.8.10-10 1.6.10-10 1.1.10-10 8.8.10-11 
rubidium    
       
Rb-79  1.0 5.7.10-10 1.0 3.2.10-10 1.6.10-10 9.2.10-11 6.3.10-11 5.0.10-11 
Rb-81  1.0 5.4.10-10 1.0 3.2.10-10 1.6.10-10 1.0.10-10 6.7.10-11 5.4.10-11 
Rb-81m  1.0 1.1.10-10 1.0 6.2.10-11 3.1.10-11 1.8.10-11 1.2.10-11 9.7.10-12 
Rb-82m  1.0 8.7.10-10 1.0 5.9.10-10 3.4.10-10 2.2.10-10 1.5.10-10 1.3.10-10 
Rb-83  1.0 1.1.10-8 1.0 8.4.10-9 4.9.10-9 3.2.10-9 2.2.10-9 1.9.10-9 
Rb-84  1.0 2.0.10-8 1.0 1.4.10-8 7.9.10-9 5.0.10-9 3.3.10-9 2.8.10-9 
Rb-86  1.0 3.1.10-8 1.0 2.0.10-8 9.9.10-9 5.9.10-9 3.5.10-9 2.8.10-9 
Rb-87  1.0 1.5.10-8 1.0 1.0.10-8 5.2.10-9 3.1.10-9 1.8.10-9 1.5.10-9 
Rb-88  1.0 1.1.10-9 1.0 6.2.10-10 3.0.10-10 1.7.10-10 1.2.10-10 9.0.10-11 
Rb-89  1.0 5.4.10-10 1.0 3.0.10-10 1.5.10-10 8.6.10-11 5.9.10-11 4.7.10-11 
strontium    
       
Sr-80  0.6 3.7.10-9 0.4X 2.3.10-9 1.1.10-9 6.5.10-10 4.2.10-10 3.4.10-10 
Sr-81  0.6 8.4.10-10 0.4X 4.9.10-10 2.4.10-10 1.4.10-10 9.6.10-11 7.7.10-11 
Sr-82  0.6 7.2.10-8 0.4X 4.1.10-8 2.1.10-8 1.3.10-8 8.7.10-9 6.1.10-9 
Sr-83  0.6 3.4.10-9 0.4X 2.7.10-9 1.4.10-9 9.1.10-10 5.7.10-10 4.9.10-10 
Sr-85  0.6 7.7.10-9 0.4X 3.1.10-9 1.7.10-9 1.5.10-9 1.3.10-9 5.6.10-10 
Sr-85m  0.6 4.5.10-11 0.4X 3.0.10-11 1.7.10-11 1.1.10-11 7.8.10-12 6.1.10-12 
Sr-87m  0.6 2.4.10-10 0.4X 1.7.10-10 9.0.10-11 5.6.10-11 3.6.10-11 3.0.10-11 
Sr-89  0.6 3.6.10-8 0.4X 1.8.10-8 8.9.10-9 5.8.10-9 4.0.10-9 2.6.10-9 
Sr-90  0.6 2.3.10-7 0.4X 7.3.10-8 4.7.10-8 6.0.10-8 8.0.10-8 2.8.10-8 
Sr-91  0.6 5.2.10-9 0.4X 4.0.10-9 2.1.10-9 1.2.10-9 7.4.10-10 6.5.10-10 
Sr-92  0.6 3.4.10-9 0.4X 2.7.10-9 1.4.10-9 8.2.10-10 4.8.10-10 4.3.10-10 
yttrium    
       
Y-86  0.001  7.6.10-9 1.0.10-4 5.2.10-9 2.9.10-9 1.9.10-9 1.2.10-9 9.6.10-10 - 142 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Y-86m  0.001  4.5.10-10 1.0.10-4 3.1.10-10 1.7.10-10 1.1.10-10 7.1.10-11 5.6.10-11 
Y-87  0.001  4.6.10-9 1.0.10-4 3.2.10-9 1.8.10-9 1.1.10-9 7.0.10-10 5.5.10-10 
Y-88  0.001  8.1.10-9 1.0.10-4 6.0.10-9 3.5.10-9 2.4.10-9 1.6.10-9 1.3.10-9 
Y-90  0.001  3.1.10-8 1.0.10-4 2.0.10-8 1.0.10-8 5.9.10-9 3.3.10-9 2.7.10-9 
Y-90m  0.001  1.8.10-9 1.0.10-4 1.2.10-9 6.1.10-10 3.7.10-10 2.2.10-10 1.7.10-10 
Y-91  0.001  2.8.10-8 1.0.10-4 1.8.10-8 8.8.10-9 5.2.10-9 2.9.10-9 2.4.10-9 
Y-91m  0.001  9.2.10-11 1.0.10-4 6.0.10-11 3.3.10-11 2.1.10-11 1.4.10-11 1.1.10-11 
Y-92  0.001  5.9.10-9 1.0.10-4 3.6.10-9 1.8.10-9 1.0.10-9 6.2.10-10 4.9.10-10 
Y-93  0.001  1.4.10-8 1.0.10-4 8.5.10-9 4.3.10-9 2.5.10-9 1.4.10-9 1.2.10-9 
Y-94  0.001  9.9.10-10 1.0.10-4 5.5.10-10 2.7.10-10 1.5.10-10 1.0.10-10 8.1.10-11 
Y-95  0.001  5.7.10-10 1.0.10-4 3.1.10-10 1.5.10-10 8.7.10-11 5.9.10-11 4.6.10-11 
zirconium    
       
Zr-86  0.02 6.9.10-9 0.01 4.8.10-9 2.7.10-9 1.7.10-9 1.1.10-9 8.6.10-10 
Zr-88  0.02 2.8.10-9 0.01 2.0.10-9 1.2.10-9 8.0.10-10 5.4.10-10 4.5.10-10 
Zr-89  0.02 6.5.10-9 0.01 4.5.10-9 2.5.10-9 1.6.10-9 9.9.10-10 7.9.10-10 
Zr-93  0.02 1.2.10-9 0.01 7.6.10-10 5.1.10-10 5.8.10-10 8.6.10-10 1.1.10-9 
Zr-95  0.02 8.5.10-9 0.01 5.6.10-9 3.0.10-9 1.9.10-9 1.2.10-9 9.5.10-10 
Zr-97  0.02 2.2.10-8 0.01 1.4.10-8 7.3.10-9 4.4.10-9 2.6.10-9 2.1.10-9 
niobium    
       
Nb-88  0.02 6.7.10-10 0.01 3.8.10-10 1.9.10-10 1.1.10-10 7.9.10-11 6.3.10-11 
Nb-89  0.02 3.0.10-9 0.01 2.0.10-9 1.0.10-9 6.0.10-10 3.4.10-10 2.7.10-10 
Nb-89m  0.02 1.5.10-9 0.01 8.7.10-10 4.4.10-10 2.7.10-10 1.8.10-10 1.4.10-10 
Nb-90  0.02 1.1.10-8 0.01 7.2.10-9 3.9.10-9 2.5.10-9 1.6.10-9 1.2.10-9 
Nb-93m  0.02 1.5.10-9 0.01 9.1.10-10 4.6.10-10 2.7.10-10 1.5.10-10 1.2.10-10 
Nb-94  0.02 1.5.10-8 0.01 9.7.10-9 5.3.10-9 3.4.10-9 2.1.10-9 1.7.10-9 
Nb-95  0.02 4.6.10-9 0.01 3.2.10-9 1.8.10-9 1.1.10-9 7.4.10-10 5.8.10-10 
Nb-95m  0.02 6.4.10-9 0.01 4.1.10-9 2.1.10-9 1.2.10-9 7.1.10-10 5.6.10-10 
Nb-96  0.02 9.2.10-9 0.01 6.3.10-9 3.4.10-9 2.2.10-9 1.4.10-9 1.1.10-9 
Nb-97  0.02 7.7.10-10 0.01 4.5.10-10 2.3.10-10 1.3.10-10 8.7.10-11 6.8.10-11 
Nb-98m  0.02 1.2.10-9 0.01 7.1.10-10 3.6.10-10 2.2.10-10 1.4.10-10 1.1.10-10 
molybdenum    
       
Mo-90  1.0 1.7.10-9 1.0 1.2.10-9 6.3.10-10 4.0.10-10 2.7.10-10 2.2.10-10 
Mo-93  1.0 7.9.10-9 1.0 6.9.10-9 5.0.10-9 4.0.10-9 3.4.10-9 3.1.10-9 
Mo-93m  1.0 8.0.10-10 1.0 5.4.10-10 3.1.10-10 2.0.10-10 1.4.10-10 1.1.10-10 
Mo-99  1.0 5.5.10-9 1.0 3.5.10-9 1.8.10-9 1.1.10-9 7.6.10-10 6.0.10-10 
Mo-101  1.0 4.8.10-10 1.0 2.7.10-10 1.3.10-10 7.6.10-11 5.2.10-11 4.1.10-11 - 143 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
technetium    
       
Tc-93  1.0 2.7.10-10 0.5 2.5.10-10 1.5.10-10 9.8.10-11 6.8.10-11 5.5.10-11 
Tc-93m  1.0 2.0.10-10 0.5 1.3.10-10 7.3.10-11 4.6.10-11 3.2.10-11 2.5.10-11 
Tc-94  1.0 1.2.10-9 0.5 1.0.1 0-9 5.8.10-10 3.7.10-10 2.5.10-10 2.0.10-10 
Tc-94m  1.0 1.3.10-9 0.5 6.5.10-10 3.3.10-10 1.9.10-10 1.3.10-10 1.0.10-10 
Tc-95  1.0 9.9.10-10 0.5 8.7.10-10 5.0.10-10 3.3.10-10 2.3.10-10 1.8.10-10 
Tc-95m  1.0 4.7.10-9 0.5 2.8.10-9 1.6.10-9 1.0.10-9 7.0.10-10 5.6.10-10 
Tc-96  1.0 6.7.10-9 0.5 5.1.10-9 3.0.10-9 2.0.10-9 1.4.10-9 1.1.10-9 
Tc-96m  1.0 1.0.10-10 0.5 6.5.10-11 3.6.10-11 2.3.10-11 1.6.10-11 1.2.10-11 
Tc-97  1.0 9.9.10-10 0.5 4.9.10-10 2.4.10-10 1.4.10-10 8.8.10-11 6.8.10-11 
Tc-97m  1.0 8.7.10-9 0.5 4.1.10-9 2.0.10-9 1.1.10-9 7.0.10-10 5.5.10-10 
Tc-98  1.0 2.3.10-8 0.5 1.2.10-8 6.1.10-9 3.7.10-9 2.5.10-9 2.0.10-9 
Tc-99  1.0 1.0.10-8 0.5 4.8.10-9 2.3.10-9 1.3.10-9 8.2.10-10 6.4.10-10 
Tc-99m  1.0 2.0.10-10 0.5 1.3.10-10 7.2.10-11 4.3.10-11 2.8.10-11 2.2.10-11 
Tc-101  1.0 2.4.10-10 0.5 1.3.10-10 6.1.10-11 3.5.10-11 2.4.10-11 1.9.10-11 
Tc-104  1.0 1.0.10-9 0.5 5.3.10-10 2.6.10-10 1.5.10-10 1.0.10-10 8.0.10-11 
ruthenium    
       
Ru-94  0.1 9.3.10-10 0.05 5.9.10-10 3.1.10-10 1.9.10-10 1.2.10-10 9.4.10-11 
Ru-97  0.1 1.2.10-9 0.05 8.5.10-10 4.7.10-10 3.0.10-10 1.9.10-10 1.5.10-10 
Ru-103  0.1 7.1.10-9 0.05 4.6.10-9 2.4.10-9 1.5.10-9 9.2.10-10 7.3.10-10 
Ru-105  0.1 2.7.10-9 0.05 1.8.10-9 9.1.10-10 5.5.10-10 3.3.10-10 2.6.10-10 
Ru-106  0.1 8.4.10-8 0.05 4.9.10-8 2.5.10-8 1.5.10-8 8.6.10-9 7.0.10-9 
rhodium    
       
Rh-99  0.1 4.2.10-9 0.05 2.9.10-9 1.6.10-9 1.0.10-9 6.5.10-10 5.1.10-10 
Rh-99m  0.1 4.9.10-10 0.05 3.5.10-10 2.0.10-10 1.3.10-10 8.3.10-11 6.6.10-11 
Rh-100  0.1 4.9.10-9 0.05 3.6.10-9 2.0.10-9 1.4.10-9 8.8.10-10 7.1.10-10 
Rh-101  0.1 4.9.10-9 0.05 2.8.10-9 1.6.10-9 1.0.10-9 6.7.10-10 5.5.10-10 
Rh-101m   0.1 1.7.10-9 0.05 1.2.10-9 6.8.10-10 4.4.10-10 2.8.10-10 2.2.10-10 
Rh-102m   0.1 1.9.10-8 0.05 1.0.10-8 6.4.10-9 4.3.10-9 3.0.10-9 2.6.10-9 
Rh-102  0.1 1.2.10-8 0.05 7.4.10-9 3.9.10-9 2.4.10-9 1.4.10-9 1.2.10-9 
Rh-103m   0.1 4.7.10-11 0.05 2.7.10-11 1.3.10-11 7.4.10-12 4.8.10-12 3.8.10-12 
Rh-105  0.1 4.0.10-9 0.05 2.7.10-9 1.3.10-9 8.0.10-10 4.6.10-10 3.7.10-10 
Rh-106m   0.1 1.4.10-9 0.05 9.7.10-10 5.3.10-10 3.3.10-10 2.0.10-10 1.6.10-10 
Rh-107  0.1 2.9.10-10 0.05 1.6.10-10 7.9.10-11 4.5.10-11 3.1.10-11 2.4.10-11 
palladium    
       
Pd-100  0.05 7.4.10-9 0.005  5.2.10-9 2.9.10-9 1.9.10-9 1.2.10-9 9.4.10-10 - 144 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Pd-101  0.05 8.2.10-10 0.005 5.7.10-10 3.1.10-10 1.9.10-10 1.2.10-10 9.4.10-11 
Pd-103  0.05 2.2.10-9 0.005  1.4.10-9 7.2.10-10 4.3.10-10 2.4.10-10 1.9.10-10 
Pd-107  0.05 4.4.10-10 0.005  2.8.10-10 1.4.10-10 8.1.10-11 4.6.10-11 3.7.10-11 
Pd-109  0.05 6.3.10-9 0.005  4.1.10-9 2.0.10-9 1.2.10-9 6.8.10-10 5.5.10-10 
silver    
       
Ag-102  0.1 4.2.10-10 0.05 2.4.10-10 1.2.10-10 7.3.10-11 5.0.10-11 4.0.10-11 
Ag-103  0.1 4.5.10-10 0.05 2.7.10-10 1.4.10-10 8.3.10-11 5.5.10-11 4.3.10-11 
Ag-104  0.1 4.3.10-10 0.05 2.9.10-10 1.7.10-10 1.1.1 0-10 7.5.10-11 6.0.10-11 
Ag-104m   0.1 5.6.10-10 0.05 3.3.10-10 1.7.10-10 1.0.10-10 6.8.10-11 5.4.10-11 
Ag-105  0.1 3.9.10-9 0.05 2.5.10-9 1.4.10-9 9.1.10-10 5.9.10-10 4.7.10-10 
Ag-106  0.1 3.7.10-10 0.05 2.1.10-10 1.0.10-10 6.0.10-11 4.1.10-11 3.2.10-11 
Ag-106m   0.1 9.7.10-9 0.05 6.9.10-9 4.1.10-9 2.8.10-9 1.8.10-9 1.5.10-9 
Ag-108m   0.1 2.1.10-8 0.05 1.1.10-8 6.5.10-9 4.3.10-9 2.8.10-9 2.3.10-9 
Ag-110m   0.1 2.4.10-8 0.05 1.4.10-8 7.8.10-9 5.2.10-9 3.4.10-9 2.8.10-9 
Ag-111  0.1 1.4.10-8 0.05 9.3.10-9 4.6.10-9 2.7.10-9 1.6.10-9 1.3.10-9 
Ag-112  0.1 4.9.10-9 0.05 3.0.10-9 1.5.10-9 8.9.10-10 5.4.10-10 4.3.10-10 
Ag-115  0.1 7.2.10-10 0.05 4.1.10-10 2.0.10-10 1.2.10-10 7.7.10-11 6.0.10-11 
cadmium    
       
Cd-104  0.1 4.2.10-10 0.05 2.9.10-10 1.7.10-10 1.1.10-10 7.2.10-11 5.4.10-11 
Cd-107  0.1 7.1.10-10 0.05 4.6.10-10 2.3.10-10 1.3.10-10 7.8.10-11 6.2.10-11 
Cd-109  0.1 2.1.10-8 0.05 9.5.10-9 5.5.10-9 3.5.10-9 2.4.10-9 2.0.10-9 
Cd-113  0.1 1.0.10-7 0.05 4.8.10-8 3.7.10-8 3.0.10-8 2.6.10-8 2.5.10-8 
Cd-113m  0.1 1.2.10-7 0.05 5.6.10-8 3.9.10-8 2.9.10-8 2.4.10-8 2.3.10-8 
Cd-115  0.1 1.4.10-8 0.05 9.7.10-9 4.9.10-9 2.9.10-9 1.7.10-9 1.4.10-9 
Cd-115m   0.1 4.1.10-8 0.05 1.9.10-8 9.7.10-9 6.9.10-9 4.1.10-9 3.3.10-9 
Cd-117  0.1 2.9.10-9 0.05 1.9.10-9 9.5.10-10 5.7.10-10 3.5.10-10 2.8.10-10 
Cd-117m   0.1 2.6.10-9 0.05 1.7.10-9 9.0.10-10 5.6.10-10 3.5.10-10 2.8.10-10 
indium    
       
In-109  0.04 5.2.10-10 0.02 3.6.10-10 2.0.10-10 1.3.10-10 8.2.10-11 6.6.10-11 
In-110  0.04 1.5.10-9 0.02 1.1.10-9 6.5.10-10 4.4.10-10 3.0.10-10 2.4.10-10 
In-110m   0.04 1.1.10-9 0.02 6.4.10-10 3.2.10-10 1.9.10-10 1.3.10-10 1.0.10-10 
In-111  0.04 2.4.10-9 0.02 1.7.10-9 9.1.10-10 5.9.10-10 3.7.10-10 2.9.10-10 
In-112  0.04 1.2.10-10 0.02 6.7.10-11 3.3.10-11 1.9.10-11 1.3.10-11 1.0.10-11 
In-113m   0.04 3.0.10-10 0.02 1.8.10-10 9.3.10-11 6.2.10-11 3.6.10-11 2.8.10-11 
In-114m   0.04 5.6.10-8 0.02 3.1.10-8 1.5.10-8 9.0.10-9 5.2.10-9 4.1.10-9 
In-115  0.04 1.3.10-7 0.02 6.4.10-8 4.8.10-8 4.3.10-8 3.6.10-8 3.2.10-8 - 145 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
In-115m   0.04 9.6.10-10 0.02 6.0.10-10 3.0.10-10 1.8.10-10 1.1.10-10 8.6.10-11 
In-116m   0.04 5.8.10-10 0.02 3.6.10-10 1.9.10-10 1.2.10-10 8.0.10-11 6.4.10-11 
In-117  0.04 3.3.10-10 0.02 1.9.10-10 9.7.10-11 5.8.10-11 3.9.10-11 3.1.10-11 
In-117m   0.04 1.4.10-9 0.02 8.6.10-10 4.3.10-10 2.5.10-10 1.6.10-10 1.2.10-10 
In-119m   0.04 5.9.10-10 0.02 3.2.10-10 1.6.10-10 8.8.10-11 6.0.10-11 4.7.10-11 
tin   
       
Sn-110  0.04 3.5.10-9 0.02 2.3.10-9 1.2.10-9 7.4.10-10 4.4.10-10 3.5.10-10 
Sn-111  0.04 2.5.10-10 0.02 1.5.10-10 7.4.10-11 4.4.10-11 3.0.10-11 2.3.10-11 
Sn-113  0.04 7.8.10-9 0.02 5.0.10-9 2.6.10-9 1.6.10-9 9.2.10-10 7.3.10-10 
Sn-117m   0.04 7.7.10-9 0.02 5.0.10-9 2.5.10-9 1.5.10-9 8.8.10-10 7.1.10-10 
Sn-119m   0.04 4.1.10-9 0.02 2.5.10-9 1.3.10-9 7.5.10-10 4.3.10-10 3.4.10-10 
Sn-121  0.04 2.6.10-9 0.02 1.7.10-9 8.4.10-10 5.0.10-10 2.8.10-10 2.3.10-10 
Sn-121m   0.04 4.6.10-9 0.02 2.7.10-9 1.4.10-9 8.2.10-10 4.7.10-10 3.8.10-10 
Sn-123  0.04 2.5.10-8 0.02 1.6.10-8 7.8.10-9 4.6.10-9 2.6.10-9 2.1.10-9 
Sn-123m   0.04 4.7.10-10 0.02 2.6.10-10 1.3.10-10 7.3.10-11 4.9.10-11 3.8.10-11 
Sn-125  0.04 3.5.10-8 0.02 2.2.10-8 1.1.10-8 6.7.10-9 3.8.10-9 3.1.10-9 
Sn-126  0.04 5.0.10-8 0.02 3.0.10-8 1.6.10-8 9.8.10-9 5.9.10-9 4.7.10-9 
Sn-127  0.04 2.0.10-9 0.02 1.3.10-9 6.6.10-10 4.0.10-10 2.5.10-10 2.0.10-10 
Sn-128  0.04 1.6.10-9 0.02 9.7.10-10 4.9.10-10 3.0.10-10 1.9.10-10 1.5.10-10 
antimony    
       
Sb-115  0.2 2.5.10-10 0.1 1.5.10-10 7.5.10-11 4.5.10-11 3.1.10-11 2.4.10-11 
Sb-116  0.2 2.7.10-10 0.1 1.6.10-10 8.0.10-11 4.8.10-11 3.3.10-11 2.6.10-11 
Sb-116m   0.2 5.0.10-10 0.1 3.3.10-10 1.9.10-10 1.2.10-10 8.3.10-11 6.7.10-11 
Sb-117  0.2 1.6.10-10 0.1 1.0.10-10 5.6.10-11 3.5.10-11 2.2.10-11 1.8.10-11 
Sb-118m   0.2 1.3.10-9 0.1 1.0.10-9 5.8.10-10 3.9.10-10 2.6.10-10 2.1.10-10 
Sb-119  0.2 8.4.10-10 0.1 5.8.10-10 3.0.10-10 1.8.10-10 1.0.10-10 8.0.10-11 
Sb-120m   0.2 8.1.10-9 0.1 6.0.10-9 3.5.10-9 2.3.10-9 1.6.10-9 1.2.10-9 
Sb-120  0.2 1.7.10-10 0.1 9.4.10-11 4.6.10-11 2.7.10-11 1.8.10-11 1.4.10-11 
Sb-122  0.2 1.8.10-8 0.1 1.2.10-8 6.1.10-9 3.7.10-9 2.1.10-9 1.7.10-9 
Sb-124  0.2 2.5.10-8 0.1 1.6.10-8 8.4.10-9 5.2.10-9 3.2.10-9 2.5.10-9 
Sb-124m’   0.2 8.5.10-11 0.1 4.9.10-11 2.5.10-11 1.5.10-11 1.0.10-11 8.0.10-12 
Sb-125  0.2 1.1.10-8 0.1 6.1.10-9 3.4.10-9 2.1.10-9 1.4.10-9 1.1.10-9 
Sb-126  0.2 2.0.10-8 0.1 1.4.10-8 7.6.10-9 4.9.10-9 3.1.10-9 2.4.10-9 
Sb-126m   0.2 3.9.10-10 0.1 2.2.10-10 1.1.10-10 6.6.10-11 4.5.10-11 3.6.10-11 
Sb-127  0.2 1.7.10-8 0.1 1.2.10-8 5.9.10-9 3.6.10-9 2.1.10-9 1.7.10-9 
Sb-128  0.2 6.3.10-9 0.1 4.5.10-9 2.4.10-9 1.5.10-9 9.5.10-10 7.6.10-10 - 146 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Sb-128m   0.2 3.7.10-10 0.1 2.1.10-10 1.0.10-10 6.0.10-11 4.1.10-11 3.3.10-11 
Sb-129  0.2 4.3.10-9 0.1 2.8.10-9 1.5.10-9 8.8.10-10 5.3.10-10 4.2.10-10 
Sb-130  0.2 9.1.10-10 0.1 5.4.10-10 2.8.10-10 1.7.10-10 1.2.10-10 9.1.10-11 
Sb-131  0.2 1.1.10-9 0.1 7.3.10-10 3.9.10-10 2.1.10-10 1.4.10-10 1.0.10-10 
tellurium    
       
Te-116  0.6 1.4.10-9 0.3 1.0.10-9 5.5.10-10 3.4.10-10 2.1.10-10 1.7.10-10 
Te-121  0.6 3.1.10-9 0.3 2.0.10-9 1.2.10-9 8.0.10-10 5.4.10-10 4.3.10-10 
Te-121m   0.6 2.7.10-8 0.3 1.2.10-8 6.9.10-9 4.2.10-9 2.8.10-9 2.3.10-9 
Te-123  0.6 2.0.10-8 0.3 9.3.10-9 6.9.10-9 5.4.10-9 4.7.10-9 4.4.10-9 
Te-123m   0.6 1.9.10-8 0.3 8.8.10-9 4.9.10-9 2.8.10-9 1.7.10-9 1.4.10-9 
Te-125m   0.6 1.3.10-8 0.3 6.3.10-9 3.3.10-9 1.9.10-9 1.1.10-9 8.7.10-10 
Te-127  0.6 1.5.10-9 0.3 1.2.10-9 6.2.10-10 3.6.10-10 2.1.10-10 1.7.10-10 
Te-127m   0.6 4.1.10-8 0.3 1.8.10-8 9.5.10-9 5.2.10-9 3.0.10-9 2.3.10-9 
Te-129  0.6 7.5.10-10 0.3 4.4.10-10 2.1.10-10 1.2.10-10 8.0.10-11 6.3.10-11 
Te-129m   0.6 4.4.10-8 0.3 2.4.10-8 1.2.10-8 6.6.10-9 3.9.10-9 3.0.10-9 
Te-131  0.6 9.0.10-10 0.3 6.6.10-10 3.5.10-10 1.9.10-10 1.2.10-10 8.7.10-11 
Te-131m   0.6 2.0.10-8 0.3 1.4.10-8 7.8.10-9 4.3.10-9 2.7.10-9 1.9.10-9 
Te-132  0.6 4.8.10-8 0.3 3.0.10-8 1.6.10-8 8.3.10-9 5.3.10-9 3.8.10-9 
Te-133  0.6 8.4.10-10 0.3 6.3.10-10 3.3.10-10 1.6.10-10 1.1.10-10 7.2.10-11 
Te-133m   0.6 3.1.10-9 0.3 2.4.10-9 1.3.10-9 6.3.10-10 4.1.10-10 2.8.10-10 
Te-134  0.6 1.1.10-9 0.3 7.5.10-10 3.9.10-10 2.2.10-10 1.4.10-10 1.1.1 0-10 
iodine    
       
I-120  1.0 3.9.10-9 1.0 2.8.10-9 1.4.10-9 7.2.10-10 4.8.10-10 3.4.10-10 
I-120m   1.0 2.3.10-9 1.0 1.5.10-9 7.8.10-10 4.2.10-10 2.9.10-10 2.1.10-10 
I-121  1.0 6.2.10-10 1.0 5.3.10-10 3.1.10-10 1.7.10-10 1.2.10-10 8.2.10-11 
I-123  1.0 2.2.10-9 1.0 1.9.10-9 1.1.10-9 4.9.10-10 3.3.10-10 2.1.10-10 
I-124  1.0 1.2.10-7 1.0 1.1.10-7 6.3.10-8 3.1.10-8 2.0.10-8 1.3.10-8 
I-125  1.0 5.2.10-8 1.0 5.7.10-8 4.1.10-8 3.1.10-8 2.2.10-8 1.5.10-8 
I-126  1.0 2.1.10-7 1.0 2.1.10-7 1.3.10-7 6.8.10-8 4.5.10-8 2.9.10-8 
I-128  1.0 5.7.10-10 1.0 3.3.10-10 1.6.10-10 8.9.10-11 6.0.10-11 4.6.10-11 
I-129  1.0 1.8.10-7 1.0 2.2.10-7 1.7.10-7 1.9.10-7 1.4.10-7 1.1.10-7 
I-130  1.0 2.1.10-8 1.0 1.8.10-8 9.8.10-9 4.6.10-9 3.0.10-9 2.0.10-9 
I-131  1.0 1.8.10-7 1.0 1.8.10-7 1.0.10-7 5.2.10-8 3.4.10-8 2.2.10-8 
I-132  1.0 3.0.10-9 1.0 2.4.10-9 1.3.10-9 6.2.10-10 4.1.10-10 2.9.10-10 
I-132m   1.0 2.4.10-9 1.0 2.0.10-9 1.1.10-9 5.0.10-10 3.3.10-10 2.2.10-10 
I-133  1.0 4.9.10-8 1.0 4.4.10-8 2.3.10-8 1.0.10-8 6.8.10-9 4.3.10-9 - 147 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
I-134  1.0 1.1.10-9 1.0 7.5.10-10 3.9.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
I-135  1.0 1.0.10-8 1.0 8.9.10-9 4.7.10-9 2.2.10-9 1.4.10-9 9.3.10-10 
caesium    
       
Cs-125  1.0 3.9.10-10 1.0 2.2.10-10 1.1.10-10 6.5.10-11 4.4.10-11 3.5.10-11 
Cs-127  1.0 1.8.10-10 1.0 1.2.10-10 6.6.10-11 4.2.10-11 2.9.10-11 2.4.10-11 
Cs-129  1.0 4.4.10-10 1.0 3.0.10-10 1.7.10-10 1.1.10-10 7.2.10-11 6.0.10-11 
Cs-130  1.0 3.3.10-10 1.0 1.8.10-10 9.0.10-11 5.2.10-11 3.6.10-11 2.8.10-11 
Cs-131  1.0 4.6.10-10 1.0 2.9.1 0-10 1.6.10-10 1.0.10-10 6.9.10-11 5.8.10-11 
Cs-132  1.0 2.7.10-9 1.0 1.8.10-9 1.1.10-9 7.7.10-10 5.7.10-10 5.0.10-10 
Cs-134  1.0 2.6.10-8 1.0 1.6.10-8 1.3.10-8 1.4.10-8 1.9.10-8 1.9.10-8 
Cs-134m   1.0 2.1.10-10 1.0 1.2.10-10 5.9.10-11 3.5.10-11 2.5.10-11 2.0.10-11 
Cs-135  1.0 4.1.10-9 1.0 2.3.10-9 1.7.10-9 1.7.10-9 2.0.10-9 2.0.10-9 
Cs-135m   1.0 1.3.10-10 1.0 8.6.10-11 4.9.10-11 3.2.10-11 2.3.10-11 1.9.10-11 
Cs-136  1.0 1.5.10-8 1.0 9.5.10-9 6.1.10-9 4.4.10-9 3.4.10-9 3.0.10-9 
Cs-137  1.0 2.1.10-8 1.0 1.2.10-8 9.6.10-9 1.0.10-8 1.3.10-8 1.3.10-8 
Cs-138  1.0 1.1.10-9 1.0 5.9.10-10 2.9.10-10 1.7.10-10 1.2.10-10 9.2.10-11 
barium    
       
Ba-126  0.6 2.7.10-9 0.3**  1.7.10-9 8.5.10-10 5.0.10-10 3.1.10-10 2.6.10-10 
Ba-128  0.6 2.0.10-8 0.3**  1.7.10-8 9.0.10-9 5.2.10-9 3.0.10-9 2.7.10-9 
Ba-131  0.6 4.2.10-9 0.3**  2.6.10-9 1.4.10-9 9.4.10-10 6.2.10-10 4.5.10-10 
Ba-131m   0.6 5.8.10-11 0.3**  3.2.10-11 1.6.10-11 9.3.10-12 6.3.10-12 4.9.10-12 
Ba-133  0.6 2.2.10-8 0.3**  6.2.10-9 3.9.10-9 4.6.10-9 7.3.10-9 1.5.10-9 
Ba-133m   0.6 4.2.10-9 0.3**  3.6.10-9 1.8.10-9 1.1.10-9 5.9.10-10 5.4.10-10 
Ba-135m   0.6 3.3.10-9 0.3**  2.9.10-9 1.5.10-9 8.5.10-10 4.7.10-10 4.3.10-10 
Ba-139  0.6 1.4.10-9 0.3**  8.4.10-10 4.1.10-10 2.4.10-10 1.5.10-10 1.2.10-10 
Ba-140  0.6 3.2.1 0-8 0.3**  1.8.10-8 9.2.10-9 5.8.10-9 3.7.10-9 2.6.10-9 
Ba-141  0.6 7.6.10-10 0.3**  4.7.10-10 2.3.10-10 1.3.10-10 8.6.10-11 7.0.10-11 
Ba-142  0.6 3.6.10-10 0.3**  2.2.10-10 1.1.10-10 6.6.10-11 4.3.10-11 3.5.10-11 
lanthanum    
       
La-131  0.005  3.5.10-10 5.0.10-4 2.1.10-10 1.1.10-10 6.6.10-11 4.4.10-11 3.5.10-11 
La-132  0.005  3.8.10-9 5.0.10-4 2.4.10-9 1.3.10-9 7.8.10-10 4.8.10-10 3.9.10-10 
La-135  0.005  2.8.10-10 5.0.10-4 1.9.10-10 1.0.10-10 6.4.10-11 3.9.10-11 3.0.10-11 
La-137  0.005  1.1.10-9 5.0.10-4 4.5.10-10 2.5.10-10 1.6.10-10 1.0.10-10 8.1.10-11 
La-138  0.005  1.3.10-8 5.0.10-4 4.6.10-9 2.7.10-9 1.9.10-9 1.3.10-9 1.1.10-9 
La-140  0.005  2.0.10-8 5.0.10-4 1.3.10-8 6.8.10-9 4.2.10-9 2.5.10-9 2.0.10-9 
La-141  0.005  4.3.10-9 5.0.10-4 2.6.10-9 1.3.1 0-9 7.6.10-10 4.5.10-10 3.6.10-10 - 148 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
La-142  0.005  1.9.10-9 5.0.10-4 1.1.10-9 5.8.10-10 3.5.10-10 2.3.10-10 1.8.10-10 
La-143  0.005  6.9.10-10 5.0.10-4 3.9.10-10 1.9.10-10 1.1.10-10 7.1.10-11 5.6.10-11 
cerium    
       
Ce-134  0.005  2.8.10-8 5.0.10-4 1.8.10-8 9.1.10-9 5.5.10-9 3.2.10-9 2.5.10-9 
Ce-135  0.005  7.0.10-9 5.0.10-4 4.7.10-9 2.6.10-9 1.6.10-9 1.0.10-9 7.9.10-10 
Ce-137  0.005  2.6.10-10 5.0.10-4 1.7.10-10 8.8.10-11 5.4.10-11 3.2.10-11 2.5.10-11 
Ce-137m   0.005  6.1.10-9 5.0.10-4 3.9.10-9 2.0.10-9 1.2.10-9 6.8.10-10 5.4.10-10 
Ce-139  0.005  2.6.10-9 5.0.10-4 1.6.10-9 8.6.10-10 5.4.10-10 3.3.10-10 2.6.10-10 
Ce-141  0.005  8.1.10-9 5.0.10-4 5.1.10-9 2.6.10-9 1.5.10-9 8.8.10-10 7.1.10-10 
Ce-143  0.005  1.2.10-8 5.0.10-4 8.0.10-9 4.1.10-9 2.4.10-9 1.4.10-9 1.1.10-9 
Ce-144  0.005  6.6.10-8 5.0.10-4 3.9.10-8 1.9.10-8 1.1.10-8 6.5.10-9 5.2.10-9 
praseodymium    
       
Pr-136  0.005  3.7.10-10 5.0.10-4 2.1.10-10 1.0.10-10 6.1.10-11 4.2.10-11 3.3.10-11 
Pr-137  0.005  4.1.10-10 5.0.10-4 2.5.10-10 1.3.10-10 7.7.10-11 5.0.10-11 4.0.10-11 
Pr-138m   0.005  1.0.10-9 5.0.10-4 7.4.10-10 4.1.10-10 2.6.10-10 1.6.10-10 1.3.10-10 
Pr-139  0.005  3.2.10-10 5.0.10-4 2.0.10-10 1.1.10-10 6.5.10-11 4.0.10-11 3.1.10-11 
Pr-142  0.005  1.5.10-8 5.0.10-4 9.8.10-9 4.9.10-9 2.9.10-9 1.6.10-9 1.3.10-9 
Pr-142m   0.005  2.0.10-10 5.0.10-4 1.2.10-10 6.2.10-11 3.7.10-11 2.1.10-11 1.7.10-11 
Pr-143  0.005  1.4.10-8 5.0.10-4 8.7.10-9 4.3.10-9 2.6.10-9 1.5.10-9 1.2.10-9 
Pr-144  0.005  6.4.10-10 5.0.10-4 3.5.10-10 1.7.10-10 9.5.10-11 6.5.10-11 5.0.1 0-11 
Pr-145  0.005  4.7.10-9 5.0.10-4 2.9.10-9 1.4.10-9 8.5.10-10 4.9.10-10 3.9.10-10 
Pr-147  0.005  3.9.10-10 5.0.10-4 2.2.10-10 1.1.10-10 6.1.10-11 4.2.10-11 3.3.10-11 
neodymium    
       
Nd-136  0.005  1.0.10-9 5.0.10-4 6.1.10-10 3.1.10-10 1.9.10-10 1.2.10-10 9.9.10-11 
Nd-138  0.005  7.2.10-9 5.0.10-4 4.5.10-9 2.3.10-9 1.3.10-9 8.0.10-10 6.4.10-10 
Nd-139  0.005  2.1.10-10 5.0.10-4 1.2.10-10 6.3.10-11 3.7.10-11 2.5.10-11 2.0.10-11 
Nd-139m   0.005  2.1.10-9 5.0.10-4 1.4.10-9 7.8.10-10 5.0.10-10 3.1.10-10 2.5.10-10 
Nd-141  0.005  7.8.10-11 5.0.10-4 5.0.10-11 2.7.10-11 1.6.10-11 1.0.10-11 8.3.10-12 
Nd-147  0.005  1.2.10-8 5.0.10-4 7.8.10-9 3.9.10-9 2.3.10-9 1.3.10-9 1.1.10-9 
Nd-149  0.005  1.4.10-9 5.0.10-4 8.7.10-10 4.3.10-10 2.6.10-10 1.6.10-10 1.2.10-10 
Nd-151  0.005  3.4.10-10 5.0.10-4 2.0.10-10 9.7.10-11 5.7.10-11 3.8.10-11 3.0.10-11 
promethium    
       
Pm-141  0.005  4.2.10-10 5.0.10-4 2.4.10-10 1.2.10-10 6.8.10-11 4.6.10-11 3.6.10-11 
Pm-143  0.005  1.9.10-9 5.0.10-4 1.2.10-9 6.7.10-10 4.4.10-10 2.9.10-10 2.3.10-10 
Pm-144  0.005  7.6.10-9 5.0.10-4 4.7.10-9 2.7.10-9 1.8.10-9 1.2.10-9 9.7.10-10 
Pm-145  0.005  1.5.10-9 5.0.10-4 6.8.10-10 3.7.10-10 2.3.10-10 1.4.10-10 1.1.10-10 - 149 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Pm-146  0.005  1.0.10-8 5.0.10-4 5.1.10-9 2.8.10-9 1.8.10-9 1.1.10-9 9.0.10-10 
Pm-147  0.005  3.6.10-9 5.0.10-4 1.9.10-9 9.6.10-10 5.7.10-10 3.2.10-10 2.6.10-10 
Pm-148  0.005  3.0.10-8 5.0.10-4 1.9.10-8 9.7.10-9 5.8.10-9 3.3.10-9 2.7.10-9 
Pm-148m   0.005  1.5.10-8 5.0.10-4 1.0.10-8 5.5.10-9 3.5.10-9 2.2.10-9 1.7.10-9 
Pm-149  0.005  1.2.1 0-8 5.0.10-4 7.4.10-9 3.7.10-9 2.2.10-9 1.2.10-9 9.9.10-10 
Pm-150  0.005  2.8.10-9 5.0.10-4 1.7.10-9 8.7.10-10 5.2.10-10 3.2.10-10 2.6.10-10 
Pm-151  0.005  8.0.10-9 5.0.10-4 5.1.10-9 2.6.10-9 1.6.10-9 9.1.10-10 7.3.10-10 
samarium    
       
Sm-141  0.005  4.5.10-10 5.0.10-4 2.5.10-10 1.3.10-10 7.3.10-11 5.0.10-11 3.9.10-11 
Sm-141m   0.005  7.0.10-10 5.0.10-4 4.0.10-10 2.0.10-10 1.2.10-10 8.2.10-11 6.5.10-11 
Sm-142  0.005  2.2.10-9 5.0.10-4 1.3.10-9 6.2.10-10 3.6.10-10 2.4.10-10 1.9.10-10 
Sm-145  0.005  2.4.10-9 5.0.10-4 1.4.10-9 7.3.10-10 4.5.10-10 2.7.10-10 2.1.10-10 
Sm-146  0.005  1.5.10-6 5.0.10-4 1.5.10-7 1.0.10-7 7.0.10-8 5.8.10-8 5.4.10-8 
Sm-147  0.005  1.4.10-6 5.0.10-4 1.4.10-7 9.2.10-8 6.4.10-8 5.2.10-8 4.9.10-8 
Sm-151  0.005  1.5.10-9 5.0.10-4 6.4.10-10 3.3.10-10 2.0.10-10 1.2.10-10 9.8.10-11 
Sm-153  0.005  8.4.10-9 5.0.10-4 5.4.10-9 2.7.10-9 1.6.10-9 9.2.10-10 7.4.10-10 
Sm-155  0.005  3.6.10-10 5.0.10-4 2.0.10-10 9.7.10-11 5.5.10-11 3.7.10-11 2.9.10-11 
Sm-156  0.005  2.8.10-9 5.0.10-4 1.8.10-9 9.0.10-10 5.4.10-10 3.1.10-10 2.5.10-10 
europium    
       
Eu-145  0.005  5.1.10-9 5.0.10-4 3.7.10-9 2.1.10-9 1.4.10-9 9.4.10-10 7.5.10-10 
Eu-146  0.005  8.5.10-9 5.0.10-4 6.2.10-9 3.6.10-9 2.4.10-9 1.6.10-9 1.3.10-9 
Eu-147  0.005  3.7.10-9 5.0.10-4 2.5.10-9 1.4.10-9 8.9.10-10 5.6.10-10 4.4.10-10 
Eu-148  0.005  8.5.10-9 5.0.10-4 6.0.10-9 3.5.10-9 2.4.10-9 1.6.10-9 1.3.10-9 
Eu-149  0.005  9.7.10-10 5.0.10-4 6.3.10-10 3.4.10-10 2.1.10-10 1.3.10-10 1.0.10-10 
Eu-150  0.005  1.3.10-8 5.0.10-4 5.7.10-9 3.4.10-9 2.3.10-9 1.5.10-9 1.3.10-9 
Eu-150m   0.005  4.4.10-9 5.0.10-4 2.8.10-9 1.4.10-9 8.2.10-10 4.7.10-10 3.8.10-10 
Eu-152  0.005  1.6.10-8 5.0.10-4 7.4.10-9 4.1.10-9 2.6.10-9 1.7.10-9 1.4.10-9 
Eu-152m   0.005  5.7.10-9 5.0.10-4 3.6.10-9 1.8.10-9 1.1.10-9 6.2.10-10 5.0.1 0-10 
Eu-154  0.005  2.5.10-8 5.0.10-4 1.2.10-8 6.5.10-9 4.1.10-9 2.5.10-9 2.0.10-9 
Eu-155  0.005  4.3.10-9 5.0.10-4 2.2.10-9 1.1.10-9 6.8.10-10 4.0.10-10 3.2.10-10 
Eu-156  0.005  2.2.10-8 5.0.10-4 1.5.10-8 7.5.10-9 4.6.10-9 2.7.10-9 2.2.10-9 
Eu-157  0.005  6.7.10-9 5.0.10-4 4.3.10-9 2.2.10-9 1.3.10-9 7.5.10-10 6.0.10-10 
Eu-158  0.005  1.1.10-9 5.0.10-4 6.2.10-10 3.1.10-10 1.8.10-10 1.2.10-10 9.4.10-11 
gadolinium    
       
Gd-145  0.005  4.5.10-10 5.0.10-4 2.6.10-10 1.3.10-10 8.1.10-11 5.6.10-11 4.4.10-11 
Gd-146  0.005  9.4.10-9 5.0.10-4 6.0.10-9 3.2.10-9 2.0.10-9 1.2.10-9 9.6.10-10 - 150 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Gd-147  0.005  4.5.10-9 5.0.10-4 3.2.10-9 1.8.10-9 1.2.10-9 7.7.10-10 6.1.10-10 
Gd-148  0.005  1.7.10-6 5.0.10-4 1.6.10-7 1.1.10-7 7.3.10-8 5.9.10-8 5.6.10-8 
Gd-149  0.005  4.0.10-9 5.0.10-4 2.7.10-9 1.5.10-9 9.3.10-10 5.7.10-10 4.5.10-10 
Gd-151  0.005  2.1.10-9 5.0.10-4 1.3.10-9 6.8.10-10 4.2.10-10 2.4.10-10 2.0.10-10 
Gd-152  0.005  1.2.10-6 5.0.10-4 1.2.10-7 7.7.10-8 5.3.10-8 4.3.10-8 4.1.10-8 
Gd-153  0.005  2.9.10-9 5.0.10-4 1.8.10-9 9.4.10-10 5.8.10-10 3.4.10-10 2.7.10-10 
Gd-159  0.005  5.7.10-9 5.0.10-4 3.6.10-9 1.8.10-9 1.1.10-9 6.2.10-10 4.9.10-10 
terbium    
       
Tb-147  0.005  1.5.10-9 5.0.10-4 1.0.10-9 5.4.10-10 3.3.10-10 2.0.10-10 1.6.10-10 
Tb-149  0.005  2.4.10-9 5.0.10-4 1.5.10-9 8.0.10-10 5.0.10-10 3.1.10-10 2.5.10-10 
Tb-150  0.005  2.5.10-9 5.0.10-4 1.6.10-9 8.3.10-10 5.1.10-10 3.2.10-10 2.5.10-10 
Tb-151  0.005  2.7.10-9 5.0.10-4 1.9.10-9 1.0.10-9 6.7.10-10 4.2.10-10 3.4.10-10 
Tb-153  0.005  2.3.10-9 5.0.10-4 1.5.10-9 8.2.10-10 5.1.10-10 3.1.10-10 2.5.10-10 
Tb-154  0.005  4.7.10-9 5.0.10-4 3.4.10-9 1.9.10-9 1.3.10-9 8.1.10-10 6.5.10-10 
Tb-155  0.005  1.9.10-9 5.0.10-4 1.3.10-9 6.8.10-10 4.3.10-10 2.6.10-10 2.1.10-10 
Tb-156  0.005  9.0.10-9 5.0.10-4 6.3.10-9 3.5.10-9 2.3.10-9 1.5.10-9 1.2.10-9 
Tb-156m   0.005  1.5.10-9 5.0.10-4 1.0.10-9 5.6.10-10 3.5.10-10 2.2.10-10 1.7.10-10 
Tb-156m’   0.005  8.0.10-10 5.0.10-4 5.2.10-10 2.7.10-10 1.7.10-10 1.0.10-10 8.1.10-11 
Tb-157  0.005  4.9.10-10 5.0.10-4 2.2.10-10 1.1.10-10 6.8.10-11 4.1.10-11 3.4.10-11 
Tb-158  0.005  1.3.10-8 5.0.10-4 5.9.10-9 3.3.10-9 2.1.10-9 1.4.10-9 1.1.10-9 
Tb-160  0.005  1.6.10-8 5.0.10-4 1.0.10-8 5.4.10-9 3.3.10-9 2.0.10-9 1.6.10-9 
Tb-161  0.005  8.3.10-9 5.0.10-4 5.3.10-9 2.7.10-9 1.6.10-9 9.0.10-10 7.2.10-10 
dysprosium    
       
Dy-155  0.005  9.7.10-10 5.0.10-4 6.8.10-10 3.8.10-10 2.5.10-10 1.6.10-10 1.3.10-10 
Dy-157  0.005  4.4.10-10 5.0.10-4 3.1.10-10 1.8.10-10 1.2.10-10 7.7.10-11 6.1.10-11 
Dy-159  0.005  1.0.10-9 5.0.10-4 6.4.10-10 3.4.10-10 2.1.10-10 1.3.10-10 1.0.10-10 
Dy-165  0.005  1.3.10-9 5.0.10-4 7.9.10-10 3.9.10-10 2.3.10-10 1.4.10-10 1.1.10-10 
Dy-166  0.005  1.9.10-8 5.0.10-4 1.2.10-8 6.0.10-9 3.6.10-9 2.0.10-9 1.6.10-9 
holmium    
       
Ho-155  0.005  3.8.10-10 5.0.10-4 2.3.10-10 1.2.10-10 7.1.1 0-11 4.7.10-11 3.7.10-11 
Ho-157  0.005  5.8.10-11 5.0.10-4 3.6.10-11 1.9.10-11 1.2.10-11 8.1.10-12 6.5.10-12 
Ho-159  0.005  7.1.10-11 5.0.10-4 4.3.10-11 2.3.10-11 1.4.10-11 9.9.10-12 7.9.10-12 
Ho-161  0.005  1.4.10-10 5.0.10-4 8.1.10-11 4.2.10-11 2.5.10-11 1.6.10-11 1.3.10-11 
Ho-162  0.005  3.5.10-11 5.0.10-4 2.0.10-11 1.0.10-11 6.0.10-12 4.2.10-12 3.3.10-12 
Ho-162m   0.005  2.4.10-10 5.0.10-4 1.5.10-10 7.9.10-11 4.9.10-11 3.3.10-11 2.6.10-11 
Ho-164  0.005  1.2.10-10 5.0.10-4 6.5.10-11 3.2.10-11 1.8.10-11 1.2.10-11 9.5.10-12 - 151 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Ho-164m   0.005  2.0.10-10 5.0.10-4 1.1.10-10 5.5.10-11 3.2.10-11 2.1.10-11 1.6.10-11 
Ho-166  0.005  1.6.10-8 5.0.10-4 1.0.10-8 5.2.10-9 3.1.10-9 1.7.10-9 1.4.10-9 
Ho-166m   0.005  2.6.10-8 5.0.10-4 9.3.10-9 5.3.10-9 3.5.10-9 2.4.10-9 2.0.1 0-9 
Ho-167  0.005  8.8.10-10 5.0.10-4 5.5.10-10 2.8.10-10 1.7.10-10 1.0.10-10 8.3.10-11 
erbium    
       
Er-161  0.005  6.5.10-10 5.0.10-4 4.4.10-10 2.4.10-10 1.6.10-10 1.0.10-10 8.0.10-11 
Er-165  0.005  1.7.10-10 5.0.10-4 1.1.10-10 6.2.10-11 3.9.10-11 2.4.10-11 1.9.10-11 
Er-169  0.005  4.4.10-9 5.0.10-4 2.8.10-9 1.4.10-9 8.2.10-10 4.7.10-10 3.7.10-10 
Er-171  0.005  4.0.10-9 5.0.10-4 2.5.10-9 1.3.10-9 7.6.10-10 4.5.10-10 3.6.10-10 
Er-172  0.005  1.0.10-8 5.0.10-4 6.8.10-9 3.5.10-9 2.1.10-9 1.3.10-9 1.0.10-9 
thulium    
       
Tm-162  0.005  2.9.10-10 5.0.10-4 1.7.10-10 8.7.10-11 5.2.10-11 3.6.10-11 2.9.10-11 
Tm-166  0.005  2.1.10-9 5.0.10-4 1.5.10-9 8.3.10-10 5.5.10-10 3.5.10-10 2.8.10-10 
Tm-167  0.005  6.0.10-9 5.0.10-4 3.9.10-9 2.0.10-9 1.2.10-9 7.0.10-10 5.6.10-10 
Tm-170  0.005  1.6.10-8 5.0.10-4 9.8.10-9 4.9.10-9 2.9.10-9 1.6.10-9 1.3.10-9 
Tm-171  0.005  1.5.10-9 5.0.10-4 7.8.10-10 3.9.10-10 2.3.10-10 1.3.10-10 1.1.10-10 
Tm-172  0.005  1.9.10-8 5.0.10-4 1.2.10-8 6.1.10-9 3.7.10-9 2.1.10-9 1.7.10-9 
Tm-173  0.005  3.3.10-9 5.0.10-4 2.1.10-9 1.1.10-9 6.5.10-10 3.8.10-10 3.1.10-10 
Tm-175  0.005  3.1.10-10 5.0.10-4 1.7.10-10 8.6.10-11 5.0.10-11 3.4.10-11 2.7.10-11 
ytterbium    
       
Yb-162  0.005  2.2.10-10 5.0.10-4 1.3.10-10 6.9.10-11 4.2.10-11 2.9.10-11 2.3.1 0-11 
Yb-166  0.005  7.7.10-9 5.0.10-4 5.4.10-9 2.9.10-9 1.9.10-9 1.2.10-9 9.5.10-10 
Yb-167  0.005  7.0.10-11 5.0.10-4 4.1.10-11 2.1.10-11 1.2.10-11 8.4.10-12 6.7.10-12 
Yb-169  0.005  7.1.10-9 5.0.10-4 4.6.10-9 2.4.10-9 1.5.10-9 8.8.10-10 7.1.10-10 
Yb-175  0.005  5.0.10-9 5.0.10-4 3.2.10-9 1.6.10-9 9.5.10-10 5.4.10-10 4.4.10-10 
Yb-177  0.005  1.0.10-9 5.0.10-4 6.8.10-10 3.4.10-10 2.0.10-10 1.1.10-10 8.8.10-11 
Yb-178  0.005  1.4.10-9 5.0.10-4 8.4.10-10 4.2.10-10 2.4.10-10 1.5.10-10 1.2.10-10 
lutetium    
       
Lu-169  0.005  3.5.10-9 5.0.10-4 2.4.10-9 1.4.10-9 8.9.10-10 5.7.10-10 4.6.10-10 
Lu-170  0.005  7.4.10-9 5.0.10-4 5.2.10-9 2.9.10-9 1.9.10-9 1.2.10-9 9.9.10-10 
Lu-171  0.005  5.9.10-9 5.0.10-4 4.0.10-9 2.2.10-9 1.4.10-9 8.5.10-10 6.7.10-10 
Lu-172  0.005  1.0.10-8 5.0.10-4 7.0.10-9 3.9.10-9 2.5.10-9 1.6.10-9 1.3.10-9 
Lu-173  0.005  2.7.10-9 5.0.10-4 1.6.10-9 8.6.10-10 5.3.10-10 3.2.10-10 2.6.10-10 
Lu-174  0.005  3.2.10-9 5.0.10-4 1.7.10-9 9.1.10-10 5.6.10-10 3.3.10-10 2.7.10-10 
Lu-174m   0.005  6.2.10-9 5.0.10-4 3.8.10-9 1.9.10-9 1.1.10-9 6.6.10-10 5.3.10-10 
Lu-176  0.005  2.4.10-8 5.0.10-4 1.1.10-8 5.7.10-9 3.5.10-9 2.2.10-9 1.8.10-9 - 152 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Lu-176m   0.005  2.0.10-9 5.0.10-4 1.2.10-9 6.0.10-10 3.5.10-10 2.1.10-10 1.7.10-10 
Lu-177  0.005  6.1.10-9 5.0.10-4 3.9.10-9 2.0.10-9 1.2.10-9 6.6.10-10 5.3.10-10 
Lu-177m   0.005  1.7.10-8 5.0.10-4 1.1.10-8 5.8.10-9 3.6.10-9 2.1.10-9 1.7.10-9 
Lu-178  0.005  5.9.10-10 5.0.10-4 3.3.10-10 1.6.10-10 9.0.10-11 6.1.10-11 4.7.10-11 
Lu-178m   0.005  4.3.10-10 5.0.10-4 2.4.10-10 1.2.10-10 7.1.10-11 4.9.10-11 3.8.10-11 
Lu-179  0.005  2.4.10-9 5.0.10-4 1.5.10-9 7.5.10-10 4.4.10-10 2.6.10-10 2.1.10-10 
hafnium    
       
Hf-170  0.02 3.9.10-9 0.002  2.7.10-9 1.5.10-9 9.5.10-10 6.0.10-10 4.8.10-10 
Hf-172  0.02 1.9.10-8 0.002  6.1.10-9 3.3.10-9 2.0.10-9 1.3.10-9 1.0.10-9 
Hf-173  0.02 1.9.10-9 0.002  1.3.10-9 7.2.10-10 4.6.10-10 2.8.10-10 2.3.10-10 
Hf-175  0.02 3.8.10-9 0.002  2.4.10-9 1.3.10-9 8.4.10-10 5.2.10-10 4.1.10-10 
Hf-177m   0.02 7.8.10-10 0.002  4.7.10-10 2.5.10-10 1.5.10-10 1.0.10-10 8.1.1 0-11 
Hf-178m   0.02 7.0.10-8 0.002  1.9.10-8 1.1.10-8 7.8.10-9 5.5.10-9 4.7.10-9 
Hf-179m   0.02 1.2.10-8 0.002  7.8.10-9 4.1.10-9 2.6.10-9 1.6.10-9 1.2.10-9 
Hf-180m   0.02 1.4.10-9 0.002  9.7.10-10 5.3.10-10 3.3.10-10 2.1.10-10 1.7.10-10 
Hf-181  0.02 1.2.10-8 0.002  7.4.10-9 3.8.10-9 2.3.10-9 1.4.10-9 1.1.10-9 
Hf-182  0.02 5.6.10-8 0.002  7.9.10-9 5.4.10-9 4.0.10-9 3.3.10-9 3.0.10-9 
Hf-182m   0.02 4.1.10-10 0.002  2.5.10-10 1.3.10-10 7.8.10-11 5.2.10-11 4.2.10-11 
Hf-183  0.02 8.1.10-10 0.002  4.8.10-10 2.4.10-10 1.4.10-10 9.3.10-11 7.3.10-11 
Hf-184  0.02 5.5.10-9 0.002  3.6.10-9 1.8.10-9 1.1.10-9 6.6.10-10 5.2.10-10 
tantalum    
       
Ta-172  0.01 5.5.10-10 0.001  3.2.10-10 1.6.10-10 9.8.10-11 6.6.10-11 5.3.10-11 
Ta-173  0.01 2.0.10-9 0.001  1.3.10-9 6.5.10-10 3.9.10-10 2.4.10-10 1.9.10-10 
Ta-174  0.01 6.2.10-10 0.001  3.7.10-10 1.9.10-10 1.1.10-10 7.2.10-11 5.7.10-11 
Ta-175  0.01 1.6.10-9 0.001  1.1.10-9 6.2.10-10 4.0.10-10 2.6.10-10 2.1.10-10 
Ta-176  0.01 2.4.10-9 0.001  1.7.10-9 9.2.10-10 6.1.10-10 3.9.10-10 3.1.10-10 
Ta-177  0.01 1.0.10-9 0.001  6.9.10-10 3.6.10-10 2.2.10-10 1.3.10-10 1.1.10-10 
Ta-178m   0.01 6.3.10-10 0.001  4.5.10-10 2.4.10-10 1.5.10-10 9.1.10-11 7.2.10-11 
Ta-179  0.01 6.2.10-10 0.001  4.1.10-10 2.2.10-10 1.3.10-10 8.1.10-11 6.5.10-11 
Ta-180  0.01 5.8.10-10 0.001  3.7.10-10 1.9.10-10 1.1.10-10 6.7.10-11 5.4.10-11 
Ta-182  0.01 1.4.10-8 0.001  9.4.10-9 5.0.10-9 3.1.10-9 1.9.10-9 1.5.10-9 
Ta-182m   0.01 1.4.10-10 0.001  7.5.10-11 3.7.10-11 2.1.10-11 1.5.10-11 1.2.10-11 
Ta-183  0.01 1.4.10-8 0.001  9.3.10-9 4.7.10-9 2.8.10-9 1.6.10-9 1.3.10-9 
Ta-184  0.01 6.7.10-9 0.001  4.4.10-9 2.3.10-9 1.4.10-9 8.5.10-10 6.8.10-10 
Ta-185  0.01 8.3.10-10 0.001  4.6.10-10 2.3.10-10 1.3.10-10 8.6.10-11 6.8.10-11 
Ta-186  0.01 3.8.10-10 0.001  2.1.10-10 1.1.10-10 6.1.10-11 4.2.10-11 3.3.10-11 - 153 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
wolfram    
       
W-176  0.6 6.8.10-10 0.3 5.5.10-10 3.0.10-10 2.0.10-10 1.3.10-10 1.0.10-10 
W-177  0.6 4.4.10-10 0.3 3.2.10-10 1.7.10-10 1.1.10-10 7.2.10-11 5.8.10-11 
W-178  0.6 1.8.10-9 0.3 1.4.10-9 7.3.10-10 4.5.10-10 2.7.10-10 2.2.10-10 
W-179  0.6 3.4.10-11 0.3 2.0.10-11 1.0.10-11 6.2.10-12 4.2.10-12 3.3.10-12 
W-181  0.6 6.3.10-10 0.3 4.7.10-10 2.5.10-10 1.6.10-10 9.5.10-11 7.6.10-11 
W-185  0.6 4.4.10-9 0.3 3.3.10-9 1.6.10-9 9.7.10-10 5.5.10-10 4.4.10-10 
W-187  0.6 5.5.1 0-9 0.3 4.3.10-9 2.2.10-9 1.3.10-9 7.8.10-10 6.3.10-10 
W-188  0.6 2.1.10-8 0.3 1.5.10-8 7.7.10-9 4.6.10-9 2.6.10-9 2.1.10-9 
rhenium    
       
Re-177  1.0 2.5.10-10 0.8 1.4.10-10 7.2.10-11 4.1.10-11 2.8.10-11 2.2.10-11 
Re-178  1.0 2.9.10-10 0.8 1.6.10-10 7.9.10-11 4.6.10-11 3.1.10-11 2.5.10-11 
Re-181  1.0 4.2.10-9 0.8 2.8.10-9 1.4.10-9 8.2.10-10 5.4.10-10 4.2.10-10 
Re-182  1.0 1.4.10-8 0.8 8.9.10-9 4.7.10-9 2.8.10-9 1.8.10-9 1.4.10-9 
Re-182m   1.0 2.4.10-9 0.8 1.7.10-9 8.9.10-10 5.2.10-10 3.5.10-10 2.7.10-10 
Re-184  1.0 8.9.10-9 0.8 5.6.10-9 3.0.10-9 1.8.10-9 1.3.10-9 1.0.10-9 
Re-184m   1.0 1.7.10-8 0.8 9.8.10-9 4.9.10-9 2.8.10-9 1.9.10-9 1.5.10-9 
Re-186  1.0 1.9.10-8 0.8 1.1.10-8 5.5.10-9 3.0.10-9 1.9.10-9 1.5.10-9 
Re-186m   1.0 3.0.10-8 0.8 1.6.10-8 7.6.10-9 4.4.10-9 2.8.10-9 2.2.10-9 
Re-187  1.0 6.8.10-11 0.8 3.8.10-11 1.8.10-11 1.0.10-11 6.6.10-12 5.1.10-12 
Re-188  1.0 1.7.10-8 0.8 1.1.10-8 5.4.10-9 2.9.10-9 1.8.10-9 1.4.10-9 
Re-188m   1.0 3.8.10-10 0.8 2.3.10-10 1.1.10-10 6.1.10-11 4.0.10-11 3.0.10-11 
Re-189  1.0 9.8.10-9 0.8 6.2.10-9 3.0.10-9 1.6.10-9 1.0.10-9 7.8.10-10 
osmium    
       
Os-180  0.02 1.6.10-10 0.01 9.8.10-11 5.1.10-11 3.2.10-11 2.2.10-11 1.7.10-11 
Os-181  0.02 7.6.10-10 0.01 5.0.10-10 2.7.10-10 1.7.10-10 1.1.10-10 8.9.10-11 
Os-182  0.02 4.6.10-9 0.01 3.2.10-9 1.7.10-9 1.1.10-9 7.0.10-10 5.6.10-10 
Os-185  0.02 3.8.10-9 0.01 2.6.10-9 1.5.10-9 9.8.10-10 6.5.10-10 5.1.10-10 
Os-189m   0.02 2.1.10-10 0.01 1.3.10-10 6.5.10-11 3.8.10-11 2.2.10-11 1.8.10-11 
Os-191  0.02 6.3.10-9 0.01 4.1.10-9 2.1.10-9 1.2.10-9 7.0.10-10 5.7.10-10 
Os-191m   0.02 1.1.10-9 0.01 7.1.10-10 3.5.10-10 2.1.10-10 1.2.10-10 9.6.10-11 
Os-193  0.02 9.3.10-9 0.01 6.0.10-9 3.0.10-9 1.8.10-9 1.0.10-9 8.1.10-10 
Os-194  0.02 2.9.10-8 0.01 1.7.10-8 8.8.10-9 5.2.10-9 3.0.10-9 2.4.10-9 
iridium    
       
Ir-182  0.02 5.3.10-10 0.01 3.0.10-10 1.5.10-10 8.9.10-11 6.0.10-11 4.8.10-11 
Ir-184  0.02 1.5.10-9 0.01 9.7.10-10 5.2.10-10 3.3.10-10 2.1.10-10 1.7.10-10 - 154 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Ir-185  0.02 2.4.10-9 0.01 1.6.10-9 8.6.10-10 5.3.10-10 3.3.10-10 2.6.10-10 
Ir-186  0.02 3.8.10-9 0.01 2.7.10-9 1.5.10-9 9.6.10-10 6.1.10-10 4.9.10-10 
Ir-186m   0.02 5.8.10-10 0.01 3.6.10-10 2.1.10-10 1.3.10-10 7.7.10-11 6.1.10-11 
Ir-187  0.02 1.1.10-9 0.01 7.3.10-10 3.9.10-10 2.5.10-10 1.5.10-10 1.2.10-10 
Ir-188  0.02 4.6.10-9 0.01 3.3.10-9 1.8.10-9 1.2.10-9 7.9.10-10 6.3.10-10 
Ir-189  0.02 2.5.10-9 0.01 1.7.10-9 8.6.10-10 5.2.10-10 3.0.10-10 2.4.10-10 
Ir-190  0.02 1.0.10-8 0.01 7.1.10-9 3.9.10-9 2.5.10-9 1.6.10-9 1.2.10-9 
Ir-190m’   0.02 9.4.10-10 0.01 6.4.10-10 3.5.10-10 2.3.10-10 1.5.10-10 1.2.10-10 
Ir-190m   0.02 7.9.10-11 0.01 5.0.10-11 2.6.10-11 1.6.10-11 1.0.10-11 8.0.10-12 
Ir-192  0.02 1.3.10-8 0.01 8.7.10-9 4.6.10-9 2.8.10-9 1.7.10-9 1.4.10-9 
Ir-192m   0.02 2.8.10-9 0.01 1.4.10-9 8.3.10-10 5.5.10-10 3.7.10-10 3.1.10-10 
Ir-193m   0.02 3.2.10-9 0.01 2.0.10-9 1.0.10-9 6.0.10-10 3.4.10-10 2.7.10-10 
Ir-194  0.02 1.5.10-8 0.01 9.8.10-9 4.9.10-9 2.9.10-9 1.7.10-9 1.3.10-9 
Ir-194m   0.02 1.7.10-8 0.01 1.1.10-8 6.4.10-9 4.1.10-9 2.6.10-9 2.1.10-9 
Ir-195  0.02 1.2.10-9 0.01 7.3.10-10 3.6.10-10 2.1.10-10 1.3.10-10 1.0.10-10 
Ir-195m   0.02 2.3.10-9 0.01 1.5.10-9 7.3.10-10 4.3.10-10 2.6.10-10 2.1.10-10 
platinum    
       
Pt-186  0.02 7.8.10-10 0.01 5.3.10-10 2.9.10-10 1.8.10-10 1.2.10-10 9.3.10-11 
Pt-188  0.02 6.7.10-9 0.01 4.5.10-9 2.4.10-9 1.5.10-9 9.5.10-10 7.6.10-10 
Pt-189  0.02 1.1.10-9 0.01 7.4.10-10 3.9.10-10 2.5.10-10 1.5.10-10 1.2.10-10 
Pt-191  0.02 3.1.10-9 0.01 2.1.10-9 1.1.10-9 6.9.10-10 4.2.10-10 3.4.10-10 
Pt-193  0.02 3.7.10-10 0.01 2.4.10-10 1.2.10-10 6.9.10-11 3.9.10-11 3.1.10-11 
Pt-193m   0.02 5.2.10-9 0.01 3.4.10-9 1.7.10-9 9.9.10-10 5.6.10-10 4.5.10-10 
Pt-195m   0.02 7.1.10-9 0.01 4.6.10-9 2.3.10-9 1.4.10-9 7.9.10-10 6.3.10-10 
Pt-197  0.02 4.7.10-9 0.01 3.0.10-9 1.5.10-9 8.8.10-10 5.1.10-10 4.0.10-10 
Pt-197m   0.02 1.0.10-9 0.01 6.1.10-10 3.0.10-10 1.8.10-10 1.1.10-10 8.4.10-11 
Pt-199  0.02 4.7.10-10 0.01 2.7.10-10 1.3.10-10 7.5.10-11 5.0.10-11 3.9.10-11 
Pt-200  0.02 1.4.10-8 0.01 8.8.10-9 4.4.10-9 2.6.10-9 1.5.10-9 1.2.10-9 
gold   
       
Au-193  0.2 1.2.10-9 0.1 8.8.10-10 4.6.10-10 2.8.10-10 1.7.10-10 1.3.10-10 
Au-194  0.2 2.9.10-9 0.1 2.2.10-9 1.2.10-9 8.1.10-10 5.3.10-10 4.2.10-10 
Au-195  0.2 2.4.10-9 0.1 1.7.10-9 8.9.10-10 5.4.10-10 3.2.10-10 2.5.10-10 
Au-198  0.2 1.0.10-8 0.1 7.2.10-9 3.7.10-9 2.2.10-9 1.3.10-9 1.0.10-9 
Au-198m   0.2 1.2.10-8 0.1 8.5.10-9 4.4.10-9 2.7.10-9 1.6.10-9 1.3.10-9 
Au-199  0.2 4.5.10-9 0.1 3.1.10-9 1.6.10-9 9.5.10-10 5.5.10-10 4.4.10-10 
Au-200  0.2 8.3.10-10 0.1 4.7.10-10 2.3.10-10 1.3.10-10 8.7.10-11 6.8.10-11 - 155 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Au-200m   0.2 9.2.10-9 0.1 6.6.10-9 3.5.10-9 2.2.10-9 1.3.10-9 1.1.10-9 
Au-201  0.2 3.1.10-10 0.1 1.7.10-10 8.2.10-11 4.6.10-11 3.1.10-11 2.4.10-11 
mercury           
Hg-193 methyl 
mercury  1.0 3.3.10-10 1.0 1.9.10-10 9.8.10-11 5.8.10-11 3.9.10-11 3.1.10-11 
 other org.  0.8 4.7.10-10 0.4 4.4.10-10 2.2.10-10 1.4.10-10 8.3.10-11 6.6.10-11 
 inorganic  0.04 8.5.10-10 0.02 5.5.10-10 2.8.10-10 1.7.10-10 1.0.10-10 8.2.10-11 
Hg-193m  methyl 
mercury  1.0 1.1.10-9 1.0 6.8.10-10 3.7.10-10 2.3.10-10 1.5.10-10 1.3.10-10 
 other org.  0.8 1.6.10-9 0.4 1.8.10-9 9.5.10-10 6.0.10-10 3.7.10-10 3.0.10-10 
 inorganic  0.04 3.6.10-9 0.02 2.4.10-9 1.3.10-9 8.1.10-10 5.0.10-10 4.0.10-10 
Hg-194 methyl 
mercury  1.0 1.3.10-7 1.0 1.2.10-7 8.4.10-8 6.6.10-8 5.5.10-8 5.1.10-8 
 other o rg. 0.8 1.1.10-7 0.4 4.8.10-8 3.5.10-8 2.7.10-8 2.3.10-8 2.1.10-8 
 inorganic  0.04 7.2.10-9 0.02 3.6.10-9 2.6.10-9 1.9.10-9 1.5.10-9 1.4.10-9 
Hg-195 methyl 
mercury  1.0 3.0.10-10 1.0 2.0.10-10 1.0.10-10 6.4.10-11 4.2.10-11 3.4.10-11 
 other org.  0.80 4.6.1 0-10 0.4 4.8.10-10 2.5.10-10 1.5.10-10 9.3.10-11 7.5.10-11 
 inorganic  0.04 9.5.10-10 0.02 6.3.10-10 3.3.10-10 2.0.10-10 1.2.10-10 9.7.10-11 
Hg-195m  methyl 
mercury  1.0 2.1.10-9 1.0 1.3.10-9 6.8.10-10 4.2.10-10 2.7.10-10 2.2.10-10 
 other org.  0.8 2.6.10-9 0.4 2.8.10-9 1.4.10-9 8.7.10-10 5.1.10-10 4.1.10-10 
 inorganic  0.04 5.8.10-9 0.02 3.8.10-9 2.0.10-9 1.2.10-9 7.0.10-10 5.6.10-10 
Hg-197 methyl 
mercury  1.0 9.7.10-10 1.0 6.2.10-10 3.1.10-10 1.9.10-10 1.2.10-10 9.9.10-11 
 other org.  0.8 1.3.10-9 0.4 1.2.10-9 6.1.10-10 3.7.10-10 2.2.10-10 1.7.10-10 
 inorganic  0.04 2.5.10-9 0.02 1.6.10-9 8.3.10-10 5.0.10-10 2.9.10-10 2.3.10-10 
Hg-197m  methyl 
mercury  1.0 1.5.10-9 1.0 9.5.10-10 4.8.10-10 2.9.10-10 1.8.10-10 1.5.10-10 
 other org.  0.8 2.2.10-9 0.4 2.5.10-9 1.2.10-9 7.3.10-10 4.2.10-10 3.4.10-10 
 inorganic  0.04 5.2.10-9 0.02 3.4.10-9 1.7.10-9 1.0.10-9 5.9.10-10 4.7.10-10 
Hg-199m  methyl 
mercury  1.0 3.4.10-10 1.0 1.9.10-10 9.3.10-11 5.3.10-11 3.6.10-11 2.8.10-11 
 other org.  0.8 3.6.10-10 0.4 2.1.10-10 1.0.10-10 5.8.10-11 3.9.10-11 3.1.10-11 
 inorganic  0.04 3.7.10-10 0.02 2.1.10-10 1.0.10-10 5.9.10-11 3.9.10-11 3.1.10-11 
Hg-203 methyl 
mercury  1.0 1.5.10-8 1.0 1.1.10-8 5.7.10-9 3.6.10-9 2.3.10-9 1.9.10-9 
 other org.  0.8 1.3.10-8 0.4 6.4.10-9 3.4.10-9 2.1.10-9 1.3.10-9 1.1.10-9 
 inorganic  0.04 5.5.10-9 0.02 3.6.10-9 1.8.10-9 1.1.10-9 6.7.10-10 5.4.10-10 - 156 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
thallium           
Tl-194  1.0 6.1.10-11 1.0 3.9.10-11 2.2.10-11 1.4.10-11 1.0.10-11 8.1.10-12 
Tl-194m   1.0 3.8.10-10 1.0 2.2.10-10 1.2.10-10 7.0.10-11 4.9.1 0-11 4.0.10-11 
Tl-195  1.0 2.3.10-10 1.0 1.4.10-10 7.5.10-11 4.7.10-11 3.3.10-11 2.7.10-11 
Tl-197  1.0 2.1.10-10 1.0 1.3.10-10 6.7.10-11 4.2.10-11 2.8.10-11 2.3.10-11 
Tl-198  1.0 4.7.10-10 1.0 3.3.10-10 1.9.10-10 1.2.10-10 8.7.10-11 7.3.10-11 
Tl-198m   1.0 4.8.10-10 1.0 3.0.10-10 1.6.10-10 9.7.10-11 6.7.10-11 5.4.10-11 
Tl-199  1.0 2.3.10-10 1.0 1.5.10-10 7.7.10-11 4.8.10-11 3.2.10-11 2.6.10-11 
Tl-200  1.0 1.3.10-9 1.0 9.1.10-10 5.3.10-10 3.5.10-10 2.4.10-10 2.0.10-10 
Tl-201  1.0 8.4.10-10 1.0 5.5.10-10 2.9.10-10 1.8.10-10 1.2.10-10 9.5.10-11 
Tl-202  1.0 2.9.10-9 1.0 2.1.10-9 1.2.10-9 7.9.10-10 5.4.10-10 4.5.10-10 
Tl-204  1.0 1.3.10-8 1.0 8.5.10-9 4.2.10-9 2.5.10-9 1.5.10-9 1.2.10-9 
lead   
       
Pb-195m   0.6 2.6.10-10 0.2 1.6.10-10 8.4.10-11 5.2.10-11 3.5.10-11 2.9.10-11 
Pb-198  0.6 5.9.10-10 0.2 4.8.10-10 2.7.10-10 1.7.10-10 1.1.10-10 1.0.10-10 
Pb-199  0.6 3.5.10-10 0.2 2.6.10-10 1.5.10-10 9.4.10-11 6.3.10-11 5.4.10-11 
Pb-200  0.6 2.5.10-9 0.2 2.0.10-9 1.1.10-9 7.0.10-10 4.4.10-10 4.0.10-10 
Pb-201  0.6 9.4.10-10 0.2 7.8.10-10 4.3.10-10 2.7.10-10 1.8.10-10 1.6.10-10 
Pb-202  0.6 3.4.10-8 0.2 1.6.10-8 1.3.10-8 1.9.10-8 2.7.10-8 8.8.10-9 
Pb-202m   0.6 7.6.10-10 0.2 6.1.10-10 3.5.10-10 2.3.10-10 1.5.10-10 1.3.10-10 
Pb-203  0.6 1.6.10-9 0.2 1.3.10-9 6.8.10-10 4.3.10-10 2.7.10-10 2.4.10-10 
Pb-205  0.6 2.1.10-9 0.2 9.9.10-10 6.2.10-10 6.1.10-10 6.5.10-10 2.8.10-10 
Pb-209  0.6 5.7.10-10 0.2 3.8.10-10 1.9.10-10 1.1.10-10 6.6.10-11 5.7.10-11 
Pb-210  0.6 8.4.10-6 0.2 3.6.10-6 2.2.10-6 1.9.10-6 1.9.10-6 6.9.10-7 
Pb-211  0.6 3.1.10-9 0.2 1.4.10-9 7.1.10-10 4.1.10-10 2.7.10-10 1.8.10-10 
Pb-212  0.6 1.5.10-7 0.2 6.3.10-8 3.3.10-8 2.0.10-8 1.3.10-8 6.0.10-9 
Pb-214  0.6 2.7.10-9 0.2 1.0.10-9 5.2.10-10 3.1.10-10 2.0.10-10 1.4.10-10 
bismuth    
       
Bi-200  0.1 4.2.10-10 0.05 2.7.10-10 1.5.10-10 9.5.10-11 6.4.10-11 5.1.10-11 
Bi-201  0.1 1.0.10-9 0.05 6.7.10-10 3.6.10-10 2.2.10-10 1.4.10-10 1.2.10-10 
Bi-202  0.1 6.4.10-10 0.05 4.4.10-10 2.5.10-10 1.6.10-10 1.1.10-10 8.9.10-11 
Bi-203  0.1 3.5.10-9 0.05 2.5.10-9 1.4.10-9 9.3.10-10 6.0.10-10 4.8.10-10 
Bi-205  0.1 6.1.10-9 0.05 4.5.10-9 2.6.10-9 1.7.10-9 1.1.10-9 9.0.10-10 
Bi-206  0.1 1.4.10-8 0.05 1.0.10-8 5.7.10-9 3.7.10-9 2.4.10-9 1.9.10-9 
Bi-207  0.1 1.0.10-8 0.05 7.1.10-9 3.9.10-9 2.5.10-9 1.6.10-9 1.3.10-9 
Bi-210  0.1 1.5.10-8 0.05 9.7.10-9 4.8.10-9 2.9.10-9 1.6.10-9 1.3.10-9 - 157 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Bi-210m   0.1 2.1.10-7 0.05 9.1.10-8 4.7.10-8 3.0.10-8 1.9.10-8 1.5.10-8 
Bi-212  0.1 3.2.10-9 0.05 1.8.10-9 8.7.10-10 5.0.10-10 3.3.10-10 2.6.10-10 
Bi-213  0.1 2.5.10-9 0.05 1.4.10-9 6.7.10-10 3.9.10-10 2.5.10-10 2.0.10-10 
Bi-214  0.1 1.4.10-9 0.05 7.4.10-10 3.6.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
polonium    
       
Po-203  1.0 2.9.10-10 0.5 2.4.10-10 1.3.10-10 8.5.10-11 5.8.10-11 4.6.10-11 
Po-205  1.0 3.5.10-10 0.5 2.8.10-10 1.6.10-10 1.1.10-10 7.2.10-11 5.8.10-11 
Po-207  1.0 4.4.10-10 0.5 5.7.10-10 3.2.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
Po-210  1.0 2.6.10-5 0.5 8.8.10-6 4.4.10-6 2.6.10-6 1.6.10-6 1.2.10-6 
astatine           
At-207  1.0 2.5.10-9 1.0 1.6.10-9 8.0.10-10 4.8.10-10 2.9.10-10 2.4.10-10 
At-211  1.0 1.2.10-7 1.0 7.8.10-8 3.8.10-8 2.3.10-8 1.3.10-8 1.1.10-8 
francium           
Fr-222  1.0 6.2.10-9 1.0 3.9.10-9 2.0.10-9 1.3.10-9 8.5.10-10 7.2.10-10 
Fr-223  1.0 2.6.10-8 1.0 1.7.10-8 8.3.10-9 5.0.10-9 2.9.10-9 2.4.1 0-9 
radium           
Ra-223  0.6 5.3.10-6 0.3**  1.1.10-6 5.7.10-7 4.5.10-7 3.7.10-7 1.0.10-7 
Ra-224  0.6 2.7.10-6 0.3**  6.6.10-7 3.5.10-7 2.6.10-7 2.0.10-7 6.5.10-8 
Ra-225  0.6 7.1.10-6 0.3**  1.2.10-6 6.1.10-7 5.0.10-7 4.4.10-7 9.9.10-8 
Ra-226  0.6 4.7.10-6 0.3**  9.6.10-7 6.2.10-7 8.0.10-7 1.5.10-6 2.8.10-7 
Ra-227  0.6 1.1.10-9 0.3**  4.3.10-10 2.5.10-10 1.7.10-10 1.3.10-10 8.1.10-11 
Ra-228  0.6 3.0.10-5 0.3**  5.7.10-6 3.4.10-6 3.9.10-6 5.3.10-6 6.9.10-7 
actinium    
       
Ac-224  0.005  1.0.10-8 5.0.1 0-4 5.2.10-9 2.6.10-9 1.5.10-9 8.8.10-10 7.0.10-10 
Ac-225  0.005  4.6.10-7 5.0.10-4 1.8.10-7 9.1.10-8 5.4.10-8 3.0.10-8 2.4.10-8 
Ac-226  0.005  1.4.10-7 5.0.10-4 7.6.10-8 3.8.10-8 2.3.10-8 1.3.10-8 1.0.10-8 
Ac-227  0.005  3.3.10-5 5.0.10-4 3.1.10-6 2.2.10-6 1.5.10-6 1.2.10-6 1.1.10-6 
Ac-228  0.005  7.4.10-9 5.0.10-4 2.8.10-9 1.4.10-9 8.7.10-10 5.3.10-10 4.3.10-10 
thorium    
       
Th-226  0.005  4.4.10-9 5.0.10-4 2.4.10-9 1.2.10-9 6.7.10-10 4.5.10-10 3.5.10-10 
Th-227  0.005  3.0.10-7 5.0.10-4 7.0.10-8 3.6.1 0-8 2.3.10-8 1.5.10-8 8.8.10-9 
Th-228  0.005  3.7.10-6 5.0.10-4 3.7.10-7 2.2.10-7 1.4.10-7 9.4.10-8 7.2.10-8 
Th-229  0.005  1.1.10-5 5.0.10-4 1.0.10-6 7.8.10-7 6.2.10-7 5.3.10-7 4.9.10-7 
Th-230  0.005  4.1.10-6 5.0.10-4 4.1.10-7 3.1.10-7 2.4.10-7 2.2.10-7 2.1.10-7 
Th-231  0.005  3.9.10-9 5.0.10-4 2.5.10-9 1.2.10-9 7.4.10-10 4.2.10-10 3.4.10-10 
Th-232  0.005  4.6.10-6 5.0.10-4 4.5.10-7 3.5.10-7 2.9.10-7 2.5.10-7 2.3.10-7 - 158 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Th-234  0.005  4.0.10-8 5.0.10-4 2.5.10-8 1.3.10-8 7.4.10-9 4.2.10-9 3.4.10-9 
protactin ium   
       
Pa-227  0.005  5.8.10-9 5.0.10-4 3.2.10-9 1.5.10-9 8.7.10-10 5.8.10-10 4.5.10-10 
Pa-228  0.005  1.2.10-8 5.0.10-4 4.8.10-9 2.6.10-9 1.6.10-9 9.7.10-10 7.8.10-10 
Pa-230  0.005  2.6.10-8 5.0.10-4 5.7.10-9 3.1.10-9 1.9.10-9 1.1.10-9 9.2.10-10 
Pa-231  0.005  1.3.10-5 5.0.10-4 1.3.10-6 1.1.10-6 9.2.10-7 8.0.10-7 7.1.10-7 
Pa-232  0.005  7.2.10-9 5.0.10-4 4.3.10-9 2.3.10-9 1.4.10-9 8.9.10-10 7.2.10-10 
Pa-233  0.005  9.7.10-9 5.0.10-4 6.2.10-9 3.2.10-9 1.9.10-9 1.1.10-9 8.7.10-10 
Pa-234  0.005  5.0.10-9 5.0.10-4 3.2.10-9 1.7.10-9 1.0.10-9 6.4.10-10 5.1.10-10 
uranium    
           
U-230  0.04 7.9.10-7 0.02 3.0.10-7 1.5.10-7 1.0.10-7 6.6.10-8 5.6.10-8 
U-231  0.04 3.1.10-9 0.02 2.0.10-9 1.0.10-9 6.1.10-10 3.6.10-10 2.8.10-10 
U-232  0.04 2.5.10-6 0.02 8.2.10-7 5.8.10-7 5.7.10-7 6.4.10-7 3.3.10-7 
U-233  0.04 3.8.10-7 0.02 1.4.10-7 9.2.10-8 7.8.10-8 7.8.10-8 5.1.10-8 
U-234  0.04 3.7.10-7 0.02 1.3.10-7 8.8.10-8 7.4.10-8 7.4.10-8 4.9.10-8 
U-235  0.04 3.5.10-7 0.02 1.3.10-7 8.5.10-8 7.1.10-8 7.0.10-8 4.7.10-8 
U-236  0.04 3.5.10-7 0.02 1.3.10-7 8.4.10-8 7.0.10-8 7.0.10-8 4.7.10-8 
U-237  0.04 8.3.10-9 0.02 5.4.10-9 2.8.10-9 1.6.10-9 9.5.10-10 7.6.10-10 
U-238  0.04 3.4.10-7 0.02 1.2.10-7 8.0.10-8 6.8.10-8 6.7.10-8 4.5.10-8 
U-239  0.04 3.4.10-10 0.02 1.9.10-10 9.3.10-11 5.4.10-11 3.5.10-11 2.7.10-11 
U-240  0.04 1.3.10-8 0.02 8.1.10-9 4.1.10-9 2.4.10-9 1.4.10-9 1.1.10-9 
neptunium    
       
Np-232  0.005  8.7.10-11 5.0.10-4 5.1.10-11 2.7.10-11 1.7.10-11 1.2.10-11 9.7.10-12 
Np-233  0.005  2.1.10-11 5.0.10-4 1.3.10-11 6.6.10-12 4.0.10-12 2.8.10-12 2.2.10-12 
Np-234  0.005  6.2.10-9 5.0.10-4 4.4.10-9 2.4.10-9 1.6.10-9 1.0.10-9 8.1.10-10 
Np-235  0.005  7.1.10-10 5.0.10-4 4.1.10-10 2.0.10-10 1.2.10-10 6.8.10-11 5.3.10-11 
Np-236  0.005  1.9.10-7 5.0.10-4 2.4.10-8 1.8.10-8 1.8.10-8 1.8.10-8 1.7.10-8 
Np-236m   0.005  2.5.10-9 5.0.10-4 1.3.10-9 6.6.10-10 4.0.10-10 2.4.10-10 1.9.10-10 
Np-237  0.005  2.0.10-6 5.0.10-4 2.1.10-7 1.4.10-7 1.1.10-7 1.1.10-7 1.1.10-7 
Np-238  0.005  9.5.10-9 5.0.10-4 6.2.10-9 3.2.10-9 1.9.10-9 1.1.10-9 9.1.10-10 
Np-239  0.005  8.9.10-9 5.0.10-4 5.7.10-9 2.9.10-9 1.7.10-9 1.0.10-9 8.0.10-10 
Np-240  0.005  8.7.10-10 5.0.10-4 5.2.10-10 2.6.10-10 1.6.10-10 1.0.10-10 8.2.10-11 
plutonium    
       
Pu-234  0.005  2.1.10-9 5.0.10-4 1.1.10-9 5.5.10-10 3.3.1 0-10 2.0.10-10 1.6.10-10 
Pu-235  0.005  2.2.10-11 5.0.10-4 1.3.10-11 6.5.10-12 3.9.10-12 2.7.10-12 2.1.10-12 
Pu-236  0.005  2.1.10-6 5.0.10-4 2.2.10-7 1.4.10-7 1.0.10-7 8.5.10-8 8.7.10-8 - 159 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Pu-237  0.005  1.1.10-9 5.0.10-4 6.9.10-10 3.6.10-10 2.2.10-10 1.3.10-10 1.0.10-10 
Pu-238  0.005  4.0.10-6 5.0.10-4 4.0.10-7 3.1.10-7 2.4.10-7 2.2.10-7 2.3.10-7 
Pu-239  0.005  4.2.10-6 5.0.10-4 4.2.10-7 3.3.10-7 2.7.10-7 2.4.10-7 2.5.10-7 
Pu-240  0.005  4.2.10-6 5.0.10-4 4.2.10-7 3.3.10-7 2.7.10-7 2.4.10-7 2.5.10-7 
Pu-241  0.005  5.6.10-8 5.0.10-4 5.7.10-9 5.5.10-9 5.1.10-9 4.8.10-9 4.8.10-9 
Pu-242  0.005  4.0.10-6 5.0.10-4 4.0.10-7 3.2.10-7 2.6.10-7 2.3.10-7 2.4.10-7 
Pu-243  0.005  1.0.10-9 5.0.10-4 6.2.10-10 3.1.10-10 1.8.10-10 1.1.10-10 8.5.10-11 
Pu-244  0.005  4.0.10-6 5.0.10-4 4.1.10-7 3.2.10-7 2.6.10-7 2.3.10-7 2.4.10-7 
Pu-245  0.005  8.0.10-9 5.0.10-4 5.1.10-9 2.6.10-9 1.5.10-9 8.9.10-10 7.2.10-10 
Pu-246  0.005  3.6.10-8 5.0.10-4 2.3.10-8 1.2.10-8 7.1.10-9 4.1.10-9 3.3.10-9 
americium    
       
Am-237  0.005  1.7.10-10 5.0.10-4 1.0.10-10 5.5.10-11 3.3.10-11 2.2.10-11 1.8.10-11 
Am-238  0.005  2.5.10-10 5.0.10-4 1.6.10-10 9.1.10-11 5.9.10-11 4.0.10-11 3.2.10-11 
Am-239  0.005  2.6.10-9 5.0.10-4 1.7.10-9 8.4.10-10 5.1.10-10 3.0.10-10 2.4.10-10 
Am-240  0.005  4.7.10-9 5.0.10-4 3.3.10-9 1.8.10-9 1.2.10-9 7.3.10-10 5.8.10-10 
Am-241  0.005  3.7.10-6 5.0.10-4 3.7.10-7 2.7.10-7 2.2.10-7 2.0.10-7 2.0.10-7 
Am-242  0.005  5.0.10-9 5.0.10-4 2.2.10-9 1.1.10-9 6.4.10-10 3.7.10-10 3.0.10-10 
Am-242m   0.005  3.1.10-6 5.0.10-4 3.0.10-7 2.3.1 0-7 2.0.10-7 1.9.10-7 1.9.10-7 
Am-243  0.005  3.6.10-6 5.0.10-4 3.7.10-7 2.7.10-7 2.2.10-7 2.0.10-7 2.0.10-7 
Am-244  0.005  4.9.10-9 5.0.10-4 3.1.10-9 1.6.10-9 9.6.10-10 5.8.10-10 4.6.10-10 
Am-244m   0.005  3.7.10-10 5.0.10-4 2.0.10-10 9.6.10-11 5.5.10-11 3.7.10-11 2.9.10-11 
Am-245  0.005  6.8.10-10 5.0.10-4 4.5.10-10 2.2.10-10 1.3.10-10 7.9.10-11 6.2.10-11 
Am-246  0.005  6.7.10-10 5.0.10-4 3.8.10-10 1.9.10-10 1.1.10-10 7.3.10-11 5.8.10-11 
Am-246m   0.005  3.9.10-10 5.0.10-4 2.2.10-10 1.1.10-10 6.4.10-11 4.4.10-11 3.4.10-11 
curium    
       
Cm-238  0.005  7.8.10-10 5.0.10-4 4.9.10-10 2.6.10-10 1.6.10-10 1.0.10-10 8.0.10-11 
Cm-240  0.005  2.2.10-7 5.0.10-4 4.8.10-8 2.5.10-8 1.5.10-8 9.2.10-9 7.6.10-9 
Cm-241  0.005  1.1.10-8 5.0.10-4 5.7.10-9 3.0.10-9 1.9.10-9 1.1.10-9 9.1.10-10 
Cm-242  0.005  5.9.10-7 5.0.10-4 7.6.10-8 3.9.10-8 2.4.10-8 1.5.10-8 1.2.10-8 
Cm-243  0.005  3.2.10-6 5.0.10-4 3.3.10-7 2.2.10-7 1.6.10-7 1.4.10-7 1.5.10-7 
Cm-244  0.005  2.9.10-6 5.0.10-4 2.9.10-7 1.9.10-7 1.4.10-7 1.2.10-7 1.2.10-7 
Cm-245  0.005  3.7.10-6 5.0.10-4 3.7.10-7 2.8.10-7 2.3.10-7 2.1.10-7 2.1.10-7 
Cm-246  0.005  3.7.10-6 5.0.10-4 3.7.10-7 2.8.10-7 2.2.10-7 2.1.10-7 2.1.10-7 
Cm-247  0.005  3.4.10-6 5.0.10-4 3.5.10-7 2.6.10-7 2.1.10-7 1.9.10-7 1.9.10-7 
Cm-248  0.005  1.4.10-5 5.0.10-4 1.4.10-6 1.0.10-6 8.4.10-7 7.7.10-7 7.7.10-7 
Cm-249  0.005  3.9.10-10 5.0.10-4 2.2.10-10 1.1.10-10 6.1.10-11 4.0.10-11 3.1.10-11 - 160 - 
 
 Element   f1 hing[Sv/Bq]  f1 hing [Sv/Bq]  
Nuclide   age < 1 year  ≥ 1 
year  1 year  5 years  10 
years  15 years  adult  
Cm-250  0.005  7.8.10-5 5.0.10-4 8.2.10-6 6.0.10-6 4.9.10-6 4.4.10-6 4.4.10-6 
berkelium    
       
Bk-245  0.005  6.1.10-9 5.0.10-4 3.9.10-9 2.0.10-9 1.2.10-9 7.2.10-10 5.7.10-10 
Bk-246  0.005  3.7.10-9 5.0.10-4 2.6.10-9 1.4.10-9 9.4.10-10 6.0.10-10 4.8.10-10 
Bk-247  0.005  8.9.10-6 5.0.10-4 8.6.10-7 6.3.10-7 4.6.10-7 3.8.10-7 3.5.10-7 
Bk-249  0.005  2.2.10-8 5.0.10-4 2.9.10-9 1.9.10-9 1.4.10-9 1.1.10-9 9.7.10-10 
Bk-250  0.005  1.5.10-9 5.0.10-4 8.5.10-10 4.4.10-10 2.7.10-10 1.7.10-10 1.4.10-10 
californium    
       
Cf-244  0.005  9.8.10-10 5.0.10-4 4.8.10-10 2.4.10-10 1.3.10-10 8.9.10-11 7.0.10-11 
Cf-246  0.005  5.0.10-8 5.0.10-4 2.4.10-8 1.2.10-8 7.3.10-9 4.1.10-9 3.3.10-9 
Cf-248  0.005  1.5.10-6 5.0.10-4 1.6.10-7 9.9.10-8 6.0.10-8 3.3.10-8 2.8.10-8 
Cf-249  0.005  9.0.10-6 5.0.10-4 8.7.10-7 6.4.10-7 4.7.10-7 3.8.10-7 3.5.10-7 
Cf-250  0.005  5.7.10-6 5.0.10-4 5.5.10-7 3.7.10-7 2.3.10-7 1.7.10-7 1.6.10-7 
Cf-251  0.005  9.1.10-6 5.0.10-4 8.8.10-7 6.5.10-7 4.7.10-7 3.9.10-7 3.6.10-7 
Cf-252  0.005  5.0.10-6 5.0.10-4 5.1.10-7 3.2.10-7 1.9.10-7 1.0.10-7 9.0.10-8 
Cf-253  0.005  1.0.10-7 5.0.10-4 1.1.10-8 6.0.10-9 3.7.10-9 1.8.10-9 1.4.10-9 
Cf-254  0.005  1.1.10-5 5.0.10-4 2.6.10-6 1.4.10-6 8.4.10-7 5.0.10-7 4.0.10-7 
einsteinium    
       
Es-250  0.005  2.3.10-10 5.0.10-4 9.9.10-11 5.7.10-11 3.7.10-11 2.6.10-11 2.1.10-11 
Es-251  0.005  1.9.10-9 5.0.10-4 1.2.10-9 6.1.10-10 3.7.10-10 2.2.10-10 1.7.10-10 
Es-253  0.005  1.7.10-7 5.0.10-4 4.5.10-8 2.3.10-8 1.4.10-8 7.6.10-9 6.1.10-9 
Es-254  0.005  1.4.10-6 5.0.10-4 1.6.10-7 9.8.10-8 6.0.10-8 3.3.10-8 2.8.10-8 
Es-254m   0.005  5.7.10-8 5.0.10-4 3.0.10-8 1.5.10-8 9.1.10-9 5.2.10-9 4.2.10-9 
fermium    
       
Fm-252  0.005  3.8.10-8 5.0.10-4 2.0.10-8 9.9.10-9 5.9.10-9 3.3.10-9 2.7.10-9 
Fm-253  0.005  2.5.10-8 5.0.10-4 6.7.10-9 3.4.10-9 2.1.10-9 1.1.10-9 9.1.10-10 
Fm-254  0.005  5.6.10-9 5.0.10-4 3.2.10-9 1.6.10-9 9.3.10-10 5.6.10-10 4.4.10-10 
Fm-255  0.005  3.3.10-8 5.0.10-4 1.9.10-8 9.5.10-9 5.6.10-9 3.2.10-9 2.5.10-9 
Fm-257  0.005  9.8.10-7 5.0.10-4 1.1.10-7 6.5.10-8 4.0.10-8 1.9.10-8 1.5.10-8 
mendelevium    
       
Md-257  0.005  3.1.10-9 5.0.10-4 8.8.10-10 4.5.10-10 2.7.10-10 1.5.10-10 1.2.10-10 
Md-258  0.005  6.3.10-7 5.0.10-4 8.9.10-8 5.0.10-8 3.0.10-8 1.6.10-8 1.3.10-8 
 
Legend:  
* - for adults f 1 = 0.1  
** - for adults f 1 = 0.2  
X - for adults f 1 = 0.3  
 
Conversion factors h ing are used for conversion of intake of radionuclides to the committed e ffective dose after - 161 - 
 
 ingestion of radioactive material by an individual from the population.  
Conversion factors h ing for intake via ingestion are provided depending on the absorption type in the digestive 
tract.  
For unidentified radionuclides and chemical f orms of radioactive substances, activity is attributed to those 
radionuclides and their forms for which the table stipulates the highest conversion factor.  - 162 - 
 
 Conversion factors h inh for intake of radioactive aerosols by inhalation by an individual 
from the p opulation  
 
Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
hydrogen           
H-3 F 1.0 2.6.10-11 1.0 2.0.10-11 1.1.10-11 8.2.10-12 5.9.10-12 6.2.10-12 
 M 0.2 3.4.10-10 0.1 2.7.10-10 1.4.10-10 8.2.10-11 5.3.10-11 4.5.10-11 
 S 0.02 1.2.10-9 0.01 1.0.10-9 6.3.10-10 3.8.10-10 2.8.10-10 2.6.10-10 
beryllium           
Be-7 M 0.02 2.5.10-10 0.005  2.1.10-10 1.2.10-10 8.3.10-11 6.2.10-11 5.0.10-11 
 S 0.02 2.8.10-10 0.005  2.4.10-10 1.4.10-10 9.6.10-11 6.8.10-11 5.5.10-11 
Be-10 M 0.02 4.1.10-8 0.005  3.4.10-8 2.0.10-8 1.3.10-8 1.1.10-8 9.6.10-9 
 S 0.02 9.9.10-8 0.005  9.1.10-8 6.1.10-8 4.2.10-8 3.7.10-8 3.5.10-8 
carbon           
C-11 F 1.0 1.0.10-10 1.0 7.0.10-11 3.2.10-11 2.1.10-11 1.3.10-11 1.1.10-11 
 M 0.2 1.5.10-10 0.1 1.1.10-10 4.9.10-11 3.2.10-11 2.1.10-11 1.8.10-11 
 S 0.02 1.6.10-10 0.01 1.1.10-10 5.1.10-11 3.3.10-11 2.2.10-11 1.8.10-11 
C-14 F 1.0 6.1.10-10 1.0 6.7.10-10 3.6.10-10 2.9.10-10 1.9.10-10 2.0.10-10 
 M 0.2 8.3.10-9 0.1 6.6.10-9 4.0.10-9 2.8.10-9 2.5.10-9 2.0.10-9 
 S 0.02 1.9.10-8 0.01 1.7.10-8 1.1.10-8 7.4.10-9 6.4.10-9 5.8.10-9 
fluorine           
F-18 F 1.0 2.6.10-10 1.0 1.9.10-10 9.1.10-11 5.6.10-11 3.4.10-11 2.8.10-11 
 M 1.0 4.1.10-10 1.0 2.9.10-10 1.5.10-10 9.7.10-11 6.9.10-11 5.6.10-11 
 S 1.0 4.2.10-10 1.0 3.1.10-10 1.5.10-10 1.0.10-10 7.3.10-11 5.9.10-11 
sodium           
Na-22 F 1.0 9.7.10-9 1.0 7.3.10-9 3.8.10-9 2.4.10-9 1.5.10-9 1.3.10-9 
Na-24 F 1.0 2.3.10-9 1.0 1.8.10-9 9.3.10-10 5.7.10-10 3.4.10-10 2.7.10-10 
magnesium           
Mg-28 F 1.0 5.3.10-9 0.5 4.7.10-9 2.2.10-9 1.3.10-9 7.3.10-10 6.0.10-10 
 M 1.0 7.3.10-9 0.5 7.2.10-9 3.5.10-9 2.3.10-9 1.5.10-9 1.2.10-9 
aluminium           
Al-26 F 0.02 8.1.10-8 0.01 6.2.10-8 3.2.10-8 2.0.10-8 1.3.10-8 1.1.10-8 
 M 0.02 8.8.10-8 0.01 7.4.10-8 4.4.10-8 2.9.10-8 2.2.10-8 2.0.10-8 
silicon           
Si-31 F 0.02 3.6.10-10 0.01 2.3.10-10 9.5.10-11 5.9.10-11 3.2.10-11 2.7.10-11 
 M 0.02 6.9.10-10 0.01 4.4.10-10 2.0.10-10 1.3.10-10 8.9.10-11 7.4.10-11 
 S 0.02 7.2.10-10 0.01 4.7.10-10 2.2.10-10 1.4.10-10 9.5.10-11 7.9.10-11 - 163 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Si-32 F 0.02 3.0.10-8 0.01 2.3.10-8 1.1.10-8 6.4.10-9 3.8.10-9 3.2.10-9 
 M 0.02 7.1.10-8 0.01 6.0.10-8 3.6.10-8 2.4.10-8 1.9.10-8 1.7.10-8 
 S 0.02 2.8.10-7 0.01 2.7.10-7 1.9.10-7 1.3.10-7 1.1.10-7 1.1.10-7 
phosphorus           
P-32 F 1.0 1.2.10-8 0.8 7.5.10-9 3.2.10-9 1.8.10-9 9.8.10-10 7.7.10-10 
 M 1.0 2.2.10-8 0.8 1.5.10-8 8.0.10-9 5.3.10-9 4.0.10-9 3.4.10-9 
P-33 F 1.0 1.2.10-9 0.8 7.8.10-10 3.0.10-10 2.0.10-10 1.1.10-10 9.2.10-11 
 M 1.0 6.1.10-9 0.8 4.6.10-9 2.8.10-9 2.1.10-9 1.9.10-9 1.5.10-9 
sulphur           
S-35 F 1.0 5.5.10-10 0.8 3.9.10-10 1.8.10-10 1.1.10-10 6.0.10-11 5.1.10-11 
anorg.  M 0.2 5.9.10-9 0.1 4.5.10-9 2.8.10-9 2.0.10-9 1.8.10-9 1.4.10-9 
 S 0.02 7.7.10-9 0.01 6.0.10-9 3.6.10-9 2.6.10-9 2.3.10-9 1.9.10-9 
chlorine           
Cl-36 F 1.0 3.9.10-9 1.0 2.6.10-9 1.1.10-9 7.1.10-10 3.9.10-10 3.3.10-10 
 M 1.0 3.1.10-8 1.0 2.6.10-8 1.5.10-8 1.0.10-8 8.8.10-9 7.3.10-9 
Cl-38 F 1.0 2.9.10-10 1.0 1.9.10-10 8.4.10-11 5.1.10-11 3.0.10-11 2.5.1 0-11 
 M 1.0 4.7.10-10 1.0 3.0.10-10 1.4.10-10 8.5.10-11 5.4.10-11 4.5.10-11 
Cl-39 F 1.0 2.7.10-10 1.0 1.8.10-10 8.4.10-11 5.1.10-11 3.1.10-11 2.5.10-11 
 M 1.0 4.3.10-10 1.0 2.8.10-10 1.3.10-10 8.5.10-11 5.6.10-11 4.6.10-11 
potassium           
K-40 F 1.0 2.4.10-8 1.0 1.7.10-8 7.5.10-9 4.5.10-9 2.5.10-9 2.1.10-9 
K-42 F 1.0 1.6.10-9 1.0 1.0.10-9 4.4.10-10 2.6.10-10 1.5.10-10 1.2.10-10 
K-43 F 1.0 1.3.10-9 1.0 9.7.10-10 4.7.10-10 2.9.10-10 1.7.10-10 1.4.10-10 
K-44 F 1.0 2.2.10-10 1.0 1.4.10-10 6.5.10-11 4.0.10-11 2.4.10-11 2.0.10-11 
K-45 F 1.0 1.5.10-10 1.0 1.0.10-10 4.8.10-11 3.0.10-11 1.8.10-11 1.5.10-11 
calcium           
Ca-41 F 0.6 6.7.10-10 0.4X 3.8.10-10 2.6.10-10 3.3.10-10 3.3.10-10 1.7.10-10 
 M 0.2 4.2.10-10 0.1 2.6.10-10 1.7.10-10 1.7.10-10 1.6.10-10 9.5.10-11 
 S 0.02 6.7.10-10 0.01 6.0.10-10 3.8.10-10 2.4.10-10 1.9.10-10 1.8.10-10 
Ca-45 F 0.6 5.7.10-9 0.4X 3.0.10-9 1.4.10-9 1.0.10-9 7.6.10-10 4.6.10-10 
 M 0.2 1.2.10-8 0.1 8.8.10-9 5.3.10-9 3.9.10-9 3.5.10-9 2.7.10-9 
 S 0.02 1.5.10-8 0.01 1.2.10-8 7.2.10-9 5.1.10-9 4.6.10-9 3.7.10-9 
Ca-47 F 0.6 4.9.10-9 0.4X 3.6.10-9 1.7.10-9 1.1.10-9 6.1.10-10 5.5.10-10 
 M 0.2 1.0.10-8 0.1 7.7.10-9 4.2.10-9 2.9.10-9 2.4.10-9 1.9.10-9 
 S 0.02 1.2.10-8 0.01 8.5.10-9 4.6.10-9 3.3.10-9 2.6.10-9 2.1.10-9 - 164 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
scan dium           
Sc-43 S 0.001  9.3.10-10 1.0.10-4 6.7.10-10 3.3.10-10 2.2.10-10 1.4.10-10 1.1.10-10 
Sc-44 S 0.001  1.6.10-9 1.0.10-4 1.2.10-9 5.6.10-10 3.6.10-10 2.3.10-10 1.8.10-10 
Sc-44m S 0.001  1.1.10-8 1.0.10-4 8.4.10-9 4.2.10-9 2.8.10-9 1.7.10-9 1.4.10-9 
Sc-46 S 0.001  2.8.10-8 1.0.10-4 2.3.10-8 1.4.10-8 9.8.10-9 8.4.10-9 6.8.10-9 
Sc-47 S 0.001  4.0.10-9 1.0.10-4 2.8.10-9 1.5.10-9 1.1.10-9 9.2.10-10 7.3.10-10 
Sc-48 S 0.001  7.8.10-9 1.0.10-4 5.9.10-9 3.1.10-9 2.0.10-9 1.4.10-9 1.1.10-9 
Sc-49 S 0.001  3.9.10-10 1.0.10-4 2.4.10-10 1.1.10-10 7.1.10-11 4.7.10-11 4.0.10-11 
titanium           
Ti-44 F 0.02 3.1.10-7 0.01 2.6.10-7 1.5.10-7 9.6.10-8 6.6.10-8 6.1.10-8 
 M 0.02 1.7.10-7 0.01 1.5.10-7 9.2.10-8 5.9.10-8 4.6.10-8 4.2.10-8 
 S 0.02 3.2.10-7 0.01 3.1.10-7 2.1.10-7 1.5.10-7 1.3.10-7 1.2.10-7 
Ti-45 F 0.02 4.4.10-10 0.01 3.2.10-10 1.5.10-10 9.1.10-11 5.1.10-11 4.2.10-11 
 M 0.02 7.4.10-10 0.01 5.2.10-10 2.5.10-10 1.6.10-10 1.1.10-10 8.8.10-11 
 S 0.02 7.7.10-10 0.01 5.5.10-10 2.7.10-10 1.7.10-10 1.1.10-10 9.3.10-11 
vanadium           
V-47 F 0.02 1.8.10-10 0.01 1.2.10-10 5.6.10-11 3.5.10-11 2.1.10-11 1.7.10-11 
 M 0.02 2.8.10-10 0.01 1.9.10-10 8.6.10-11 5.5.10-11 3.5.10-11 2.9.10-11 
V-48 F 0.02 8.4.10-9 0.01 6.4.10-9 3.3.10-9 2.1.10-9 1.3.10-9 1.1.10-9 
 M 0.02 1.4.10-8 0.01 1.1.10-8 6.3.10-9 4.3.10-9 2.9.10-9 2.4.10-9 
V-49 F 0.02 2.0.10-10 0.01 1.6.10-10 7.7.10-11 4.3.10-11 2.5.10-11 2.1.10-11 
 M 0.02 2.8.10-10 0.01 2.1.10-10 1.1.10-10 6.3.10-11 4.0.10-11 3.4.10-11 
chromium           
Cr-48 F 0.2 7.6.10-10 0.1 6.0.10-10 3.1.10-10 2.0.10-10 1.2.10-10 9.9.10-11 
 M 0.2 1.1.10-9 0.1 9.1.10-10 5.1.10-10 3.4.10-10 2.5.10-10 2.0.10-10 
 S 0.2 1.2.10-9 0.1 9.8.10-10 5.5.10-10 3.7.10-10 2.8.10-10 2.2.10-10 
Cr-49 F 0.2 1.9.10-10 0.1 1.3.10-10 6.0.10-11 3.7.10-11 2.2.10-11 1.9.10-11 
 M 0.2 3.0.10-10 0.1 2.0.10-10 9.5.10-11 6.1.10-11 4.0.10-11 3.3.10-11 
 S 0.2 3.1.10-10 0.1 2.1.10-10 9.9.10-11 6.4.10-11 4.2.10-11 3.5.10-11 
Cr-51 F 0.2 1.7.10-10 0.1 1.3.10-10 6.3.10-11 4.0.10-11 2.4.10-11 2.0.10-11 
 M 0.2 2.6.10-10 0.1 1.9.10-10 1.0.10-10 6.4.10-11 3.9.10-11 3.2.10-11 
 S 0.2 2.6.10-10 0.1 2.1.10-10 1.0.10-10 6.6.10-11 4.5.10-11 3.7.10-11 
manganese           
Mn-51 F 0.2 2.5.10-10 0.1 1.7.10-10 7.5.10-11 4.6.10-11 2.7.10-11 2.3.10-11 
 M 0.2 4.0.10-10 0.1 2.7.10-10 1.2.10-10 7.8.10-11 5.0.10-11 4.1.10-11 - 165 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Mn-52 F 0.2 7.0.10-9 0.1 5.5.10-9 2.9.10-9 1.8.10-9 1.1.10-9 9.4.10-10 
 M 0.2 8.6.10-9 0.1 6.8.10-9 3.7.10-9 2.4.10-9 1.7.10-9 1.4.10-9 
Mn-52m F 0.2 1.9.10-10 0.1 1.3.10-10 6.1.10-11 3.8.10-11 2.2.10-11 1.9.10-11 
 M 0.2 2.8.10-10 0.1 1.9.10-10 8.7.10-11 5.5.10-11 3.4.10-11 2.9.10-11 
Mn-53 F 0.2 3.2.10-10 0.1 2.2.10-10 1.1.10-10 6.0.10-11 3.4.10-11 2.9.10-11 
 M 0.2 4.6.10-10 0.1 3.4.10-10 1.7.10-10 1.0.10-10 6.4.10-11 5.4.10-11 
Mn-54 F 0.2 5.2.10-9 0.1 4.1.10-9 2.2.10-9 1.5.10-9 9.9.10-10 8.5.10-10 
 M 0.2 7.5.10-9 0.1 6.2.10-9 3.8.10-9 2.4.10-9 1.9.10-9 1.5.10-9 
Mn-56 F 0.2 6.9.10-10 0.1 4.9.10-10 2.3.10-10 1.4.10-10 7.8.10-11 6.4.10-11 
 M 0.2 1.1.10-9 0.1 7.8.10-10 3.7.10-10 2.4.10-10 1.5.10-10 1.2.10-10 
iron          
Fe-52 F 0.6 5.2.10-9 0.2* 3.6.10-9 1.5.10-9 8.9.10-10 4.9.10-10 3.9.10-10 
 M 0.2 5.8.10-9 0.1 4.1.10-9 1.9.10-9 1.2.10-9 7.4.10-10 6.0.10-10 
 S 0.02 6.0.10-9 0.01 4.2.10-9 2.0.10-9 1.3.10-9 7.7.10-10 6.3.10-10 
Fe-55 F 0.6 4.2.10-9 0.2* 3.2.10-9 2.2.10-9 1.4.10-9 9.4.10-10 7.7.10-10 
 M 0.2 1.9.10-9 0.1 1.4.10-9 9.9.10-10 6.2.10-10 4.4.10-10 3.8.10-10 
 S 0.02 1.0.10-9 0.01 8.5.10-10 5.0.10-10 2.9.10-10 2.0.10-10 1.8.10-10 
Fe-59 F 0.6 2.1.10-8 0.2* 1.3.10-8 7.1.10-9 4.2.10-9 2.6.10-9 2.2.10-9 
 M 0.2 1.8.10-8 0.1 1.3.10-8 7.9.10-9 5.5.10-9 4.6.10-9 3.7.10-9 
 S 0.02 1.7.10-8 0.01 1.3.10-8 8.1.10-9 5.8.10-9 5.1.10-9 4.0.10-9 
Fe-60 F 0.6 4.4.10-7 0.2* 3.9.10-7 3.5.10-7 3.2.10-7 2.9.10-7 2.8.10-7 
 M 0.2 2.0.10-7 0.1 1.7.10-7 1.6.10-7 1.4.10-7 1.4.10-7 1.4.10-7 
 S 0.02 9.3.10-8 0.01 8.8.10-8 6.7.10-8 5.2.10-8 4.9.10-8 4.9.10-8 
cobalt           
Co-55 F 0.6 2.2.10-9 0.3* 1.8.10-9 9.0.10-10 5.5.10-10 3.1.10-10 2.7.10-10 
 M 0.2 4.1.10-9 0.1 3.1.10-9 1.5.10-9 9.8.10-10 6.1.10-10 5.0.10-10 
 S 0.02 4.6.10-9 0.01 3.3.10-9 1.6.10-9 1.1.10-9 6.6.10-10 5.3.10-10 
Co-56 F 0.6 1.4.10-8 0.3* 1.0.10-8 5.5.10-9 3.5.10-9 2.2.10-9 1.8.10-9 
 M 0.2 2.5.10-8 0.1 2.1.10-8 1.1.10-8 7.4.10-9 5.8.10-9 4.8.10-9 
 S 0.02 2.9.10-8 0.01 2.5.10-8 1.5.10-8 1.0.10-8 8.0.1 0-9 6.7.10-9 
Co-57 F 0.6 1.5.10-9 0.3* 1.1.10-9 5.6.10-10 3.7.10-10 2.3.10-10 1.9.10-10 
 M 0.2 2.8.10-9 0.1 2.2.10-9 1.3.10-9 8.5.10-10 6.7.10-10 5.5.10-10 
 S 0.02 4.4.10-9 0.01 3.7.10-9 2.3.10-9 1.5.10-9 1.2.10-9 1.0.10-9 
Co-58 F 0.6 4.0.10-9 0.3* 3.0.10-9 1.6.10-9 1.0.10-9 6.4.10-10 5.3.10-10 
 M 0.2 7.3.10-9 0.1 6.5.10-9 3.5.10-9 2.4.10-9 2.0.10-9 1.6.10-9 - 166 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 9.0.10-9 0.01 7.5.10-9 4.5.10-9 3.1.10-9 2.6.10-9 2.1.10-9 
Co-58m F 0.6 4.8.10-11 0.3* 3.6.10-11 1.7.10-11 1.1.10-11 5.9.10-12 5.2.10-12 
 M 0.2 1.1.10-10 0.1 7.6.10-11 3.8.10-11 2.4.10-11 1.6.10-11 1.3.10-11 
 S 0.02 1.3.10-10 0.01 9.0.10-11 4.5.10-11 3.0.10-11 2.0.10-11 1.7.10-11 
Co-60 F 0.6 3.0.10-8 0.3* 2.3.10-8 1.4.10-8 8.9.10-9 6.1.10-9 5.2.10-9 
 M 0.2 4.2.10-8 0.1 3.4.10-8 2.1.10-8 1.5.10-8 1.2.10-8 1.0.10-8 
 S 0.02 9.2.10-8 0.01 8.6.10-8 5.9.10-8 4.0.10-8 3.4.10-8 3.1.10-8 
Co-60m F 0.6 4.4.10-12 0.3* 2.8.10-12 1.5.10-12 1.0.10-12 8.3.10-13 6.9.10-13 
 M 0.2 7.1.10-12 0.1 4.7.10-12 2.7.10-12 1.8.10-12 1.5.10-12 1.2.10-12 
 S 0.02 7.6.10-12 0.01 5.1.10-12 2.9.10-12 2.0.10-12 1.7.10-12 1.4.10-12 
Co-61 F 0.6 2.1.10-10 0.3* 1.4.10-10 6.0.10-11 3.8.10-11 2.2.10-11 1.9.10-11 
 M 0.2 4.0.10-10 0.1 2.7.10-10 1.2.10-10 8.2.10-11 5.7.10-11 4.7.10-11 
 S 0.02 4.3.10-10 0.01 2.8.10-10 1.3.10-10 8.8.10-11 6.1.10-11 5.1.10-11 
Co-62m F 0.6 1.4.10-10 0.3* 9.5.10-11 4.5.10-11 2.8.10-11 1.7.10-11 1.4.10-11 
 M 0.2 1.9.10-10 0.1 1.3.10-10 6.1.10-11 3.8.10-11 2.4.10-11 2.0.10-11 
 S 0.02 2.0.10-10 0.01 1.3.10-10 6.3.10-11 4.0.10-11 2.5.10-11 2.1.10-11 
nickel           
Ni-56 F 0.1 3.3.10-9 0.05 2.8.10-9 1.5.10-9 9.3.10-10 5.8.10-10 4.9.10-10 
 M 0.1 4.9.10-9 0.05 4.1.10-9 2.3.10-9 1.5.10-9 1.1.10-9 8.7.10-10 
 S 0.02 5.5.10-9 0.01 4.6.10-9 2.7.10-9 1.8.10-9 1.3.10-9 1.0.10-9 
Ni-57 F 0.1 2.2.10-9 0.05 1.8.10-9 8.9.10-10 5.5.10-10 3.1.10-10 2.5.10-10 
 M 0.1 3.6.10-9 0.05 2.8.10-9 1.5.10-9 9.5.10-10 6.2.10-10 5.0.10-10 
 S 0.02 3.9.10-9 0.01 3.0.10-9 1.5.10-9 1.0.10-9 6.6.10-10 5.3.10-10 
Ni-59 F 0.1 9.6.10-10 0.05 8.1.10-10 4.5.10-10 2.8.10-10 1.9.10-10 1.8.10-10 
 M 0.1 7.9.10-10 0.05 6.2.10-10 3.4.10-10 2.1.10-10 1.4.10-10 1.3.10-10 
 S 0.02 1.7.10-9 0.01 1.5.10-9 9.5.10-10 5.9.10-10 4.6.10-10 4.4.10-10 
Ni-63 F 0.1 2.3.10-9 0.05 2.0.10-9 1.1.10-9 6.7.10-10 4.6.10-10 4.4.10-10 
 M 0.1 2.5.10-9 0.05 1.9.10-9 1.1.10-9 7.0.10-10 5.3.10-10 4.8.10-10 
 S 0.02 4.8.10-9 0.01 4.3.10-9 2.7.10-9 1.7.10-9 1.3.10-9 1.3.10-9 
Ni-65 F 0.1 4.4.10-10 0.05 3.0.10-10 1.4.10-10 8.5.10-11 4.9.10-11 4.1.10-11 
 M 0.1 7.7.10-10 0.05 5.2.10-10 2.4.10-10 1.6.10-10 1.0.10-10 8.5.10-11 
 S 0.02 8.1.10-10 0.01 5.5.10-10 2.6.10-10 1.7.10-10 1.1.10-10 9.0.10-11 
Ni-66 F 0.1 5.7.10-9 0.05 3.8.10-9 1.6.10-9 1.0.10-9 5.1.10-10 4.2.10-10 
 M 0.1 1.3.10-8 0.05 9.4.10-9 4.5.10-9 2.9.10-9 2.0.10-9 1.6.10-9 
 S 0.02 1.5.10-8 0.01 1.0.10-8 5.0.10-9 3.2.10-9 2.2.10-9 1.8.10-9 - 167 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
copper           
Cu-60 F 1.0 2.1.10-10 0.5 1.6.10-10 7.5.10-11 4.6.10-11 2.8.10-11 2.3.10-11 
 M 1.0 3.0.10-10 0.5 2.2.10-10 1.0.10-10 6.5.10-11 4.0.10-11 3.3.10-11 
 S 1.0 3.1.10-10 0.5 2.2.10-10 1.1.10-10 6.7.10-11 4.2.10-11 3.4.10-11 
Cu-61 F 1.0 3.1.10-10 0.5 2.7.10-10 1.3.10-10 7.9.10-11 4.5.10-11 3.7.10-11 
 M 1.0 4.9.10-10 0.5 4.4.10-10 2.1.10-10 1.4.10-10 9.1.10-11 7.4.10-11 
 S 1.0 5.1.10-10 0.5 4.5.10-10 2.2.10-10 1.4.10-10 9.6.10-11 7.8.10-11 
Cu-64 F 1.0 2.8.10-10 0.5 2.7.10-10 1.2.10-10 7.6.10-11 4.2.10-11 3.5.10-11 
 M 1.0 5.5.10-10 0.5 5.4.10-10 2.7.10-10 1.9.10-10 1.4.10-10 1.1.10-10 
 S 1.0 5.8.10-10 0.5 5.7.10-10 2.9.10-10 2.0.10-10 1.3.10-10 1.2.10-10 
Cu-67 F 1.0 9.5.10-10 0.5 8.0.10-10 3.5.10-10 2.2.10-10 1.2.10-10 1.0.10-10 
 M 1.0 2.3.10-9 0.5 2.0.10-9 1.1.10-9 8.1.10-10 6.9.10-10 5.5.10-10 
 S 1.0 2.5.10-9 0.5 2.1.10-9 1.2.10-9 8.9.10-10 7.7.10-10 6.1.10-10 
zinc          
Zn-62 F 1.0 1.7.10-9 0.5 1.7.10-9 7.7.10-10 4.6.10-10 2.5.10-10 2.0.10-10 
 M 0.2 4.5.10-9 0.1 3.5.10-9 1.6.10-9 1.0.10-9 6.0.10-10 5.0.10-10 
 S 0.02 5.1.10-9 0.01 3.4.10-9 1.8.10-9 1.1.10-9 6.6.10-10 5.5.10-10 
Zn-63 F 1.0 2.1.10-10 0.5 1.4.10-10 6.5.10-11 4.0.10-11 2.4.10-11 2.0.10-11 
 M 0.2 3.4.10-10 0.1 2.3.10-10 1.0.10-10 6.6.10-11 4.2.10-11 3.5.10-11 
 S 0.02 3.6.10-10 0.01 2.4.10-10 1.1.10-10 6.9.10-11 4.4.10-11 3.7.10-11 
Zn-65 F 1.0 1.5.10-8 0.5 1.0.10-8 5.7.10-9 3.8.10-9 2.5.10-9 2.2.10-9 
 M 0.2 8.5.10-9 0.1 6.5.10-9 3.7.10-9 2.4.10-9 1.9.10-9 1.6.10-9 
 S 0.02 7.6.10-9 0.01 6.7.10-9 4.4.10-9 2.9.10-9 2.4.10-9 2.0.10-9 
Zn-69 F 1.0 1.1.10-10 0.5 7.4.10-11 3.2.10-11 2.1.10-11 1.2.10-11 1.1.10-11 
 M 0.2 2.2.10-10 0.1 1.4.10-10 6.5.10-11 4.4.10-11 3.1.10-11 2.6.10-11 
 S 0.02 2.3.10-10 0.01 1.5.10-10 6.9.10-11 4.7.10-11 3.4.10-11 2.8.10-11 
Zn-69m F 1.0 6.6.10-10 0.5 6.7.10-10 3.0.10-10 1.8.10-10 9.9.10-11 8.2.10-11 
 M 0.2 2.1.10-9 0.1 1.5.10-9 7.5.10-10 5.0.10-10 3.0.10-10 2.4.10-10 
 S 0.02 2.2.10-9 0.01 1.7.10-9 8.2.10-10 5.4.10-10 3.3.10-10 2.7.10-10 
Zn-71m F 1.0 6.2.10-10 0.5 5.5.10-10 2.6.10-10 1.6.10-10 9.1.10-11 7.4.10-11 
 M 0.2 1.3.10-9 0.1 9.4.10-10 4.6.10-10 2.9.10-10 1.9.10-10 1.5.10-10 
 S 0.02 1.4.10-9 0.01 1.0.10-9 4.9.10-10 3.1.10-10 2.0.10-10 1.6.10-10 
Zn-72 F 1.0 4.3.10-9 0.5 3.5.10-9 1.7.10-9 1.0.10-9 5.9.10-10 4.9.10-10 
 M 0.2 8.8.10-9 0.1 6.5.10-9 3.4.10-9 2.3.10-9 1.5.10-9 1.2.10-9 
 S 0.02 9.7.10-9 0.01 7.0.10-9 3.6.10-9 2.4.10-9 1.6.10-9 1.3.10-9 - 168 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
gallium           
Ga-65 F 0.01 1.1.10-10 0.001  7.3.10-11 3.4.10-11 2.1.10-11 1.3.10-11 1.1.10-11 
 M 0.01 1.6.10-10 0.001  1.1.10-10 4.8.10-11 3.1.10-11 2.0.10-11 1.7.10-11 
Ga-66 F 0.01 2.8.10-9 0.001  2.0.10-9 9.2.10-10 5.7.10-10 3.0.10-10 2.5.10-10 
 M 0.01 4.5.10-9 0.001  3.1.10-9 1.5.10-9 9.2.10-10 5.3.10-10 4.4.10-10 
Ga-67 F 0.01 6.4.10-10 0.001  4.6.10-10 2.2.10-10 1.4.10-10 7.7.10-11 6.4.10-11 
 M 0.01 1.4.10-9 0.001  1.0.10-9 5.0.10-10 3.6.10-10 3.0.10-10 2.4.10-10 
Ga-68 F 0.01 2.9.10-10 0.001  1.9.10-10 8.8.10-11 5.4.10-11 3.1.10-11 2.6.10-11 
 M 0.01 4.6.10-10 0.001  3.1.10-10 1.4.10-10 9.2.10-11 5.9.10-11 4.9.10-11 
Ga-70 F 0.01 9.5.10-11 0.001  6.0.10-11 2.6.10-11 1.6.10-11 1.0.10-11 8.8.10-12 
 M 0.01 1.5.10-10 0.001  9.6.10-11 4.3.10-11 2.8.10-11 1.8.10-11 1.6.10-11 
Ga-72 F 0.01 2.9.10-9 0.001  2.2.10-9 1.0.10-9 6.4.10-10 3.6.10-10 2.9.10-10 
 M 0.01 4.5.10-9 0.001  3.3.10-9 1.6.10-9 1.0.10-9 6.5.10-10 5.3.10-10 
Ga-73 F 0.01 6.7.10-10 0.001  4.5.10-10 2.0.10-10 1.2.10-10 6.4.10-11 5.4.10-11 
 M 0.01 1.2.10-9 0.001  8.4.10-10 4.0.10-10 2.6.10-10 1.7.10-10 1.4.10-10 
germanium           
Ge-66 F 1.0 4.5.10-10 1.0 3.5.10-10 1.8.10-10 1.1.10-10 6.7.10-11 5.4.10-11 
 M 1.0 6.4.10-10 1.0 4.8.10-10 2.5.10-10 1.6.10-10 1.1.10-10 9.1.10-11 
Ge-67 F 1.0 1.7.10-10 1.0 1.1.10-10 4.9.10-11 3.1.10-11 1.8.10-11 1.5.10-11 
 M 1.0 2.5.10-10 1.0 1.6.10-10 7.3.10-11 4.6.1 0-11 2.9.10-11 2.5.10-11 
Ge-68 F 1.0 5.4.10-9 1.0 3.8.10-9 1.8.10-9 1.1.10-9 6.3.10-10 5.2.10-10 
 M 1.0 6.0.10-8 1.0 5.0.10-8 3.0.10-8 2.0.10-8 1.6.10-8 1.4.10-8 
Ge-69 F 1.0 1.2.10-9 1.0 9.0.10-10 4.6.10-10 2.8.10-10 1.7.10-10 1.3.10-10 
 M 1.0 1.8.10-9 1.0 1.4.10-9 7.4.10-10 4.9.10-10 3.6.10-10 2.9.10-10 
Ge-71 F 1.0 6.0.10-11 1.0 4.3.10-11 2.0.10-11 1.1.10-11 6.1.10-12 4.8.10-12 
 M 1.0 1.2.10-10 1.0 8.6.10-11 4.1.10-11 2.4.10-11 1.3.10-11 1.1.10-11 
Ge-75 F 1.0 1.6.10-10 1.0 1.0.10-10 4.3.10-11 2.8.10-11 1.7.10-11 1.5.10-11 
 M 1.0 2.9.10-10 1.0 1.9.10-10 8.9.10-11 6.1.10-11 4.4.10-11 3.6.10-11 
Ge-77 F 1.0 1.3.10-9 1.0 9.5.10-10 4.7.10-10 2.9.10-10 1.7.10-10 1.4.10-10 
 M 1.0 2.3.10-9 1.0 1.7.10-9 8.8.10-10 6.0.10-10 4.5.10-10 3.7.10-10 
Ge-78 F 1.0 4.3.10-10 1.0 2.9.10-10 1.4.10-10 8.9.10-11 5.5.10-11 4.5.10-11 
 M 1.0 7.3.10-10 1.0 5.0.10-10 2.5.10-10 1.6.10-10 1.2.10-10 9.5.10-11 
arsenic           
As-69 M 1.0 2.1.10-10 0.5 1.4.10-10 6.3.10-11 4.0.10-11 2.5.10-11 2.1.10-11 
As-70 M 1.0 5.7.10-10 0.5 4.3.10-10 2.1.10-10 1.3.10-10 8.3.10-11 6.7.10-11 - 169 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
As-71 M 1.0 2.2.10-9 0.5 1.9.10-9 1.0.10-9 6.8.10-10 5.0.10-10 4.0.10-10 
As-72 M 1.0 5.9.10-9 0.5 5.7.10-9 2.7.10-9 1.7.10-9 1.1.10-9 9.0.10-10 
As-73 M 1.0 5.4.10-9 0.5 4.0.10-9 2.3.10-9 1.5.10-9 1.2.10-9 1.0.10-9 
As-74 M 1.0 1.1.10-8 0.5 8.4.10-9 4.7.10-9 3.3.10-9 2.6.10-9 2.1.10-9 
As-76 M 1.0 5.1.10-9 0.5 4.6.10-9 2.2.10-9 1.4.10-9 8.8.10-10 7.4.10-10 
As-77 M 1.0 2.2.10-9 0.5 1.7.10-9 8.9.10-10 6.2.10-10 5.0.10-10 3.9.10-10 
As-78 M 1.0 8.0.10-10 0.5 5.8.10-10 2.7.10-10 1.7.10-10 1.1.10-10 8.9.10-11 
selenium           
Se-70 F 1.0 3.9.10-10 0.8 3.0.10-10 1.5.10-10 9.0.10-11 5.1.10-11 4.2.10-11 
 M 0.2 6.5.10-10 0.1 4.7.10-10 2.3.10-10 1.4.10-10 8.9.10-11 7.3.10-11 
 S 0.02 6.8.10-10 0.01 4.8.10-10 2.3.10-10 1.5.10-10 9.4.10-11 7.6.10-11 
Se-73 F 1.0 7.7.10-10 0.8 6.5.10-10 3.3.10-10 2.1.10-10 1.0.10-10 8.0.10-11 
 M 0.2 1.6.10-9 0.1 1.2.10-9 5.9.10-10 3.8.10-10 2.4.10-10 1.9.10-10 
 S 0.02 1.8.10-9 0.01 1.3.10-9 6.3.10-10 4.0.10-10 2.6.10-10 2.1.10-10 
Se-73m F 1.0 9.3.10-11 0.8 7.2.10-11 3.5.10-11 2.3.10-11 1.1.10-11 9.2.10-12 
 M 0.2 1.8.10-10 0.1 1.3.10-10 6.1.10-11 3.9.10-11 2.5.10-11 2.0.10-11 
 S 0.02 1.9.10-10 0.01 1.3.10-10 6.5.10-11 4.1.10-11 2.6.10-11 2.2.10-11 
Se-75 F 1.0 7.8.10-9 0.8 6.0.1 0-9 3.4.10-9 2.5.10-9 1.2.10-9 1.0.10-9 
 M 0.2 5.4.10-9 0.1 4.5.10-9 2.5.10-9 1.7.10-9 1.3.10-9 1.1.10-9 
 S 0.02 5.6.10-9 0.01 4.7.10-9 2.9.10-9 2.0.10-9 1.6.10-9 1.3.10-9 
Se-79 F 1.0 1.6.10-8 0.8 1.3.10-8 7.7.10-9 5.6.10-9 1.5.10-9 1.1.10-9 
 M 0.2 1.4.10-8 0.1 1.1.10-8 6.9.10-9 4.9.10-9 3.3.10-9 2.6.10-9 
 S 0.02 2.3.10-8 0.01 2.0.10-8 1.3.10-8 8.7.10-9 7.6.10-9 6.8.10-9 
Se-81 F 1.0 8.6.10-11 0.8 5.4.10-11 2.3.10-11 1.5.10-11 9.2.10-12 8.0.10-12 
 M 0.2 1.3.10-10 0.1 8.5.10-11 3.8.10-11 2.5.10-11 1.6.10-11 1.4.10-11 
 S 0.02 1.4.10-10 0.01 8.9.10-11 3.9.10-11 2.6.10-11 1.7.10-11 1.5.10-11 
Se-81m F 1.0 1.8.10-10 0.8 1.2.10-10 5.4.10-11 3.4.10-11 1.9.10-11 1.6.10-11 
 M 0.2 3.8.10-10 0.1 2.5.10-10 1.2.10-10 8.0.10-11 5.8.10-11 4.7.10-11 
 S 0.02 4.1.10-10 0.01 2.7.10-10 1.3.10-10 8.5.10-11 6.2.10-11 5.1.10-11 
Se-83 F 1.0 1.7.10-10 0.8 1.2.10-10 5.8.10-11 3.6.10-11 2.1.10-11 1.8.10-11 
 M 0.2 2.7.10-10 0.1 1.9.10-10 9.2.10-11 5.9.10-11 3.9.10-11 3.2.10-11 
 S 0.02 2.8.10-10 0.01 2.0.10-10 9.6.10-11 6.2.1 0-11 4.1.10-11 3.4.10-11 
bromine           
Br-74 F 1.0 2.5.10-10 1.0 1.8.10-10 8.6.10-11 5.3.10-11 3.2.10-11 2.6.10-11 
 M 1.0 3.6.10-10 1.0 2.5.10-10 1.2.10-10 7.5.10-11 4.6.10-11 3.8.10-11 - 170 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Br-74m F 1.0 4.0.10-10 1.0 2.8.10-10 1.3.10-10 8.1.10-11 4.8.10-11 3.9.10-11 
 M 1.0 5.9.10-10 1.0 4.1.10-10 1.9.10-10 1.2.10-10 7.5.10-11 6.2.10-11 
Br-75 F 1.0 2.9.10-10 1.0 2.1.10-10 9.7.10-11 5.9.10-11 3.5.10-11 2.9.10-11 
 M 1.0 4.5.10-10 1.0 3.1.10-10 1.5.10-10 9.7.10-11 6.5.10-11 5.3.10-11 
Br-76 F 1.0 2.2.10-9 1.0 1.7.10-9 8.4.10-10 5.1.10-10 3.0.10-10 2.4.10-10 
 M 1.0 3.0.10-9 1.0 2.3.10-9 1.2.10-9 7.5.10-10 5.0.10-10 4.1.10-10 
Br-77 F 1.0 5.3.10-10 1.0 4.4.10-10 2.2.10-10 1.3.10-10 7.7.10-11 6.2.10-11 
 M 1.0 6.3.10-10 1.0 5.1.10-10 2.7.10-10 1.6.10-10 1.1.10-10 8.4.10-11 
Br-80 F 1.0 7.1.10-11 1.0 4.4.10-11 1.8.10-11 1.2.10-11 6.9.10-12 5.9.10-12 
 M 1.0 1.1.10-10 1.0 6.5.10-11 2.8.10-11 1.8.10-11 1.1.10-11 9.4.10-12 
Br-80m F 1.0 4.3.10-10 1.0 2.8.10-10 1.2.10-10 7.2.10-11 4.0.10-11 3.3.10-11 
 M 1.0 6.8.1 0-10 1.0 4.5.10-10 2.1.10-10 1.4.10-10 9.3.10-11 7.6.10-11 
Br-82 F 1.0 2.7.10-9 1.0 2.2.10-9 1.2.10-9 7.0.10-10 4.2.10-10 3.5.10-10 
 M 1.0 3.8.10-9 1.0 3.0.10-9 1.7.10-9 1.1.10-9 7.9.10-10 6.3.10-10 
Br-83 F 1.0 1.7.10-10 1.0 1.1.10-10 4.7.10-11 3.0.10-11 1.8.10-11 1.6.10-11 
 M 1.0 3.5.10-10 1.0 2.3.10-10 1.1.10-10 7.7.10-11 5.9.10-11 4.8.10-11 
Br-84 F 1.0 2.4.10-10 1.0 1.6.10-10 7.1.10-11 4.4.10-11 2.6.10-11 2.2.10-11 
 M 1.0 3.7.10-10 1.0 2.4.10-10 1.1.10-10 6.9.10-11 4.4.10-11 3.7.10-11 
rubidium           
Rb-79 F 1.0 1.6.10-10 1.0 1.1.10-10 5.0.10-11 3.2.10-11 1.9.10-11 1.6.10-11 
Rb-81 F 1.0 3.2.10-10 1.0 2.5.10-10 1.2.10-10 7.1.10-11 4.2.10-11 3.4.10-11 
Rb-81m F 1.0 6.2.10-11 1.0 4.6.10-11 2.2.10-11 1.4.10-11 8.5.10-12 7.0.10-12 
Rb-82m F 1.0 8.6.10-10 1.0 7.3.10-10 3.9.10-10 2.3.10-10 1.4.10-10 1.1.10-10 
Rb-83 F 1.0 4.9.10-9 1.0 3.8.10-9 2.0.10-9 1.3.10-9 7.9.10-10 6.9.10-10 
Rb-84 F 1.0 8.6.10-9 1.0 6.4.10-9 3.1.10-9 2.0.10-9 1.2.10-9 1.0.10-9 
Rb-86 F 1.0 1.2.10-8 1.0 7.7.10-9 3.4.10-9 2.0.10-9 1.1.10-9 9.3.10-10 
Rb-87 F 1.0 6.0.10-9 1.0 4.1.10-9 1.8.10-9 1.1.10-9 6.0.10-10 5.0.10-10 
Rb-88 F 1.0 1.9.10-10 1.0 1.2.10-10 5.2.10-11 3.2.10-11 1.9.10-11 1.6.10-11 
Rb-89 F 1.0 1.4.10-10 1.0 9.3.10-11 4.3.10-11 2.7.10-11 1.6.10-11 1.4.10-11 
strontiu m          
Sr-80 F 0.6 7.8.10-10 0.4X 5.4.10-10 2.4.10-10 1.4.10-10 7.9.10-11 7.1.10-11 
 M 0.2 1.4.10-9 0.1 9.0.10-10 4.1.10-10 2.5.10-10 1.5.10-10 1.3.10-10 
 S 0.02 1.5.10-9 0.01 9.4.10-10 4.3.10-10 2.7.10-10 1.6.10-10 1.4.10-10 
Sr-81 F 0.6 2.1.10-10 0.4X 1.5.10-10 6.7.10-11 4.1.10-11 2.4.10-11 2.1.10-11 
 M 0.2 3.3.10-10 0.1 2.2.10-10 1.0.10-10 6.6.10-11 4.2.10-11 3.5.10-11 - 171 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 3.4.10-10 0.01 2.3.10-10 1.1.10-10 6.9.10-11 4.4.10-11 3.7.10-11 
Sr-82 F 0.6 2.8.10-8 0.4X 1.5.10-8 6.6.10-9 4.6.10-9 3.2.10-9 2.1.10-9 
 M 0.2 5.5.10-8 0.1 4.0.10-8 2.1.10-8 1.4.10-8 1.0.10-8 8.9.10-9 
 S 0.02 6.1.10-8 0.01 4.6.10-8 2.5.10-8 1.7.10-8 1.2.10-8 1.1.10-8 
Sr-83 F 0.6 1.4.10-9 0.4X 1.1.10-9 5.5.10-10 3.4.10-10 2.0.10-10 1.6.10-10 
 M 0.2 2.5.10-9 0.1 1.9.10-9 9.5.10-10 6.0.10-10 3.9.10-10 3.1.10-10 
 S 0.02 2.8.10-9 0.01 2.0.10-9 1.0.10-9 6.5.10-10 4.2.10-10 3.4.10-10 
Sr-85 F 0.6 4.4.10-9 0.4X 2.3.10-9 1.1.10-9 9.6.10-10 8.3.10-10 3.8.10-10 
 M 0.2 4.3.10-9 0.1 3.1.10-9 1.8.10-9 1.2.10-9 8.8.10-10 6.4.10-10 
 S 0.02 4.4.10-9 0.01 3.7.10-9 2.2.10-9 1.3.10-9 1.0.10-9 8.1.10-10 
Sr-85m F 0.6 2.4.10-11 0.4X 1.9.10-11 9.6.10-12 6.0.10-12 3.7.10-12 2.9.10-12 
 M 0.2 3.1.10-11 0.1 2.5.10-11 1.3.10-11 8.0.10-12 5.1.10-12 4.1.10-12 
 S 0.02 3.2.10-11 0.01 2.6.10-11 1.3.10-11 8.3.10-12 5.4.10-12 4.3.10-12 
Sr-87m F 0.6 9.7.10-11 0.4X 7.8.10-11 3.8.10-11 2.3.10-11 1.3.10-11 1.1.10-11 
 M 0.2 1.6.10-10 0.1 1.2.10-10 5.9.10-11 3.8.10-11 2.5.10-11 2.0.10-11 
 S 0.02 1.7.10-10 0.01 1.2.10-10 6.2.10-11 4.0.10-11 2.6.10-11 2.1.10-11 
Sr-89 F 0.6 1.5.10-8 0.4X 7.3.10-9 3.2.10-9 2.3.10-9 1.7.10-9 1.0.10-9 
 M 0.2 3.3.10-8 0.1 2.4.10-8 1.3.10-8 9.1.10-9 7.3.10-9 6.1.10-9 
 S 0.02 3.9.10-8 0.01 3.0.10-8 1.7.10-8 1.2.10-8 9.3.10-9 7.9.10-9 
Sr-90 F 0.6 1.3.10-7 0.4X 5.2.10-8 3.1.10-8 4.1.10-8 5.3.10-8 2.4.10-8 
 M 0.2 1.5.10-7 0.1 1.1.10-7 6.5.10-8 5.1.10-8 5.0.10-8 3.6.10-8 
 S 0.02 4.2.10-7 0.01 4.0.10-7 2.7.10-7 1.8.10-7 1.6.10-7 1.6.10-7 
Sr-91 F 0.6 1.4.10-9 0.4X 1.1.10-9 5.2.10-10 3.1.10-10 1.7.10-10 1.6.10-10 
 M 0.2 3.1.10-9 0.1 2.2.10-9 1.1.10-9 6.9.10-10 4.4.10-10 3.7.10-10 
 S 0.02 3.5.10-9 0.01 2.5.10-9 1.2.10-9 7.7.10-10 4.9.10-10 4.1.10-10 
Sr-92 F 0.6 9.0.10-10 0.4X 7.1.10-10 3.3.10-10 2.0.10-10 1.0.10-10 9.8.10-11 
 M 0.2 1.9.10-9 0.1 1.4.10-9 6.5.10-10 4.1.10-10 2.5.10-10 2.1.10-10 
 S 0.02 2.2.10-9 0.01 1.5.10-9 7.0.10-10 4.5.10-10 2.7.10-10 2.3.10-10 
yttrium           
Y-86 M 0.001  3.7.10-9 1.0.10-4 2.9.10-9 1.5.10-9 9.3.10-10 5.6.10-10 4.5.10-10 
 S 0.001  3.8.10-9 1.0.10-4 3.0.10-9 1.5.10-9 9.6.10-10 5.8.10-10 4.7.10-10 
Y-86m M 0.001  2.2.10-10 1.0.10-4 1.7.10-10 8.7.10-11 5.6.10-11 3.4.10-11 2.7.10-11 
 S 0.001  2.3.10-10 1.0.10-4 1.8.10-10 9.0.10-11 5.7.10-11 3.5.10-11 2.8.10-11 
Y-87 M 0.001  2.7.10-9 1.0.10-4 2.1.10-9 1.1.10-9 7.0.10-10 4.7.10-10 3.7.10-10 
 S 0.001  2.8.10-9 1.0.10-4 2.2.10-9 1.1.10-9 7.3.10-10 5.0.10-10 3.9.10-10 - 172 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Y-88 M 0.001  1.9.10-8 1.0.10-4 1.6.10-8 1.0.10-8 6.7.10-9 4.9.10-9 4.1.10-9 
 S 0.001  2.0.10-8 1.0.10-4 1.7.10-8 9.8.10-9 6.6.10-9 5.4.10-9 4.4.10-9 
Y-90 M 0.001  1.3.10-8 1.0.10-4 8.4.10-9 4.0.10-9 2.6.10-9 1.7.10-9 1.4.10-9 
 S 0.001  1.3.10-8 1.0.10-4 8.8.10-9 4.2.10-9 2.7.10-9 1.8.10-9 1.5.10-9 
Y-90m M 0.001  7.2.10-10 1.0.10-4 5.7.10-10 2.8.10-10 1.8.10-10 1.1.10-10 9.5.10-11 
 S 0.001  7.5.10-10 1.0.10-4 6.0.10-10 2.9.10-10 1.9.10-10 1.2.10-10 1.0.10-10 
Y-91 M 0.001  3.9.10-8 1.0.10-4 3.0.10-8 1.6.10-8 1.1.10-8 8.4.10-9 7.1.10-9 
 S 0.001  4.3.10-8 1.0.10-4 3.4.10-8 1.9.10-8 1.3.10-8 1.0.10-8 8.9.10-9 
Y-91m M 0.001  7.0.10-11 1.0.10-4 5.5.10-11 2.9.10-11 1.8.10-11 1.2.10-11 1.0.10-11 
 S 0.001  7.4.10-11 1.0.10-4 5.9.10-11 3.1.10-11 2.0.10-11 1.4.10-11 1.1.10-11 
Y-92 M 0.001  1.8.10-9 1.0.10-4 1.2.10-9 5.3.10-10 3.3.10-10 2.0.10-10 1.7.10-10 
 S 0.001  1.9.10-9 1.0.10-4 1.2.10-9 5.5.10-10 3.5.10-10 2.1.10-10 1.8.10-10 
Y-93 M 0.001  4.4.10-9 1.0.10-4 2.9.10-9 1.3.10-9 8.1.10-10 4.7.10-10 4.0.10-10 
 S 0.001  4.6.10-9 1.0.10-4 3.0.10-9 1.4.10-9 8.5.10-10 5.0.10-10 4.2.10-10 
Y-94 M 0.001  2.8.10-10 1.0.10-4 1.8.10-10 8.1.10-11 5.0.10-11 3.1.10-11 2.7.10-11 
 S 0.001  2.9.10-10 1.0.10-4 1.9.10-10 8.4.10-11 5.2.10-11 3.3.10-11 2.8.10-11 
Y-95 M 0.001  1.5.10-10 1.0.10-4 9.8.10-11 4.4.10-11 2.8.10-11 1.8.10-11 1.5.10-11 
 S 0.001  1.6.10-10 1.0.10-4 1.0.10-10 4.5.10-11 2.9.10-11 1.8.10-11 1.6.10-11 
zirconium           
Zr-86 F 0.02 2.4.10-9 0.002  1.9.10-9 9.5.10-10 5.9.10-10 3.4.10-10 2.7.10-10 
 M 0.02 3.4.10-9 0.002  2.6.10-9 1.3.10-9 8.4.10-10 5.2.10-10 4.2.10-10 
 S 0.02 3.5.10-9 0.002  2.7.10-9 1.4.10-9 8.7.10-10 5.4.10-10 4.3.10-10 
Zr-88 F 0.02 6.9.10-9 0.002  8.3.10-9 5.6.10-9 4.7.10-9 3.6.10-9 3.5.10-9 
 M 0.02 8.5.10-9 0.002  7.8.10-9 5.1.10-9 3.6.10-9 3.0.10-9 2.6.10-9 
 S 0.02 1.3.10-8 0.002  1.2.10-8 7.7.10-9 5.2.10-9 4.3.10-9 3.6.10-9 
Zr-89 F 0.02 2.6.10-9 0.002  2.0.10-9 9.9.10-10 6.1.10-10 3.6.10-10 2.9.10-10 
 M 0.02 3.7.10-9 0.002  2.8.10-9 1.5.10-9 9.6.10-10 6.5.10-10 5.2.10-10 
 S 0.02 3.9.10-9 0.002  2.9.10-9 1.5.10-9 1.0.10-9 6.8.10-10 5.5.10-10 
Zr-93 F 0.02 3.5.10-9 0.002  4.8.10-9 5.3.10-9 9.7.10-9 1.8.10-8 2.5.10-8 
 M 0.02 3.3.10-9 0.002  3.1.10-9 2.8.10-9 4.1.10-9 7.5.10-9 1.0.10-8 
 S 0.02 7.0.10-9 0.002  6.4.10-9 4.5.10-9 3.3.10-9 3.3.10-9 3.3.10-9 
Zr-95 F 0.02 1.2.10-8 0.002  1.1.10-8 6.4.10-9 4.2.10-9 2.8.10-9 2.5.10-9 
 M 0.02 2.0.10-8 0.002  1.6.10-8 9.7.10-9 6.8.10-9 5.9.10-9 4.8.10-9 
 S 0.02 2.4.10-8 0.002  1.9.10-8 1.2.10-8 8.3.10-9 7.3.10-9 5.9.10-9 
Zr-97 F 0.02 5.0.10-9 0.002  3.4.10-9 1.5.10-9 9.1.10-10 4.8.10-10 3.9.10-10 - 173 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.02 7.8.10-9 0.002  5.3.10-9 2.8.10-9 1.8.10-9 1.1.10-9 9.2.10-10 
 S 0.02 8.2.10-9 0.002  5.6.10-9 2.9.10-9 1.9.10-9 1.2.10-9 8.9.10-10 
niobium           
Nb-88 F 0.02 1.8.10-10 0.01 1.3.10-10 6.3.10-11 3.9.10-11 2.4.10-11 1.9.10-11 
 M 0.02 2.5.10-10 0.01 1.8.10-10 8.5.10-11 5.3.10-11 3.3.10-11 2.7.10-11 
 S 0.02 2.6.10-10 0.01 1.8.10-10 8.7.10-11 5.5.10-11 3.5.10-11 2.8.10-11 
Nb-89 F 0.02 7.0.10-10 0.01 4.8.10-10 2.2.10-10 1.3.10-10 7.4.10-11 6.1.10-11 
 M 0.02 1.1.10-9 0.01 7.6.10-10 3.6.10-10 2.2.10-10 1.4.10-10 1.1.10-10 
 S 0.02 1.2.10-9 0.01 7.9.10-10 3.7.10-10 2.3.10-10 1.5.10-10 1.2.10-10 
Nb-89m F 0.02 4.0.10-10 0.01 2.9.10-10 1.4.10-10 8.3.10-11 4.8.10-11 3.9.10-11 
 M 0.02 6.2.10-10 0.01 4.3.10-10 2.1.10-10 1.3.10-10 8.2.10-11 6.8.10-11 
 S 0.02 6.4.10-10 0.01 4.4.10-10 2.1.10-10 1.4.10-10 8.6.10-11 7.1.10-11 
Nb-90 F 0.02 3.5.10-9 0.01 2.7.10-9 1.3.10-9 8.2.10-10 4.7.10-10 3.8.10-10 
 M 0.02 5.1.10-9 0.01 3.9.10-9 1.9.10-9 1.3.10-9 7.8.10-10 6.3.10-10 
 S 0.02 5.3.10-9 0.01 4.0.10-9 2.0.10-9 1.3.10-9 8.1.10-10 6.6.10-10 
Nb-93m F 0.02 1.8.10-9 0.01 1.4.10-9 7.0.10-10 4.4.10-10 2.7.10-10 2.2.10-10 
 M 0.02 3.1.10-9 0.01 2.4.10-9 1.3.10-9 8.2.10-10 5.9.10-10 5.1.10-10 
 S 0.02 7.4.10-9 0.01 6.5.10-9 4.0.10-9 2.5.10-9 1.9.10-9 1.8.10-9 
Nb-94 F 0.02 3.1.10-8 0.01 2.7.10-8 1.5.10-8 1.0.10-8 6.7.10-9 5.8.10-9 
 M 0.02 4.3.10-8 0.01 3.7.10-8 2.3.10-8 1.6.10-8 1.3.10-8 1.1.10-8 
 S 0.02 1.2.10-7 0.01 1.2.10-7 8.3.10-8 5.8.10-8 5.2.10-8 4.9.10-8 
Nb-95 F 0.02 4.1.10-9 0.01 3.1.10-9 1.6.10-9 1.2.10-9 7.5.10-10 5.7.10-10 
 M 0.02 6.8.10-9 0.01 5.2.10-9 3.1.10-9 2.2.10-9 1.9.10-9 1.5.10-9 
 S 0.02 7.7.10-9 0.01 5.9.10-9 3.6.10-9 2.5.10-9 2.2.10-9 1.8.10-9 
Nb-95m F 0.02 2.3.10-9 0.01 1.6.10-9 7.0.10-10 4.2.10-10 2.4.10-10 2.0.10-10 
 M 0.02 4.3.10-9 0.01 3.1.10-9 1.7.10-9 1.2.10-9 1.0.10-9 7.9.10-10 
 S 0.02 4.6.10-9 0.01 3.4.10-9 1.9.10-9 1.3.10-9 1.1.10-9 8.8.10-10 
Nb-96 F 0.02 3.1.10-9 0.01 2.4.10-9 1.2.10-9 7.3.10-10 4.2.10-10 3.4.10-10 
 M 0.02 4.7.10-9 0.01 3.6.10-9 1.8.10-9 1.2.10-9 7.8.10-10 6.3.10-10 
 S 0.02 4.9.10-9 0.01 3.7.10-9 1.9.10-9 1.2.10-9 8.3.10-10 6.6.10-10 
Nb-97 F 0.02 2.2.10-10 0.01 1.5.10-10 6.8.10-11 4.2.10-11 2.5.10-11 2.1.10-11 
 M 0.02 3.7.10-10 0.01 2.5.10-10 1.2.10-10 7.7.10-11 5.2.10-11 4.3.10-11 
 S 0.02 3.8.10-10 0.01 2.6.10-10 1.2.10-10 8.1.10-11 5.5.10-11 4.5.10-11 
Nb-98m F 0.02 3.4.10-10 0.01 2.4.10-10 1.1.10-10 6.9.10-11 4.1.10-11 3.3.10-11 
 M 0.02 5.2.10-10 0.01 3.6.10-10 1.7.10-10 1.1.10-10 6.8.10-11 5.6.10-11 - 174 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 5.3.10-10 0.01 3.7.10-10 1.8.10-10 1.1.10-10 7.1.10-11 5.8.10-11 
molybdenum           
Mo-90 F 1.0 1.2.10-9 0.8 1.1.10-9 5.3.10-10 3.2.10-10 1.9.10-10 1.5.10-10 
 M 0.2 2.6.10-9 0.1 2.0.10-9 9.9.10-10 6.5.1 0-10 4.2.10-10 3.4.10-10 
 S 0.02 2.8.10-9 0.01 2.1.10-9 1.1.10-9 6.9.10-10 4.5.10-10 3.6.10-10 
Mo-93 F 1.0 3.1.10-9 0.8 2.6.10-9 1.7.10-9 1.3.10-9 1.1.10-9 1.0.10-9 
 M 0.2 2.2.10-9 0.1 1.8.10-9 1.1.10-9 7.9.10-10 6.6.10-10 5.9.10-10 
 S 0.02 6.0.10-9 0.01 5.8.10-9 4.0.10-9 2.8.10-9 2.4.10-9 2.3.10-9 
Mo-93m F 1.0 7.3.10-10 0.8 6.4.10-10 3.3.10-10 2.0.10-10 1.2.10-10 9.6.10-11 
 M 0.2 1.2.10-9 0.1 9.7.10-10 5.0.10-10 3.2.10-10 2.0.10-10 1.6.10-10 
 S 0.02 1.3.10-9 0.01 1.0.10-9 5.2.10-10 3.4.10-10 2.1.10-10 1.7.10-10 
Mo-99 F 1.0 2.3.10-9 0.8 1.7.10-9 7.7.10-10 4.7.10-10 2.6.10-10 2.2.10-10 
 M 0.2 6.0.10-9 0.1 4.4.10-9 2.2.10-9 1.5.10-9 1.1.10-9 8.9.10-10 
 S 0.02 6.9.10-9 0.01 4.8.10-9 2.4.10-9 1.7.10-9 1.2.10-9 9.9.10-10 
Mo-101 F 1.0 1.4.10-10 0.8 9.7.10-11 4.4.10-11 2.8.10-11 1.7.10-11 1.4.10-11 
 M 0.2 2.2.10-10 0.1 1.5.10-10 7.0.10-11 4.5.10-11 3.0.10-11 2.5.10-11 
 S 0.02 2.3.10-10 0.01 1.6.10-10 7.2.10-11 4.7.10-11 3.1.10-11 2.6.10-11 
technetium           
Tc-93 F 1.0 2.4.10-10 0.8 2.1.10-10 1.1.10-10 6.7.10-11 4.0.10-11 3.2.10-11 
 M 0.2 2.7.10-10 0.1 2.3.10-10 1.2.10-10 7.5.10-11 4.4.10-11 3.5.10-11 
 S 0.02 2.8.10-10 0.01 2.3.10-10 1.2.10-10 7.6.10-11 4.5.10-11 3.5.10-11 
Tc-93m F 1.0 1.2.10-10 0.8 9.8.10-11 4.9.10-11 2.9.10-11 1.8.10-11 1.4.10-11 
 M 0.2 1.4.10-10 0.1 1.1.10-10 5.4.10-11 3.4.10-11 2.1.10-11 1.7.10-11 
 S 0.02 1.4.10-10 0.01 1.1.10-10 5.4.10-11 3.4.10-11 2.1.10-11 1.7.10-11 
Tc-94 F 1.0 8.9.10-10 0.8 7.5.10-10 3.9.10-10 2.3.10-10 1.4.10-10 1.1.10-10 
 M 0.2 9.8.10-10 0.1 8.1.10-10 4.2.10-10 2.6.10-10 1.6.10-10 1.2.10-10 
 S 0.02 9.9.10-10 0.01 8.2.10-10 4.3.10-10 2.7.10-10 1.6.10-10 1.3.10-10 
Tc-94m F 1.0 4.8.10-10 0.8 3.4.10-10 1.6.10-10 8.6.10-11 5.2.10-11 4.1.10-11 
 M 0.2 4.4.10-10 0.1 3.0.10-10 1.4.10-10 8.8.10-11 5.5.10-11 4.5.10-11 
 S 0.02 4.3.10-10 0.01 3.0.10-10 1.4.10-10 8.8.10-11 5.6.10-11 4.6.10-11 
Tc-95 F 1.0 7.5.10-10 0.8 6.3.10-10 3.3.10-10 2.0.10-10 1.2.10-10 9.6.10-11 
 M 0.2 8.3.10-10 0.1 6.9.10-10 3.6.10-10 2.2.10-10 1.3.10-10 1.0.10-10 
 S 0.02 8.5.10-10 0.01 7.0.10-10 3.6.10-10 2.3.10-10 1.4.10-10 1.1.10-10 
Tc-95m F 1.0 2.4.10-9 0.8 1.8.10-9 9.3.10-10 5.7.10-10 3.6.10-10 2.9.10-10 
 M 0.2 4.9.10-9 0.1 4.0.10-9 2.3.10-9 1.5.10-9 1.1.10-9 8.8.10-10 - 175 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 6.0.10-9 0.01 5.0.10-9 2.7.10-9 1.8.10-9 1.5.10-9 1.2.10-9 
Tc-96 F 1.0 4.2.10-9 0.8 3.4.10-9 1.8.10-9 1.1.10-9 7.0.10-10 5.7.10-10 
 M 0.2 4.7.10-9 0.1 3.9.10-9 2.1.10-9 1.3.10-9 8.6.10-10 6.8.10-10 
 S 0.02 4.8.10-9 0.01 3.9.10-9 2.1.10-9 1.4.10-9 8.9.10-10 7.0.10-10 
Tc-96m F 1.0 5.3.10-11 0.8 4.1.10-11 2.1.10-11 1.3.10-11 7.7.10-12 6.2.10-12 
 M 0.2 5.6.10-11 0.1 4.4.10-11 2.3.10-11 1.4.10-11 9.3.10-12 7.4.10-12 
 S 0.02 5.7.10-11 0.01 4.4.10-11 2.3.10-11 1.5.10-11 9.5.10-12 7.5.10-12 
Tc-97 F 1.0 5.2.10-10 0.8 3.7.10-10 1.7.10-10 9.4.10-11 5.6.10-11 4.3.1 0-11 
 M 0.2 1.2.10-9 0.1 1.0.10-9 5.7.10-10 3.6.10-10 2.8.10-10 2.2.10-10 
 S 0.02 5.0.10-9 0.01 4.8.10-9 3.3.10-9 2.2.10-9 1.9.10-9 1.8.10-9 
Tc-97m F 1.0 3.4.10-9 0.8 2.3.10-9 9.8.10-10 5.6.10-10 3.0.10-10 2.7.10-10 
 M 0.2 1.3.10-8 0.1 1.0.10-8 6.1.10-9 4.4.10-9 4.1.10-9 3.2.10-9 
 S 0.02 1.6.10-8 0.01 1.3.10-8 7.8.10-9 5.7.10-9 5.2.10-9 4.1.10-9 
Tc-98 F 1.0 1.0.10-8 0.8 6.8.10-9 3.2.10-9 1.9.10-9 1.2.10-9 9.7.10-10 
 M 0.2 3.5.10-8 0.1 2.9.10-8 1.7.10-8 1.2.10-8 1.0.10-8 8.3.10-9 
 S 0.02 1.1.10-7 0.01 1.1.10-7 7.6.10-8 5.4.10-8 4.8.10-8 4.5.10-8 
Tc-99 F 1.0 4.0.10-9 0.8 2.5.10-9 1.0.10-9 5.9.10-10 3.6.10-10 2.9.10-10 
 M 0.2 1.7.10-8 0.1 1.3.10-8 8.0.10-9 5.7.10-9 5.0.10-9 4.0.10-9 
 S 0.02 4.1.10-8 0.01 3.7.10-8 2.4.10-8 1.7.10-8 1.5.10-8 1.3.10-8 
Tc-99m F 1.0 1.2.10-10 0.8 8.7.10-11 4.1.10-11 2.4.10-11 1.5.10-11 1.2.10-11 
 M 0.2 1.3.10-10 0.1 9.9.10-11 5.1.10-11 3.4.10-11 2.4.10-11 1.9.10-11 
 S 0.02 1.3.10-10 0.01 1.0.10-10 5.2.10-11 3.5.10-11 2.5.10-11 2.0.10-11 
Tc-101 F 1.0 8.5.10-11 0.8 5.6.1 0-11 2.5.10-11 1.6.10-11 9.7.10-12 8.2.10-12 
 M 0.2 1.1.10-10 0.1 7.1.10-11 3.2.10-11 2.1.10-11 1.4.10-11 1.2.10-11 
 S 0.02 1.1.10-10 0.01 7.3.10-11 3.3.10-11 2.2.10-11 1.4.10-11 1.2.10-11 
Tc-104 F 1.0 2.7.10-10 0.8 1.8.10-10 8.0.10-11 4.6.10-11 2.8.10-11 2.3.10-11 
 M 0.2 2.9.10-10 0.1 1.9.10-10 8.6.10-11 5.4.10-11 3.3.10-11 2.8.10-11 
 S 0.02 2.9.10-10 0.01 1.9.10-10 8.7.10-11 5.4.10-11 3.4.10-11 2.9.10-11 
ruthenium           
Ru-94 F 0.1 2.5.10-10 0.05 1.9.10-10 9.0.10-11 5.4.10-11 3.1.10-11 2.5.10-11 
 M 0.1 3.8.10-10 0.05 2.8.10-10 1.3.10-10 8.4.10-11 5.2.10-11 4.2.10-11 
 S 0.02 4.0.10-10 0.01 2.9.10-10 1.4.10-10 8.7.10-11 5.4.10-11 4.4.10-11 
Ru-97 F 0.1 5.5.10-10 0.05 4.4.10-10 2.2.10-10 1.3.10-10 7.7.10-11 6.2.10-11 
 M 0.1 7.7.10-10 0.05 6.1.10-10 3.1.10-10 2.0.10-10 1.3.10-10 1.0.10-10 
 S 0.02 8.1.10-10 0.01 6.3.10-10 3.3.10-10 2.1.10-10 1.4.10-10 1.1.10-10 - 176 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Ru-103 F 0.1 4.2.10-9 0.05 3.0.10-9 1.5.10-9 9.3.10-10 5.6.10-10 4.8.10-10 
 M 0.1 1.1.10-8 0.05 8.4.10-9 5.0.10-9 3.5.10-9 3.0.10-9 2.4.1 0-9 
 S 0.02 1.3.10-8 0.01 1.0.10-8 6.0.10-9 4.2.10-9 3.7.10-9 3.0.10-9 
Ru-105 F 0.1 7.1.10-10 0.05 5.1.10-10 2.3.10-10 1.4.10-10 7.9.10-11 6.5.10-11 
 M 0.1 1.3.10-9 0.05 9.2.10-10 4.5.10-10 3.0.10-10 2.0.10-10 1.7.10-10 
 S 0.02 1.4.10-9 0.01 9.8.10-10 4.8.10-10 3.2.10-10 2.2.10-10 1.8.10-10 
Ru-106 F 0.1 7.2.10-8 0.05 5.4.10-8 2.6.10-8 1.6.10-8 9.2.10-9 7.9.10-9 
 M 0.1 1.4.10-7 0.05 1.1.10-7 6.4.10-8 4.1.10-8 3.1.10-8 2.8.10-8 
 S 0.02 2.6.10-7 0.01 2.3.10-7 1.4.10-7 9.1.10-8 7.1.10-8 6.6.10-8 
rhodium           
Rh-99 F 0.1 2.6.10-9 0.05 2.0.10-9 9.9.10-10 6.2.10-10 3.8.10-10 3.2.10-10 
 M 0.1 4.5.10-9 0.05 3.5.10-9 2.0.10-9 1.3.10-9 9.6.10-10 7.7.10-10 
 S 0.1 4.9.10-9 0.05 3.8.10-9 2.2.10-9 1.3.10-9 1.1.10-9 8.7.10-10 
Rh-99m F 0.1 2.4.10-10 0.05 2.0.10-10 1.0.10-10 6.1.10-11 3.5.10-11 2.8.10-11 
 M 0.1 3.1.10-10 0.05 2.5.10-10 1.3.10-10 8.0.10-11 4.9.10-11 3.9.10-11 
 S 0.1 3.2.10-10 0.05 2.6.10-10 1.3.10-10 8.2.10-11 5.1.10-11 4.0.10-11 
Rh-100 F 0.1 2.1.10-9 0.05 1.8.10-9 9.1.10-10 5.6.10-10 3.3.10-10 2.6.10-10 
 M 0.1 2.7.10-9 0.05 2.2.10-9 1.1.10-9 7.1.10-10 4.3.10-10 3.4.10-10 
 S 0.1 2.8.10-9 0.05 2.2.10-9 1.2.10-9 7.3.10-10 4.4.10-10 3.5.10-10 
Rh-101 F 0.1 7.4.10-9 0.05 6.1.10-9 3.5.10-9 2.3.10-9 1.5.10-9 1.4.10-9 
 M 0.1 9.8.10-9 0.05 8.0.10-9 4.9.10-9 3.4.10-9 2.8.10-9 2.3.10-9 
 S 0.1 1.9.10-8 0.05 1.7.10-8 1.1.10-8 7.4.10-9 6.2.10-9 5.4.10-9 
Rh-101m  F 0.1 8.4.10-10 0.05 6.6.10-10 3.3.10-10 2.0.10-10 1.2.10-10 9.7.10-11 
 M 0.1 1.3.10-9 0.05 9.8.10-10 5.2.10-10 3.5.10-10 2.5.10-10 1.9.10-10 
 S 0.1 1.3.10-9 0.05 1.0.10-9 5.5.10-10 3.7.10-10 2.7.10-10 2.1.10-10 
Rh-102m  F 0.1 3.3.10-8 0.05 2.8.10-8 1.7.10-8 1.1.10-8 7.9.10-9 7.3.10-9 
 M 0.1 3.0.10-8 0.05 2.5.10-8 1.5.10-8 1.0.10-8 7.9.10-9 6.9.10-9 
 S 0.1 5.4.10-8 0.05 5.0.10-8 3.5.10-8 2.4.10-8 2.0.10-8 1.7.10-8 
Rh-102 F 0.1 1.2.10-8 0.05 8.7.10-9 4.4.10-9 2.7.10-9 1.7.10-9 1.5.10-9 
 M 0.1 2.0.10-8 0.05 1.6.10-8 9.0.10-9 6.0.10-9 4.7.10-9 4.0.10-9 
 S 0.1 3.0.10-8 0.05 2.5.10-8 1.5.10-8 1.0.10-8 8.2.10-9 7.1.10-9 
Rh-103m  F 0.1 8.6.10-12 0.05 5.9.10-12 2.7.10-12 1.6.10-12 1.0.10-12 8.6.10-13 
 M 0.1 1.9.10-11 0.05 1.2.10-11 6.3.10-12 4.0.10-12 3.0.10-12 2.5.10-12 
 S 0.1 2.0.10-11 0.05 1.3.10-11 6.7.10-12 4.3.10-12 3.2.10-12 2.7.10-12 
Rh-105 F 0.1 1.0.10-9 0.05 6.9.10-10 3.0.10-10 1.8.10-10 9.6.10-11 8.2.10-11 - 177 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.1 2.2.10-9 0.05 1.6.10-9 7.4.10-10 5.2.10-10 4.1.10-10 3.2.10-10 
 S 0.1 2.4.10-9 0.05 1.7.10-9 8.0.10-10 5.6.10-10 4.5.10-10 3.5.10-10 
Rh-106m  F 0.1 5.7.10-10 0.05 4.5.10-10 2.2.10-10 1.4.10-10 8.0.10-11 6.5.10-11 
 M 0.1 8.2.10-10 0.05 6.3.10-10 3.2.10-10 2.0.10-10 1.3.10-10 1.1.10-10 
 S 0.1 8.5.10-10 0.05 6.5.10-10 3.3.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
Rh-107 F 0.1 8.9.10-11 0.05 5.9.10-11 2.6.10-11 1.7.10-11 1.0.10-11 9.0.10-12 
 M 0.1 1.4.10-10 0.05 9.3.10-11 4.2.10-11 2.8.10-11 1.9.10-11 1.6.10-11 
 S 0.1 1.5.10-10 0.05 9.7.10-11 4.4.10-11 2.9.10-11 1.9.10-11 1.7.10-11 
palladium           
Pd-100 F 0.05 3.9.10-9 0.005  3.0.10-9 1.5.10-9 9.7.10-10 5.8.10-10 4.7.10-10 
 M 0.05 5.2.10-9 0.005  4.0.10-9 2.2.10-9 1.4.10-9 9.9.10-10 8.0.10-10 
 S 0.05 5.3.10-9 0.005  4.1.10-9 2.2.10-9 1.5.10-9 1.0.10-9 8.5.10-10 
Pd-101 F 0.05 3.6.10-10 0.005  2.9.10-10 1.4.10-10 8.6.10-11 4.9.10-11 3.9.10-11 
 M 0.05 4.8.10-10 0.005  3.8.10-10 1.9.10-10 1.2.10-10 7.5.10-11 5.9.10-11 
 S 0.05 5.0.1 0-10 0.005  3.9.10-10 2.0.10-10 1.2.10-10 7.8.10-11 6.2.10-11 
Pd-103 F 0.05 9.7.10-10 0.005  6.5.10-10 3.0.10-10 1.9.10-10 1.1.10-10 8.9.10-11 
 M 0.05 2.3.10-9 0.005  1.6.10-9 9.0.10-10 5.9.10-10 4.5.10-10 3.8.10-10 
 S 0.05 2.5.10-9 0.005  1.8.10-9 1.0.10-9 6.8.10-10 5.3.10-10 4.5.10-10 
Pd-107 F 0.05 2.6.10-10 0.005  1.8.10-10 8.2.10-11 5.2.10-11 3.1.10-11 2.5.10-11 
 M 0.05 6.5.10-10 0.005  5.0.10-10 2.6.10-10 1.5.10-10 1.0.10-10 8.5.10-11 
 S 0.05 2.2.10-9 0.005  2.0.10-9 1.3.10-9 7.8.10-10 6.2.10-10 5.9.10-10 
Pd-109 F 0.05 1.5.10-9 0.005  9.9.10-10 4.2.10-10 2.6.10-10 1.4.10-10 1.2.10-10 
 M 0.05 2.6.10-9 0.005  1.8.10-9 8.8.10-10 5.9.10-10 4.3.10-10 3.4.10-10 
 S 0.05 2.7.10-9 0.005  1.9.10-9 9.3.10-10 6.3.10-10 4.6.10-10 3.7.10-10 
silver           
Ag-102 F 0.1 1.2.10-10 0.05 8.6.10-11 4.2.10-11 2.6.10-11 1.5.10-11 1.3.10-11 
 M 0.1 1.6.10-10 0.05 1.1.10-10 5.5.10-11 3.4.10-11 2.1.10-11 1.7.10-11 
 S 0.02 1.6.10-10 0.01 1.2.10-10 5.6.10-11 3.5.10-11 2.2.10-11 1.8.10-11 
Ag-103 F 0.1 1.4.10-10 0.05 1.0.10-10 4.9.10-11 3.0.10-11 1.8.10-11 1.4.10-11 
 M 0.1 2.2.10-10 0.05 1.6.10-10 7.6.10-11 4.8.10-11 3.2.10-11 2.6.10-11 
 S 0.02 2.3.10-10 0.01 1.6.10-10 7.9.10-11 5.1.10-11 3.3.10-11 2.7.10-11 
Ag-104 F 0.1 2.3.10-10 0.05 1.9.10-10 9.8.10-11 5.9.10-11 3.5.10-11 2.8.10-11 
 M 0.1 2.9.10-10 0.05 2.3.10-10 1.2.10-10 7.4.10-11 4.5.10-11 3.6.10-11 
 S 0.02 2.9.10-10 0.01 2.4.10-10 1.2.10-10 7.6.10-11 4.6.10-11 3.7.10-11 
Ag-104m  F 0.1 1.6.10-10 0.05 1.1.10-10 5.5.10-11 3.4.10-11 2.0.10-11 1.6.10-11 - 178 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.1 2.3.10-10 0.05 1.6.10-10 7.7.10-11 4.8.10-11 3.0.10-11 2.5.10-11 
 S 0.02 2.4.10-10 0.01 1.7.10-10 8.0.10-11 5.0.10-11 3.1.10-11 2.6.10-11 
Ag-105 F 0.1 3.9.10-9 0.05 3.4.10-9 1.7.10-9 1.0.10-9 6.4.10-10 5.4.10-10 
 M 0.1 4.5.10-9 0.05 3.5.10-9 2.0.10-9 1.3.10-9 9.0.1 0-10 7.3.10-10 
 S 0.02 4.5.10-9 0.01 3.6.10-9 2.1.10-9 1.3.10-9 1.0.10-9 8.1.10-10 
Ag-106 F 0.1 9.4.10-11 0.05 6.4.10-11 2.9.10-11 1.8.10-11 1.1.10-11 9.1.10-12 
 M 0.1 1.4.10-10 0.05 9.5.10-11 4.4.10-11 2.8.10-11 1.8.10-11 1.5.10-11 
 S 0.02 1.5.10-10 0.01 9.9.10-11 4.5.10-11 2.9.10-11 1.9.10-11 1.6.10-11 
Ag-106m  F 0.1 7.7.10-9 0.05 6.1.10-9 3.2.10-9 2.1.10-9 1.3.10-9 1.1.10-9 
 M 0.1 7.2.10-9 0.05 5.8.10-9 3.2.10-9 2.1.10-9 1.4.10-9 1.1.10-9 
 S 0.02 7.0.10-9 0.01 5.7.10-9 3.2.10-9 2.1.10-9 1.4.10-9 1.1.10-9 
Ag-108m  F 0.1 3.5.10-8 0.05 2.8.10-8 1.6.10-8 1.0.10-8 6.9.10-9 6.1.10-9 
 M 0.1 3.3.10-8 0.05 2.7.10-8 1.7.10-8 1.1.10-8 8.6.10-9 7.4.10-9 
 S 0.02 8.9.10-8 0.01 8.7.10-8 6.2.10-8 4.4.10-8 3.9.10-8 3.7.10-8 
Ag-110m  F 0.1 3.5.10-8 0.05 2.8.10-8 1.5.10-8 9.7.10-9 6.3.10-9 5.5.10-9 
 M 0.1 3.5.10-8 0.05 2.8.10-8 1.7.10-8 1.2.10-8 9.2.10-9 7.6.10-9 
 S 0.02 4.6.10-8 0.01 4.1.10-8 2.6.10-8 1.8.10-8 1.5.10-8 1.2.10-8 
Ag-111 F 0.1 4.8.10-9 0.05 3.2.10-9 1.4.10-9 8.8.10-10 4.8.10-10 4.0.10-10 
 M 0.1 9.2.10-9 0.05 6.6.10-9 3.5.10-9 2.4.10-9 1.9.10-9 1.5.10-9 
 S 0.02 9.9.10-9 0.01 7.1.10-9 3.8.10-9 2.7.10-9 2.1.10-9 1.7.10-9 
Ag-112 F 0.1 9.8.10-10 0.05 6.4.10-10 2.8.10-10 1.7.10-10 9.1.10-11 7.6.10-11 
 M 0.1 1.7.10-9 0.05 1.1.10-9 5.1.10-10 3.2.10-10 2.0.10-10 1.6.10-10 
 S 0.02 1.8.10-9 0.01 1.2.10-9 5.4.10-10 3.4.10-10 2.1.10-10 1.7.10-10 
Ag-115 F 0.1 1.6.10-10 0.05 1.0.10-10 4.6.10-11 2.9.10-11 1.7.10-11 1.5.10-11 
 M 0.1 2.5.10-10 0.05 1.7.10-10 7.6.10-11 4.9.10-11 3.2.10-11 2.7.10-11 
 S 0.02 2.7.1 0-10 0.01 1.7.10-10 8.0.10-11 5.2.10-11 3.4.10-11 2.9.10-11 
cadmium           
Cd-104 F 0.1 2.0.10-10 0.05 1.7.10-10 8.7.10-11 5.2.10-11 3.1.10-11 2.4.10-11 
 M 0.1 2.6.10-10 0.05 2.1.10-10 1.1.10-10 6.9.10-11 4.2.10-11 3.4.10-11 
 S 0.1 2.7.10-10 0.05 2.2.10-10 1.1.10-10 7.0.10-11 4.4.10-11 3.5.10-11 
Cd-107 F 0.1 2.3.10-10 0.05 1.7.10-10 7.4.10-11 4.6.10-11 2.5.10-11 2.1.10-11 
 M 0.1 5.2.10-10 0.05 3.7.10-10 2.0.10-10 1.3.10-10 8.8.10-11 8.3.10-11 
 S 0.1 5.5.10-10 0.05 3.9.10-10 2.1.10-10 1.4.10-10 9.7.10-11 7.7.10-11 
Cd-109 F 0.1 4.5.10-8 0.05 3.7.10-8 2.1.10-8 1.4.10-8 9.3.10-9 8.1.10-9 
 M 0.1 3.0.10-8 0.05 2.3.10-8 1.4.10-8 9.5.10-9 7.8.10-9 6.6.10-9 - 179 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.1 2.7.10-8 0.05 2.1.10-8 1.3.10-8 8.9.10-9 7.6.10-9 6.2.10-9 
Cd-113 F 0.1 2.6.10-7 0.05 2.4.1 0-7 1.7.10-7 1.4.10-7 1.2.10-7 1.2.10-7 
 M 0.1 1.2.10-7 0.05 1.0.10-7 7.6.10-8 6.1.10-8 5.7.10-8 5.5.10-8 
 S 0.1 7.8.10-8 0.05 5.8.10-8 4.1.10-8 3.0.10-8 2.7.10-8 2.6.10-8 
Cd-113m  F 0.1 3.0.10-7 0.05 2.7.10-7 1.8.10-7 1.3.10-7 1.1.10-7 1.1.10-7 
 M 0.1 1.4.10-7 0.05 1.2.10-7 8.1.10-8 6.0.10-8 5.3.10-8 5.2.10-8 
 S 0.1 1.1.10-7 0.05 8.4.10-8 5.5.10-8 3.9.10-8 3.3.10-8 3.1.10-8 
Cd-115 F 0.1 4.0.10-9 0.05 2.6.10-9 1.2.10-9 7.5.10-10 4.3.10-10 3.5.10-10 
 M 0.1 6.7.10-9 0.05 4.8.10-9 2.4.10-9 1.7.10-9 1.2.1 0-9 9.8.10-10 
 S 0.1 7.2.10-9 0.05 5.1.10-9 2.6.10-9 1.8.10-9 1.3.10-9 1.1.10-9 
Cd-115m  F 0.1 4.6.10-8 0.05 3.2.10-8 1.5.10-8 1.0.10-8 6.4.10-9 5.3.10-9 
 M 0.1 4.0.10-8 0.05 2.5.10-8 1.4.10-8 9.4.10-9 7.3.10-9 6.2.10-9 
 S 0.1 3.9.10-8 0.05 3.0.10-8 1.7.10-8 1.1.10-8 8.9.10-9 7.7.10-9 
Cd-117 F 0.1 7.4.10-10 0.05 5.2.10-10 2.4.10-10 1.5.10-10 8.1.10-11 6.7.10-11 
 M 0.1 1.3.10-9 0.05 9.3.10-10 4.5.10-10 2.9.10-10 2.0.10-10 1.6.10-10 
 S 0.1 1.4.10-9 0.05 9.8.10-10 4.8.10-10 3.1.10-10 2.1.10-10 1.7.10-10 
Cd-117m  F 0.1 8.9.10-10 0.05 6.7.10-10 3.3.10-10 2.0.10-10 1.1.10-10 9.4.10-11 
 M 0.1 1.5.10-9 0.05 1.1.10-9 5.5.10-10 3.6.10-10 2.4.10-10 2.0.10-10 
 S 0.1 1.5.10-9 0.05 1.1.10-9 5.7.10-10 3.8.10-10 2.6.10-10 2.1.10-10 
indium           
In-109 F 0.04 2.6.10-10 0.02 2.1.10-10 1.0.10-10 6.3.10-11 3.6.10-11 2.9.10-11 
 M 0.04 3.3.10-10 0.02 2.6.10-10 1.3.10-10 8.4.10-11 5.3.10-11 4.2.10-11 
In-110 F 0.04 8.2.10-10 0.02 7.1.10-10 3.7.10-10 2.3.10-10 1.3.10-10 1.1.10-10 
 M 0.04 9.9.10-10 0.02 8.3.10-10 4.4.1 0-10 2.7.10-10 1.6.10-10 1.3.10-10 
In-110m  F 0.04 3.0.10-10 0.02 2.1.10-10 9.9.10-11 6.0.10-11 3.5.10-11 2.8.10-11 
 M 0.04 4.5.10-10 0.02 3.1.10-10 1.5.10-10 9.2.10-11 5.8.10-11 4.7.10-11 
In-111 F 0.04 1.2.10-9 0.02 8.6.10-10 4.2.10-10 2.6.10-10 1.5.10-10 1.3.10-10 
 M 0.04 1.5.10-9 0.02 1.2.10-9 6.2.10-10 4.1.10-10 2.9.10-10 2.3.10-10 
In-112 F 0.04 4.4.10-11 0.02 3.0.10-11 1.3.10-11 8.7.10-12 5.4.10-12 4.7.10-12 
 M 0.04 6.5.10-11 0.02 4.4.10-11 2.0.10-11 1.3.10-11 8.7.10-12 7.4.10-12 
In-113m  F 0.04 1.0.10-10 0.02 7.0.10-11 3.2.10-11 2.0.10-11 1.2.10-11 9.7.10-12 
 M 0.04 1.6.10-10 0.02 1.1.10-10 5.5.10-11 3.6.10-11 2.4.10-11 2.0.10-11 
In-114m  F 0.04 1.2.10-7 0.02 7.7.10-8 3.4.10-8 1.9.10-8 1.1.10-8 9.3.10-9 
 M 0.04 4.8.10-8 0.02 3.3.10-8 1.6.10-8 1.0.10-8 7.8.10-9 6.1.10-9 
In-115 F 0.04 8.3.10-7 0.02 7.8.10-7 5.5.10-7 5.0.10-7 4.2.10-7 3.9.10-7 - 180 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.04 3.0.10-7 0.02 2.8.10-7 2.1.10-7 1.9.10-7 1.7.10-7 1.6.10-7 
In-115m  F 0.04 2.8.10-10 0.02 1.9.10-10 8.4.10-11 5.1.10-11 2.8.10-11 2.4.10-11 
 M 0.04 4.7.10-10 0.02 3.3.10-10 1.6.10-10 1.0.10-10 7.2.10-11 5.9.10-11 
In-116m  F 0.04 2.5.10-10 0.02 1.9.10-10 9.2.10-11 5.7.10-11 3.4.10-11 2.8.10-11 
 M 0.04 3.6.10-10 0.02 2.7.10-10 1.3.10-10 8.5.10-11 5.6.10-11 4.5.10-11 
In-117 F 0.04 1.4.10-10 0.02 9.7.1 0-11 4.5.10-11 2.8.10-11 1.7.10-11 1.5.10-11 
 M 0.04 2.3.10-10 0.02 1.6.10-10 7.5.10-11 5.0.10-11 3.5.10-11 2.9.10-11 
In-117m  F 0.04 3.4.10-10 0.02 2.3.10-10 1.0.10-10 6.2.10-11 3.5.10-11 2.9.10-11 
 M 0.04 6.0.10-10 0.02 4.0.10-10 1.9.10-10 1.3.10-10 8.7.10-11 7.2.10-11 
In-119m  F 0.04 1.2.10-10 0.02 7.3.10-11 3.1.10-11 2.0.10-11 1.2.10-11 1.0.10-11 
 M 0.04 1.8.10-10 0.02 1.1.10-10 4.9.10-11 3.2.10-11 2.0.10-11 1.7.10-11 
tin          
Sn-110 F 0.04 1.0.10-9 0.02 7.6.10-10 3.6.10-10 2.2.10-10 1.2.10-10 9.9.10-11 
 M 0.04 1.5.10-9 0.02 1.1.10-9 5.1.10-10 3.2.10-10 1.9.10-10 1.6.10-10 
Sn-111 F 0.04 7.7.10-11 0.02 5.4.10-11 2.6.10-11 1.6.10-11 9.4.10-12 7.8.10-12 
 M 0.04 1.1.10-10 0.02 8.0.10-11 3.8.10-11 2.5.10-11 1.6.10-11 1.3.10-11 
Sn-113 F 0.04 5.1.1 0-9 0.02 3.7.10-9 1.8.10-9 1.1.10-9 6.4.10-10 5.4.10-10 
 M 0.04 1.3.10-8 0.02 1.0.10-8 5.8.10-9 4.0.10-9 3.2.10-9 2.7.10-9 
Sn-117m  F 0.04 3.3.10-9 0.02 2.2.10-9 1.0.10-9 6.1.10-10 3.4.10-10 2.8.10-10 
 M 0.04 1.0.10-8 0.02 7.7.10-9 4.6.10-9 3.4.10-9 3.1.10-9 2.4.10-9 
Sn-119m  F 0.04 3.0.10-9 0.02 2.2.10-9 1.0.10-9 6.0.10-10 3.4.10-10 2.8.10-10 
 M 0.04 1.0.10-8 0.02 7.9.10-9 4.7.10-9 3.1.10-9 2.6.10-9 2.2.10-9 
Sn-121 F 0.04 7.7.10-10 0.02 5.0.10-10 2.2.10-10 1.3.10-10 7.0.10-11 6.0.10-11 
 M 0.04 1.5.10-9 0.02 1.1.10-9 5.1.10-10 3.6.10-10 2.9.10-10 2.3.10-10 
Sn-121m  F 0.04 6.9.10-9 0.02 5.4.10-9 2.8.10-9 1.6.10-9 9.4.10-10 8.0.10-10 
 M 0.04 1.9.10-8 0.02 1.5.10-8 9.2.10-9 6.4.10-9 5.5.10-9 4.5.10-9 
Sn-123 F 0.04 1.4.10-8 0.02 9.9.10-9 4.5.10-9 2.6.10-9 1.4.10-9 1.2.10-9 
 M 0.04 4.0.10-8 0.02 3.1.10-8 1.8.10-8 1.2.10-8 9.5.10-9 8.1.10-9 
Sn-123m  F 0.04 1.4.10-10 0.02 8.9.10-11 3.9.10-11 2.5.10-11 1.5.10-11 1.3.10-11 
 M 0.04 2.3.10-10 0.02 1.5.10-10 7.0.10-11 4.6.10-11 3.2.10-11 2.7.10-11 
Sn-125 F 0.04 1.2.10-8 0.02 8.0.10-9 3.5.10-9 2.0.10-9 1.1.10-9 8.9.10-10 
 M 0.04 2.1.10-8 0.02 1.5.10-8 7.6.10-9 5.0.10-9 3.6.10-9 3.1.10-9 
Sn-126 F 0.04 7.3.10-8 0.02 5.9.10-8 3.2.10-8 2.0.10-8 1.3.10-8 1.1.10-8 
 M 0.04 1.2.10-7 0.02 1.0.10-7 6.2.10-8 4.1.10-8 3.3.10-8 2.8.10-8 
Sn-127 F 0.04 6.6.10-10 0.02 4.7.10-10 2.3.10-10 1.4.10-10 7.9.10-11 6.5.10-11 - 181 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.04 1.0.10-9 0.02 7.4.10-10 3.7.10-10 2.4.10-10 1.6.10-10 1.3.10-10 
Sn-128 F 0.04 5.1.10-10 0.02 3.6.10-10 1.7.10-10 1.0.10-10 6.1.10-11 5.0.10-11 
 M 0.04 8.0.10-10 0.02 5.5.10-10 2.7.10-10 1.7.10-10 1.1.10-10 9.2.10-11 
antimony           
Sb-115 F 0.2 8.1.10-11 0.1 5.9.10-11 2.8.10-11 1.7.10-11 1.0.10-11 8.5.10-12 
 M 0.02 1.2.10-10 0.01 8.3.10-11 4.0.10-11 2.5.10-11 1.6.10-11 1.3.10-11 
 S 0.02 1.2.10-10 0.01 8.6.10-11 4.1.10-11 2.6.10-11 1.7.10-11 1.4.10-11 
Sb-116 F 0.2 8.4.10-11 0.1 6.2.10-11 3.0.10-11 1.9.10-11 1.1.10-11 9.1.10-12 
 M 0.02 1.1.10-10 0.01 8.2.10-11 4.0.10-11 2.5.10-11 1.5.10-11 1.3.10-11 
 S 0.02 1.2.10-10 0.01 8.5.10-11 4.1.10-11 2.6.1 0-11 1.6.10-11 1.3.10-11 
Sb-116m  F 0.2 2.6.10-10 0.1 2.1.10-10 1.1.10-10 6.6.10-11 4.0.10-11 3.2.10-11 
 M 0.02 3.6.10-10 0.01 2.8.10-10 1.5.10-10 9.1.10-11 5.9.10-11 4.7.10-11 
 S 0.02 3.7.10-10 0.01 2.9.10-10 1.5.10-10 9.4.10-11 6.1.10-11 4.9.10-11 
Sb-117 F 0.2 7.7.10-11 0.1 6.0.10-11 2.9.10-11 1.8.10-11 1.0.10-11 8.5.10-12 
 M 0.02 1.2.10-10 0.01 9.1.10-11 4.6.10-11 3.0.10-11 2.0.10-11 1.6.10-11 
 S 0.02 1.3.10-10 0.01 9.5.10-11 4.8.10-11 3.1.10-11 2.2.10-11 1.7.10-11 
Sb-118m  F 0.2 7.3.10-10 0.1 6.2.1 0-10 3.3.10-10 2.0.10-10 1.2.10-10 9.3.10-11 
 M 0.02 9.3.10-10 0.01 7.6.10-10 4.0.10-10 2.5.10-10 1.5.10-10 1.2.10-10 
 S 0.02 9.5.10-10 0.01 7.8.10-10 4.1.10-10 2.5.10-10 1.5.10-10 1.2.10-10 
Sb-119 F 0.2 2.7.10-10 0.1 2.0.10-10 9.4.10-11 5.5.10-11 2.9.1 0-11 2.3.10-11 
 M 0.02 4.0.10-10 0.01 2.8.10-10 1.3.10-10 7.9.10-11 4.4.10-11 3.5.10-11 
 S 0.02 4.1.10-10 0.01 2.9.10-10 1.4.10-10 8.2.10-11 4.5.10-11 3.6.10-11 
Sb-120m  F 0.2 4.1.10-9 0.1 3.3.10-9 1.8.10-9 1.1.10-9 6.7.10-10 5.5.10-10 
 M 0.02 6.3.10-9 0.01 5.0.10-9 2.8.10-9 1.8.10-9 1.3.10-9 1.0.10-9 
 S 0.02 6.6.10-9 0.01 5.3.10-9 2.9.10-9 1.9.10-9 1.4.10-9 1.1.10-9 
Sb-120 F 0.2 4.6.10-11 0.1 3.1.10-11 1.4.10-11 8.9.10-12 5.4.10-12 4.6.10-12 
 M 0.02 6.6.10-11 0.01 4.4.10-11 2.0.10-11 1.3.10-11 8.3.10-12 7.0.10-12 
 S 0.02 6.8.10-11 0.01 4.6.10-11 2.1.10-11 1.4.10-11 8.7.10-12 7.3.10-12 
Sb-122 F 0.2 4.2.10-9 0.1 2.8.10-9 1.4.10-9 8.4.10-10 4.4.10-10 3.6.10-10 
 M 0.02 8.3.10-9 0.01 5.7.10-9 2.8.10-9 1.8.10-9 1.3.10-9 1.0.10-9 
 S 0.02 8.8.10-9 0.01 6.1.10-9 3.0.10-9 2.0.10-9 1.4.10-9 1.1.10-9 
Sb-124 F 0.2 1.2.10-8 0.1 8.8.10-9 4.3.10-9 2.6.10-9 1.6.10-9 1.3.10-9 
 M 0.02 3.1.10-8 0.01 2.4.10-8 1.4.10-8 9.6.10-9 7.7.10-9 6.4.10-9 
 S 0.02 3.9.10-8 0.01 3.1.10-8 1.8.10-8 1.3.10-8 1.0.10-8 8.6.10-9 
Sb-124m F 0.2 2.7.10-11 0.1 1.9.10-11 9.0.10-12 5.6.10-12 3.4.10-12 2.8.10-12 - 182 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.02 4.3.10-11 0.01 3.1.10-11 1.5.10-11 9.6.10-12 6.5.10-12 5.4.10-12 
 S 0.02 4.6.10-11 0.01 3.3.10-11 1.6.10-11 1.0.10-11 7.2.10-12 5.9.10-12 
Sb-125 F 0.2 8.7.10-9 0.1 6.8.10-9 3.7.10-9 2.3.10-9 1.5.10-9 1.4.10-9 
 M 0.02 2.0.10-8 0.01 1.6.10-8 1.0.10-8 6.8.10-9 5.8.10-9 4.8.10-9 
 S 0.02 4.2.10-8 0.01 3.8.10-8 2.4.10-8 1.6.10-8 1.4.10-8 1.2.10-8 
Sb-126 F 0.2 8.8.10-9 0.1 6.6.10-9 3.3.10-9 2.1.10-9 1.2.10-9 1.0.10-9 
 M 0.02 1.7.10-8 0.01 1.3.10-8 7.4.10-9 5.1.10-9 3.5.10-9 2.8.10-9 
 S 0.02 1.9.10-8 0.01 1.5.10-8 8.2.10-9 5.0.10-9 4.0.10-9 3.2.10-9 
Sb-126m  F 0.2 1.2.10-10 0.1 8.2.10-11 3.8.10-11 2.4.10-11 1.5.10-11 1.2.10-11 
 M 0.02 1.7.10-10 0.01 1.2.10-10 5.5.10-11 3.5.10-11 2.3.10-11 1.9.10-11 
 S 0.02 1.8.10-10 0.01 1.2.10-10 5.7.10-11 3.7.10-11 2.4.10-11 2.0.10-11 
Sb-127 F 0.2 5.1.10-9 0.1 3.5.10-9 1.6.10-9 9.7.10-10 5.2.10-10 4.3.10-10 
 M 0.02 1.0.10-8 0.01 7.3.10-9 3.9.10-9 2.7.10-9 2.1.10-9 1.7.10-9 
 S 0.02 1.1.10-8 0.01 7.9.10-9 4.2.10-9 3.0.10-9 2.3.10-9 1.9.10-9 
Sb-128 F 0.2 2.1.10-9 0.1 1.7.10-9 8.3.10-10 5.1.10-10 2.9.10-10 2.3.10-10 
 M 0.02 3.3.10-9 0.01 2.5.10-9 1.2.10-9 7.9.10-10 5.0.10-10 4.0.10-10 
 S 0.02 3.4.10-9 0.01 2.6.10-9 1.3.10-9 8.3.10-10 5.2.10-10 4.2.10-10 
Sb-128m  F 0.2 9.8.10-11 0.1 6.9.10-11 3.2.10-11 2.0.10-11 1.2.10-11 1.0.10-11 
 M 0.02 1.3.10-10 0.01 9.2.10-11 4.3.10-11 2.7.10-11 1.7.10-11 1.4.10-11 
 S 0.02 1.4.10-10 0.01 9.4.10-11 4.4.10-11 2.8.10-11 1.8.10-11 1.5.10-11 
Sb-129 F 0.2 1.1.10-9 0.1 8.2.10-10 3.8.10-10 2.3.10-10 1.3.10-10 1.0.10-10 
 M 0.02 2.0.10-9 0.01 1.4.10-9 6.8.10-10 4.4.10-10 2.9.10-10 2.3.10-10 
 S 0.02 2.1.10-9 0.01 1.5.10-9 7.2.10-10 4.6.10-10 3.0.10-10 2.5.10-10 
Sb-130 F 0.2 3.0.10-10 0.1 2.2.10-10 1.1.10-10 6.6.10-11 4.0.10-11 3.3.10-11 
 M 0.02 4.5.10-10 0.01 3.2.10-10 1.6.10-10 9.8.10-11 6.3.10-11 5.1.10-11 
 S 0.02 4.6.10-10 0.01 3.3.10-10 1.6.10-10 1.0.10-10 6.5.10-11 5.3.10-11 
Sb-131 F 0.2 3.5.10-10 0.1 2.8.10-10 1.4.10-10 7.7.10-11 4.6.10-11 3.5.10-11 
 M 0.02 3.9.10-10 0.01 2.6.10-10 1.3.10-10 8.0.10-11 5.3.10-11 4.4.10-11 
 S 0.02 3.8.10-10 0.01 2.6.10-10 1.2.10-10 7.9.10-11 5.3.10-11 4.4.10-11 
tellurium           
Te-116 F 0.6 5.3.10-10 0.3 4.2.10-10 2.1.10-10 1.3.10-10 7.2.10-11 5.8.10-11 
 M 0.2 8.6.10-10 0.1 6.4.10-10 3.2.10-10 2.0.10-10 1.3.10-10 1.0.10-10 
 S 0.02 9.1.10-10 0.01 6.7.10-10 3.3.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
Te-121 F 0.6 1.7.10-9 0.3 1.4.10-9 7.2.10-10 4.6.10-10 2.9.10-10 2.4.10-10 
 M 0.2 2.3.10-9 0.1 1.9.10-9 1.0.10-9 6.8.10-10 4.7.10-10 3.8.10-10 - 183 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 2.4.10-9 0.01 2.0.10-9 1.1.10-9 7.2.10-10 5.1.10-10 4.1.10-10 
Te-121m  F 0.6 1.4.10-8 0.3 1.0.10-8 5.3.10-9 3.3.10-9 2.1.10-9 1.8.10-9 
 M 0.2 1.9.10-8 0.1 1.5.10-8 8.8.10-9 6.1.10-9 5.1.10-9 4.2.10-9 
 S 0.02 2.3.10-8 0.01 1.9.10-8 1.2.10-8 8.1.10-9 6.9.10-9 5.7.10-9 
Te-123 F 0.6 1.1.10-8 0.3 9.1.10-9 6.2.10-9 4.8.10-9 4.0.10-9 3.9.10-9 
 M 0.2 5.6.10-9 0.1 4.4.10-9 3.0.10-9 2.3.10-9 2.0.10-9 1.9.10-9 
 S 0.02 5.3.10-9 0.01 5.0.10-9 3.5.10-9 2.4.10-9 2.1.10-9 2.0.10-9 
Te-123m F 0.6 9.8.10-9 0.3 6.8.10-9 3.4.10-9 1.9.10-9 1.1.10-9 9.5.10-10 
 M 0.2 1.8.10-8 0.1 1.3.10-8 8.0.10-9 5.7.10-9 5.0.10-9 4.0.10-9 
 S 0.02 2.0.10-8 0.01 1.6.10-8 9.8.10-9 7.1.10-9 6.3.10-9 5.1.10-9 
Te-125m  F 0.6 6.2.10-9 0.3 4.2.10-9 2.0.10-9 1.1.10-9 6.1.10-10 5.1.10-10 
 M 0.2 1.5.10-8 0.1 1.1.10-8 6.6.10-9 4.8.10-9 4.3.10-9 3.4.10-9 
 S 0.02 1.7.10-8 0.01 1.3.10-8 7.8.10-9 5.8.10-9 5.3.10-9 4.2.10-9 
Te-127 F 0.6 4.3.10-10 0.3 3.2.10-10 1.4.10-10 8.5.10-11 4.5.10-11 3.9.10-11 
 M 0.2 1.0.10-9 0.1 7.3.10-10 3.6.10-10 2.4.10-10 1.6.10-10 1.3.10-10 
 S 0.02 1.2.10-9 0.01 7.9.10-10 3.9.10-10 2.6.10-10 1.7.10-10 1.4.10-10 
Te-127m  F 0.6 2.1.10-8 0.3 1.4.10-8 6.5.10-9 3.5.10-9 2.0.10-9 1.5.10-9 
 M 0.2 3.5.10-8 0.1 2.6.10-8 1.5.10-8 1.1.10-8 9.2.10-9 7.4.10-9 
 S 0.02 4.1.10-8 0.01 3.3.10-8 2.0.10-8 1.4.10-8 1.2.10-8 9.8.10-9 
Te-129 F 0.6 1.8.10-10 0.3 1.2.10-10 5.1.10-11 3.2.10-11 1.9.10-11 1.6.10-11 
 M 0.2 3.3.10-10 0.1 2.2.10-10 9.9.10-11 6.5.10-11 4.4.10-11 3.7.10-11 
 S 0.02 3.5.10-10 0.01 2.3.10-10 1.0.10-10 6.9.10-11 4.7.10-11 3.9.10-11 
Te-129m  F 0.6 2.0.10-8 0.3 1.3.10-8 5.8.10-9 3.1.10-9 1.7.10-9 1.3.10-9 
 M 0.2 3.5.10-8 0.1 2.6.10-8 1.4.10-8 9.8.10-9 8.0.10-9 6.6.10-9 
 S 0.02 3.8.10-8 0.01 2.9.10-8 1.7.10-8 1.2.10-8 9.6.10-9 7.9.10-9 
Te-131 F 0.6 2.3.10-10 0.3 2.0.10-10 9.9.10-11 5.3.10-11 3.3.10-11 2.3.10-11 
 M 0.2 2.6.10-10 0.1 1.7.10-10 8.1.10-11 5.2.10-11 3.5.10-11 2.8.10-11 
 S 0.02 2.4.10-10 0.01 1.6.10-10 7.4.10-11 4.9.10-11 3.3.10-11 2.8.10-11 
Te-131m  F 0.6 8.7.10-9 0.3 7.6.10-9 3.9.10-9 2.0.10-9 1.2.10-9 8.6.10-10 
 M 0.2 7.9.10-9 0.1 5.8.10-9 3.0.10-9 1.9.10-9 1.2.10-9 9.4.10-10 
 S 0.02 7.0.10-9 0.01 5.1.10-9 2.6.10-9 1.8.10-9 1.1.10-9 9.1.10-10 
Te-132 F 0.6 2.2.10-8 0.3 1.8.10-8 8.5.10-9 4.2.10-9 2.6.10-9 1.8.10-9 
 M 0.2 1.6.10-8 0.1 1.3.10-8 6.4.10-9 4.0.10-9 2.6.10-9 2.0.10-9 
 S 0.02 1.5.10-8 0.01 1.1.10-8 5.8.10-9 3.8.10-9 2.5.10-9 2.0.10-9 
Te-133 F 0.6 2.4.10-10 0.3 2.1.10-10 9.6.10-11 4.6.10-11 2.8.10-11 1.9.10-11 - 184 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.2 2.0.10-10 0.1 1.3.10-10 6.1.10-11 3.8.10-11 2.4.10-11 2.0.10-11 
 S 0.02 1.7.10-10 0.01 1.2.10-10 5.4.10-11 3.5.10-11 2.2.10-11 1.9.10-11 
Te-133m  F 0.6 1.0.10-9 0.3 8.9.10-10 4.1.10-10 2.0.10-10 1.2.10-10 8.1.10-11 
 M 0.2 8.5.10-10 0.1 5.8.10-10 2.8.10-10 1.7.10-10 1.1.10-10 8.7.10-11 
 S 0.02 7.4.10-10 0.01 5.1.10-10 2.5.10-10 1.6.10-10 1.0.10-10 8.4.10-11 
Te-134 F 0.6 4.7.10-10 0.3 3.7.10-10 1.8.10-10 1.0.10-10 6.0.10-11 4.7.10-11 
 M 0.2 5.5.10-10 0.1 3.9.10-10 1.9.10-10 1.2.10-10 8.1.10-11 6.6.10-11 
 S 0.02 5.6.10-10 0.01 4.0.10-10 1.9.10-10 1.3.10-10 8.4.10-11 6.8.10-11 
iodine           
I-120 F 1.0 1.3.10-9 1.0 1.0.10-9 4.8.10-10 2.3.10-10 1.4.10-10 1.0.10-10 
 M 0.2 1.1.10-9 0.1 7.3.10-10 3.4.10-10 2.1.10-10 1.3.10-10 1.0.10-10 
 S 0.02 1.0.10-9 0.01 6.9.10-10 3.2.10-10 2.0.10-10 1.2.10-10 1.0.10-10 
I-120m  F 1.0 8.6.10-10 1.0 6.9.10-10 3.3.10-10 1.8.10-10 1.1.10-10 8.2.10-11 
 M 0.2 8.2.10-10 0.1 5.9.10-10 2.9.10-10 1.8.10-10 1.1.10-10 8.7.10-11 
 S 0.02 8.2.10-10 0.01 5.8.10-10 2.8.10-10 1.8.10-10 1.1.10-10 8.8.10-11 
I-121 F 1.0 2.3.10-10 1.0 2.1.10-10 1.1.10-10 6.0.10-11 3.8.10-11 2.7.10-11 
 M 0.2 2.1.10-10 0.1 1.5.10-10 7.8.10-11 4.9.10-11 3.2.10-11 2.5.10-11 
 S 0.02 1.9.10-10 0.01 1.4.10-10 7.0.10-11 4.5.10-11 3.0.10-11 2.4.10-11 
I-123 F 1.0 8.7.10-10 1.0 7.9.10-10 3.8.10-10 1.8.10-10 1.1.10-10 7.4.10-11 
 M 0.2 5.3.10-10 0.1 3.9.10-10 2.0.10-10 1.2.10-10 8.2.10-11 6.4.10-11 
 S 0.02 4.3.10-10 0.01 3.2.10-10 1.7.10-10 1.1.10-10 7.6.10-11 6.0.10-11 
I-124 F 1.0 4.7.10-8 1.0 4.5.10-8 2.2.10-8 1.1.10-8 6.7.10-9 4.4.10-9 
 M 0.2 1.4.10-8 0.1 9.3.10-9 4.6.10-9 2.5.10-9 1.6.10-9 1.2.10-9 
 S 0.02 6.2.10-9 0.01 4.4.10-9 2.2.10-9 1.4.10-9 9.4.10-10 7.7.10-10 
I-125 F 1.0 2.0.10-8 1.0 2.3.10-8 1.5.10-8 1.1.10-8 7.2.10-9 5.1.10-9 
 M 0.2 6.9.10-9 0.1 5.6.10-9 3.6.10-9 2.6.10-9 1.8.10-9 1.4.10-9 
 S 0.02 2.4.10-9 0.01 1.8.10-9 1.0.10-9 6.7.10-10 4.8.10-10 3.8.10-10 
I-126 F 1.0 8.1.10-8 1.0 8.3.10-8 4.5.10-8 2.4.10-8 1.5.10-8 9.8.10-9 
 M 0.2 2.4.10-8 0.1 1.7.10-8 9.5.10-9 5.5.10-9 3.8.10-9 2.7.10-9 
 S 0.02 8.3.10-9 0.01 5.9.10-9 3.3.10-9 2.2.10-9 1.8.10-9 1.4.10-9 
I-128 F 1.0 1.5.10-10 1.0 1.1.10-10 4.7.10-11 2.7.10-11 1.6.10-11 1.3.10-11 
 M 0.2 1.9.10-10 0.1 1.2.10-10 5.3.10-11 3.4.10-11 2.2.10-11 1.9.10-11 
 S 0.02 1.9.10-10 0.01 1.2.10-10 5.4.10-11 3.5.10-11 2.3.10-11 2.0.10-11 
I-129 F 1.0 7.2.10-8 1.0 8.6.10-8 6.1.10-8 6.7.10-8 4.6.10-8 3.6.10-8 
 M 0.2 3.6.10-8 0.1 3.3.10-8 2.4.10-8 2.4.10-8 1.9.10-8 1.5.10-8 - 185 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 2.9.10-8 0.01 2.6.10-8 1.8.10-8 1.3.10-8 1.1.10-8 9.8.10-9 
I-130 F 1.0 8.2.10-9 1.0 7.4.10-9 3.5.10-9 1.6.10-9 1.0.10-9 6.7.10-10 
 M 0.2 4.3.10-9 0.1 3.1.10-9 1.5.10-9 9.2.10-10 5.8.10-10 4.5.10-10 
 S 0.02 3.3.10-9 0.01 2.4.10-9 1.2.10-9 7.9.10-10 5.1.10-10 4.1.10-10 
I-131 F 1.0 7.2.10-8 1.0 7.2.10-8 3.7.10-8 1.9.10-8 1.1.10-8 7.4.10-9 
 M 0.2 2.2.10-8 0.1 1.5.10-8 8.2.10-9 4.7.10-9 3.4.10-9 2.4.10-9 
 S 0.02 8.8.10-9 0.01 6.2.10-9 3.5.10-9 2.4.10-9 2.0.10-9 1.6.10-9 
I-132 F 1.0 1.1.10-9 1.0 9.6.10-10 4.5.10-10 2.2.10-10 1.3.10-10 9.4.10-11 
 M 0.2 9.9.10-10 0.1 7.3.10-10 3.6.10-10 2.2.10-10 1.4.10-10 1.1.10-10 
 S 0.02 9.3.10-10 0.01 6.8.10-10 3.4.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
I-132m  F 1.0 9.6.10-10 1.0 8.4.10-10 4.0.10-10 1.9.10-10 1.2.10-10 7.9.10-11 
 M 0.2 7.2.10-10 0.1 5.3.10-10 2.6.10-10 1.6.10-10 1.1.10-10 8.7.10-11 
 S 0.02 6.6.10-10 0.01 4.8.10-10 2.4.10-10 1.6.1 0-10 1.1.10-10 8.5.10-11 
I-133 F 1.0 1.9.10-8 1.0 1.8.10-8 8.3.10-9 3.8.10-9 2.2.10-9 1.5.10-9 
 M 0.2 6.6.10-9 0.1 4.4.10-9 2.1.10-9 1.2.10-9 7.4.10-10 5.5.10-10 
 S 0.02 3.8.10-9 0.01 2.9.10-9 1.4.10-9 9.0.10-10 5.3.10-10 4.3.10-10 
I-134 F 1.0 4.6.10-10 1.0 3.7.10-10 1.8.10-10 9.7.10-11 5.9.10-11 4.5.10-11 
 M 0.2 4.8.10-10 0.1 3.4.10-10 1.7.10-10 1.0.10-10 6.7.10-11 5.4.10-11 
 S 0.02 4.8.10-10 0.01 3.4.10-10 1.7.10-10 1.1.10-10 6.8.10-11 5.5.10-11 
I-135 F 1.0 4.1.10-9 1.0 3.7.10-9 1.7.10-9 7.9.10-10 4.8.10-10 3.2.10-10 
 M 0.2 2.2.10-9 0.1 1.6.10-9 7.8.10-10 4.7.10-10 3.0.10-10 2.4.10-10 
 S 0.02 1.8.10-9 0.01 1.3.10-9 6.5.10-10 4.2.10-10 2.7.10-10 2.2.10-10 
caesium           
Cs-125 F 1.0 1.2.10-10 1.0 8.3.10-11 3.9.10-11 2.4.10-11 1.4.10-11 1.2.10-11 
 M 0.2 2.0.10-10 0.1 1.4.10-10 6.5.10-11 4.2.10-11 2.7.10-11 2.2.10-11 
 S 0.02 2.1.10-10 0.01 1.4.10-10 6.8.10-11 4.4.10-11 2.8.10-11 2.3.10-11 
Cs-127 F 1.0 1.6.10-10 1.0 1.3.10-10 6.9.10-11 4.2.10-11 2.5.10-11 2.0.10-11 
 M 0.2 2.8.10-10 0.1 2.2.10-10 1.1.10-10 7.3.10-11 4.6.10-11 3.6.10-11 
 S 0.02 3.0.10-10 0.01 2.3.10-10 1.2.10-10 7.6.10-11 4.8.10-11 3.8.10-11 
Cs-129 F 1.0 3.4.10-10 1.0 2.8.10-10 1.4.10-10 8.7.10-11 5.2.10-11 4.2.10-11 
 M 0.2 5.7.10-10 0.1 4.6.10-10 2.4.10-10 1.5.10-10 9.1.10-11 7.3.10-11 
 S 0.02 6.3.10-10 0.01 4.9.10-10 2.5.10-10 1.6.10-10 9.7.10-11 7.7.10-11 
Cs-130 F 1.0 8.3.10-11 1.0 5.6.10-11 2.5.10-11 1.6.10-11 9.4.10-12 7.8.10-12 
 M 0.2 1.3.10-10 0.1 8.7.10-11 4.0.10-11 2.5.10-11 1.6.10-11 1.4.10-11 
 S 0.02 1.4.10-10 0.01 9.0.10-11 4.1.10-11 2.6.10-11 1.7.10-11 1.4.10-11 - 186 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Cs-131 F 1.0 2.4.10-10 1.0 1.7.10-10 8.4.10-11 5.3.10-11 3.2.10-11 2.7.10-11 
 M 0.2 3.5.10-10 0.1 2.6.10-10 1.4.10-10 8.5.10-11 5.5.10-11 4.4.10-11 
 S 0.02 3.8.10-10 0.01 2.8.10-10 1.4.10-10 9.1.10-11 5.9.10-11 4.7.10-11 
Cs-132 F 1.0 1.5.10-9 1.0 1.2.10-9 6.4.10-10 4.1.10-10 2.7.10-10 2.3.10-10 
 M 0.2 1.9.10-9 0.1 1.5.10-9 8.4.10-10 5.4.10-10 3.7.10-10 2.9.10-10 
 S 0.02 2.0.10-9 0.01 1.6.10-9 8.7.10-10 5.6.10-10 3.8.10-10 3.0.10-10 
Cs-134 F 1.0 1.1.10-8 1.0 7.3.10-9 5.2.10-9 5.3.10-9 6.3.10-9 6.6.10-9 
 M 0.2 3.2.10-8 0.1 2.6.10-8 1.6.10-8 1.2.10-8 1.1.10-8 9.1.10-9 
 S 0.02 7.0.10-8 0.01 6.3.10-8 4.1.10-8 2.8.10-8 2.3.10-8 2.0.10-8 
Cs-134m  F 1.0 1.3.10-10 1.0 8.6.10-11 3.8.10-11 2.5.10-11 1.6.10-11 1.4.10-11 
 M 0.2 3.3.10-10 0.1 2.3.10-10 1.2.10-10 8.3.10-11 6.6.10-11 5.4.10-11 
 S 0.02 3.6.10-10 0.01 2.5.10-10 1.3.10-10 9.2.10-11 7.4.10-11 6.0.10-11 
Cs-135 F 1.0 1.7.10-9 1.0 9.9.10-10 6.2.10-10 6.1.10-10 6.8.10-10 6.9.10-10 
 M 0.2 1.2.10-8 0.1 9.3.10-9 5.7.10-9 4.1.10-9 3.8.10-9 3.1.10-9 
 S 0.02 2.7.10-8 0.01 2.4.10-8 1.6.10-8 1.1.10-8 9.5.10-9 8.6.10-9 
Cs-135m  F 1.0 9.2.10-11 1.0 7.8.10-11 4.1.10-11 2.4.10-11 1.5.10-11 1.2.10-11 
 M 0.2 1.2.10-10 0.1 9.9.10-11 5.2.10-11 3.2.10-11 1.9.10-11 1.5.10-11 
 S 0.02 1.2.10-10 0.01 1.0.10-10 5.3.10-11 3.3.10-11 2.0.10-11 1.6.10-11 
Cs-136 F 1.0 7.3.10-9 1.0 5.2.10-9 2.9.10-9 2.0.10-9 1.4.10-9 1.2.10-9 
 M 0.2 1.3.10-8 0.1 1.0.10-8 6.0.10-9 3.7.10-9 3.1.10-9 2.5.10-9 
 S 0.02 1.5.10-8 0.01 1.1.10-8 5.7.1 0-9 4.1.10-9 3.5.10-9 2.8.10-9 
Cs-137 F 1.0 8.8.10-9 1.0 5.4.10-9 3.6.10-9 3.7.10-9 4.4.10-9 4.6.10-9 
 M 0.2 3.6.10-8 0.1 2.9.10-8 1.8.10-8 1.3.10-8 1.1.10-8 9.7.10-9 
 S 0.02 1.1.10-7 0.01 1.0.10-7 7.0.10-8 4.8.10-8 4.2.10-8 3.9.10-8 
Cs-138 F 1.0 2.6.1 0-10 1.0 1.8.10-10 8.1.10-11 5.0.10-11 2.9.10-11 2.4.10-11 
 M 0.2 4.0.10-10 0.1 2.7.10-10 1.3.10-10 7.8.10-11 4.9.10-11 4.1.10-11 
 S 0.02 4.2.10-10 0.01 2.8.10-10 1.3.10-10 8.2.10-11 5.1.10-11 4.3.10-11 
barium           
Ba-126 F 0.6 6.7.10-10 0.3**  5.2.10-10 2.4.10-10 1.4.10-10 6.9.10-11 7.4.10-11 
 M 0.2 1.0.10-9 0.1 7.0.10-10 3.2.10-10 2.0.10-10 1.2.10-10 1.0.10-10 
 S 0.02 1.1.10-9 0.01 7.2.10-10 3.3.10-10 2.1.10-10 1.3.10-10 1.1.10-10 
Ba-128 F 0.6 5.9.10-9 0.3**  5.4.10-9 2.5.10-9 1.4.10-9 7.4.10-10 7.6.10-10 
 M 0.2 1.1.10-8 0.1 7.8.10-9 3.7.10-9 2.4.10-9 1.5.10-9 1.3.10-9 
 S 0.02 1.2.10-8 0.01 8.3.10-9 4.0.10-9 2.6.10-9 1.6.10-9 1.4.10-9 
Ba-131 F 0.6 2.1.10-9 0.3**  1.4.10-9 7.1.10-10 4.7.10-10 3.1.10-10 2.2.10-10 - 187 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.2 3.7.10-9 0.1 3.1.10-9 1.6.10-9 1.1.10-9 9.7.10-10 7.6.10-10 
 S 0.02 4.0.10-9 0.01 3.0.10-9 1.8.10-9 1.3.10-9 1.1.10-9 8.7.10-10 
Ba-131m  F 0.6 2.7.10-11 0.3**  2.1.10-11 1.0.10-11 6.7.10-12 4.7.10-12 4.0.10-12 
 M 0.2 4.8.10-11 0.1 3.3.10-11 1.7.10-11 1.2.10-11 9.0.10-12 7.4.10-12 
 S 0.02 5.0.10-11 0.01 3.5.10-11 1.8.10-11 1.2.10-11 9.5.10-12 7.8.10-12 
Ba-133 F 0.6 1.1.10-8 0.3**  4.5.10-9 2.6.10-9 3.7.10-9 6.0.10-9 1.5.10-9 
 M 0.2 1.5.10-8 0.1 1.0.10-8 6.4.10-9 5.1.10-9 5.5.10-9 3.1.10-9 
 S 0.02 3.2.10-8 0.01 2.9.10-8 2.0.10-8 1.3.10-8 1.1.10-8 1.0.10-8 
Ba-133m  F 0.6 1.4.10-9 0.3**  1.1.10-9 4.9.10-10 3.1.10-10 1.5.10-10 1.8.10-10 
 M 0.2 3.0.10-9 0.1 2.2.10-9 1.0.10-9 6.9.10-10 5.2.10-10 4.2.10-10 
 S 0.02 3.1.10-9 0.01 2.4.10-9 1.1.10-9 7.6.10-10 5.8.10-10 4.6.10-10 
Ba-135m  F 0.6 1.1.10-9 0.3**  1.0.10-9 4.6.10-10 2.5.10-10 1.2.10-10 1.4.10-10 
 M 0.2 2.4.10-9 0.1 1.8.10-9 8.9.10-10 5.4.10-10 4.1.10-10 3.3.10-10 
 S 0.02 2.7.10-9 0.01 1.9.10-9 8.6.10-10 5.9.10-10 4.5.10-10 3.6.10-10 
Ba-139 F 0.6 3.3.10-10 0.3**  2.4.10-10 1.1.10-10 6.0.10-11 3.1.10-11 3.4.10-11 
 M 0.2 5.4.10-10 0.1 3.5.10-10 1.6.10-10 1.0.10-10 6.6.10-11 5.6.10-11 
 S 0.02 5.7.10-10 0.01 3.6.10-10 1.6.10-10 1.1.10-10 7.0.10-11 5.9.10-11 
Ba-140 F 0.6 1.4.10-8 0.3**  7.8.10-9 3.6.10-9 2.4.10-9 1.6.10-9 1.0.10-9 
 M 0.2 2.7.10-8 0.1 2.0.10-8 1.1.10-8 7.6.10-9 6.2.10-9 5.1.10-9 
 S 0.02 2.9.10-8 0.01 2.2.10-8 1.2.10-8 8.6.10-9 7.1.10-9 5.8.10-9 
Ba-141 F 0.6 1.9.10-10 0.3**  1.4.10-10 6.4.10-11 3.8.10-11 2.1.10-11 2.1.10-11 
 M 0.2 3.0.10-10 0.1 2.0.10-10 9.3.10-11 5.9.10-11 3.8.10-11 3.2.10-11 
 S 0.02 3.2.10-10 0.01 2.1.10-10 9.7.10-11 6.2.10-11 4.0.10-11 3.4.10-11 
Ba-142 F 0.6 1.3.10-10 0.3**  9.6.10-11 4.5.10-11 2.7.10-11 1.6.10-11 1.5.10-11 
 M 0.2 1.8.10-10 0.1 1.3.10-10 6.1.10-11 3.9.10-11 2.5.10-11 2.1.10-11 
 S 0.02 1.9.10-10 0.01 1.3.10-10 6.2.10-11 4.0.10-11 2.6.10-11 2.2.10-11 
lanthanum           
La-131 F 0.005  1.2.10-10 5.0.10-4 8.7.10-11 4.2.10-11 2.6.10-11 1.5.10-11 1.3.10-11 
 M 0.005  1.8.10-10 5.0.10-4 1.3.10-10 6.4.10-11 4.1.10-11 2.8.10-11 2.3.10-11 
La-132 F 0.005  1.0.10-9 5.0.10-4 7.7.10-10 3.7.10-10 2.2.10-10 1.2.10-10 1.0.10-10 
 M 0.005  1.5.10-9 5.0.10-4 1.1.10-9 5.4.10-10 3.4.10-10 2.0.10-10 1.6.10-10 
La-135 F 0.005  1.0.10-10 5.0.10-4 7.7.10-11 3.8.10-11 2.3.10-11 1.3.10-11 1.0.10-11 
 M 0.005  1.3.10-10 5.0.10-4 1.0.10-10 4.9.10-11 3.0.10-11 1.7.10-11 1.4.10-11 
La-137 F 0.005  2.5.10-8 5.0.10-4 2.3.10-8 1.5.10-8 1.1.10-8 8.9.10-9 8.7.10-9 
 M 0.005  8.6.10-9 5.0.10-4 8.1.10-9 5.6.10-9 4.0.10-9 3.6.10-9 3.6.10-9 - 188 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
La-138 F 0.005  3.7.10-7 5.0.10-4 3.5.10-7 2.4.10-7 1.8.10-7 1.6.10-7 1.5.10-7 
 M 0.005  1.3.10-7 5.0.10-4 1.2.10-7 9.1.10-8 6.8.10-8 6.4.10-8 6.4.10-8 
La-140 F 0.005  5.8.10-9 5.0.10-4 4.2.10-9 2.0.10-9 1.2.10-9 6.9.10-10 5.7.10-10 
 M 0.005  8.8.10-9 5.0.10-4 6.3.10-9 3.1.10-9 2.0.10-9 1.3.10-9 1.1.10-9 
La-141 F 0.005  8.6.10-10 5.0.10-4 5.5.10-10 2.3.10-10 1.4.10-10 7.5.10-11 6.3.10-11 
 M 0.005  1.4.10-9 5.0.10-4 9.3.10-10 4.3.10-10 2.8.10-10 1.8.10-10 1.5.10-10 
La-142 F 0.005  5.3.10-10 5.0.10-4 3.8.10-10 1.8.10-10 1.1.10-10 6.3.10-11 5.2.10-11 
 M 0.005  8.1.10-10 5.0.10-4 5.7.10-10 2.7.10-10 1.7.10-10 1.1.10-10 8.9.10-11 
La-143 F 0.005  1.4.10-10 5.0.10-4 8.6.10-11 3.7.10-11 2.3.10-11 1.4.10-11 1.2.10-11 
 M 0.005  2.1.10-10 5.0.10-4 1.3.10-10 6.0.10-11 3.9.10-11 2.5.10-11 2.1.10-11 
ceriu m          
Ce-134 F 0.005  7.6.10-9 5.0.10-4 5.3.10-9 2.3.10-9 1.4.10-9 7.7.10-10 5.7.10-10 
 M 0.005  1.1.10-8 5.0.10-4 7.6.10-9 3.7.10-9 2.4.10-9 1.5.10-9 1.3.10-9 
 S 0.005  1.2.10-8 5.0.10-4 8.0.10-9 3.8.10-9 2.5.10-9 1.6.10-9 1.3.10-9 
Ce-135 F 0.005  2.3.10-9 5.0.10-4 1.7.10-9 8.5.10-10 5.3.10-10 3.0.10-10 2.4.10-10 
 M 0.005  3.6.10-9 5.0.10-4 2.7.10-9 1.4.10-9 8.9.10-10 5.9.10-10 4.8.10-10 
 S 0.005  3.7.10-9 5.0.10-4 2.8.10-9 1.4.10-9 9.4.10-10 6.3.10-10 5.0.10-10 
Ce-137 F 0.005  7.5.10-11 5.0.10-4 5.6.10-11 2.7.10-11 1.6.10-11 8.7.10-12 7.0.10-12 
 M 0.005  1.1.10-10 5.0.10-4 7.6.10-11 3.6.10-11 2.2.10-11 1.2.10-11 9.8.10-12 
 S 0.005  1.1.10-10 5.0.10-4 7.8.10-11 3.7.10-11 2.3.10-11 1.3.10-11 1.0.10-11 
Ce-137m  F 0.005  1.6.10-9 5.0.10-4 1.1.10-9 4.6.10-10 2.8.10-10 1.5.10-10 1.2.10-10 
 M 0.005  3.1.10-9 5.0.10-4 2.2.10-9 1.1.10-9 6.7.10-10 5.1.10-10 4.1.10-10 
 S 0.005  3.3.10-9 5.0.10-4 2.3.10-9 1.0.10-9 7.3.10-10 5.6.10-10 4.4.10-10 
Ce-139 F 0.005  1.1.10-8 5.0.10-4 8.5.10-9 4.5.10-9 2.8.10-9 1.8.10-9 1.5.10-9 
 M 0.005  7.5.10-9 5.0.10-4 6.1.10-9 3.6.10-9 2.5.10-9 2.1.10-9 1.7.10-9 
 S 0.005  7.8.10-9 5.0.10-4 6.3.10-9 3.9.10-9 2.7.10-9 2.4.10-9 1.9.10-9 
Ce-141 F 0.005  1.1.10-8 5.0.10-4 7.3.10-9 3.5.10-9 2.0.10-9 1.2.10-9 9.3.10-10 
 M 0.005  1.4.10-8 5.0.10-4 1.1.10-8 6.3.10-9 4.6.10-9 4.1.10-9 3.2.10-9 
 S 0.005  1.6.10-8 5.0.10-4 1.2.10-8 7.1.10-9 5.3.10-9 4.8.10-9 3.8.10-9 
Ce-143 F 0.005  3.6.10-9 5.0.10-4 2.3.10-9 1.0.10-9 6.2.10-10 3.3.10-10 2.7.10-10 
 M 0.005  5.6.10-9 5.0.10-4 3.9.10-9 1.9.10-9 1.3.1 0-9 9.3.10-10 7.5.10-10 
 S 0.005  5.9.10-9 5.0.10-4 4.1.10-9 2.1.10-9 1.4.10-9 1.0.10-9 8.3.10-10 
Ce-144 F 0.005  3.6.10-7 5.0.10-4 2.7.10-7 1.4.10-7 7.8.10-8 4.8.10-8 4.0.10-8 
 M 0.005  1.9.10-7 5.0.10-4 1.6.10-7 8.8.10-8 5.5.10-8 4.1.10-8 3.6.10-8 
 S 0.005 2.1.10-7 5.0.10-4 1.8.10-7 1.1.10-7 7.3.10-8 5.8.10-8 5.3.10-8 - 189 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
praseodymium           
Pr-136 M 0.005  1.3.10-10 5.0.10-4 8.8.10-11 4.2.10-11 2.6.10-11 1.6.10-11 1.3.10-11 
 S 0.005  1.3.10-10 5.0.10-4 9.0.10-11 4.3.10-11 2.7.10-11 1.7.10-11 1.4.10-11 
Pr-137 M 0.005  1.8.10-10 5.0.10-4 1.3.10-10 6.1.10-11 3.9.10-11 2.4.10-11 2.0.10-11 
 S 0.005  1.9.10-10 5.0.10-4 1.3.10-10 6.4.10-11 4.0.10-11 2.5.10-11 2.1.10-11 
Pr-138m  M 0.005  5.9.10-10 5.0.10-4 4.5.10-10 2.3.10-10 1.4.10-10 9.0.10-11 7.2.10-11 
 S 0.005 6.0.10-10 5.0.10-4 4.7.10-10 2.4.10-10 1.5.10-10 9.3.10-11 7.4.10-11 
Pr-139 M 0.005  1.5.10-10 5.0.10-4 1.1.10-10 5.5.10-11 3.5.10-11 2.3.10-11 1.8.10-11 
 S 0.005  1.6.10-10 5.0.10-4 1.2.10-10 5.7.10-11 3.7.10-11 2.4.10-11 2.0.10-11 
Pr-142 M 0.005  5.3.1 0-9 5.0.10-4 3.5.10-9 1.6.10-9 1.0.10-9 6.2.10-10 5.2.10-10 
 S 0.005  5.5.10-9 5.0.10-4 3.7.10-9 1.7.10-9 1.1.10-9 6.6.10-10 5.5.10-10 
Pr-142m  M 0.005  6.7.10-11 5.0.10-4 4.5.10-11 2.0.10-11 1.3.10-11 7.9.10-12 6.6.10-12 
 S 0.005  7.0.10-11 5.0.10-4 4.7.10-11 2.2.10-11 1.4.10-11 8.4.10-12 7.0.10-12 
Pr-143 M 0.005  1.2.10-8 5.0.10-4 8.4.10-9 4.6.10-9 3.2.10-9 2.7.10-9 2.2.10-9 
 S 0.005  1.3.10-8 5.0.10-4 9.2.10-9 5.1.10-9 3.6.10-9 3.0.10-9 2.4.10-9 
Pr-144 M 0.005  1.9.10-10 5.0.10-4 1.2.10-10 5.0.10-11 3.2.1 0-11 2.1.10-11 1.8.10-11 
 S 0.005  1.9.10-10 5.0.10-4 1.2.10-10 5.2.10-11 3.4.10-11 2.1.10-11 1.8.10-11 
Pr-145 M 0.005  1.6.10-9 5.0.10-4 1.0.10-9 4.7.10-10 3.0.10-10 1.9.10-10 1.6.10-10 
 S 0.005  1.6.10-9 5.0.10-4 1.1.10-9 4.9.10-10 3.2.10-10 2.0.10-10 1.7.10-10 
Pr-147 M 0.005  1.5.10-10 5.0.10-4 1.0.10-10 4.8.10-11 3.1.10-11 2.1.10-11 1.8.10-11 
 S 0.005  1.6.10-10 5.0.10-4 1.1.10-10 5.0.10-11 3.3.10-11 2.2.10-11 1.8.10-11 
neodymium           
Nd-136 M 0.005  4.6.10-10 5.0.10-4 3.2.10-10 1.6.10-10 9.8.10-11 6.3.10-11 5.1.10-11 
 S 0.005  4.8.10-10 5.0.10-4 3.3.10-10 1.6.10-10 1.0.10-10 6.6.10-11 5.4.10-11 
Nd-138 M 0.005  2.3.10-9 5.0.10-4 1.7.10-9 7.7.10-10 4.8.10-10 2.8.10-10 2.3.10-10 
 S 0.005  2.4.10-9 5.0.10-4 1.8.10-9 8.0.10-10 5.0.10-10 3.0.10-10 2.5.10-10 
Nd-139 M 0.005  9.0.10-11 5.0.10-4 6.2.10-11 3.0.10-11 1.9.10-11 1.2.10-11 9.9.10-12 
 S 0.005  9.4.10-11 5.0.10-4 6.4.10-11 3.1.10-11 2.0.10-11 1.3.10-11 1.0.10-11 
Nd-139m  M 0.005  1.1.10-9 5.0.10-4 8.8.10-10 4.5.10-10 2.9.10-10 1.8.10-10 1.5.10-10 
 S 0.005  1.2.10-9 5.0.10-4 9.1.10-10 4.6.10-10 3.0.10-10 1.9.10-10 1.5.10-10 
Nd-141 M 0.005  4.1.10-11 5.0.10-4 3.1.10-11 1.5.10-11 9.6.10-12 6.0.10-12 4.8.10-12 
 S 0.005  4.3.10-11 5.0.10-4 3.2.10-11 1.6.10-11 1.0.10-11 6.2.10-12 5.0.10-12 
Nd-147 M 0.005  1.1.10-8 5.0.10-4 8.0.10-9 4.5.10-9 3.2.10-9 2.6.10-9 2.1.10-9 
 S 0.005  1.2.10-8 5.0.10-4 8.6.10-9 4.9.10-9 3.5.10-9 3.0.10-9 2.4.10-9 
Nd-149 M 0.005  6.8.10-10 5.0.10-4 4.6.10-10 2.2.10-10 1.5.10-10 1.0.10-10 8.4.10-11 - 190 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.005  7.1.10-10 5.0.10-4 4.8.10-10 2.3.10-10 1.5.10-10 1.1.10-10 8.9.10-11 
Nd-151 M 0.005  1.5.10-10 5.0.10-4 9.9.10-11 4.6.10-11 3.0.10-11 2.0.10-11 1.7.10-11 
 S 0.005  1.5.10-10 5.0.10-4 1.0.10-10 4.8.10-11 3.1.10-11 2.1.10-11 1.7.10-11 
promethium           
Pm-141 M 0.005  1.4.10-10 5.0.10-4 9.4.10-11 4.3.10-11 2.7.10-11 1.7.10-11 1.4.10-11 
 S 0.005  1.5.10-10 5.0.10-4 9.7.10-11 4.4.10-11 2.8.10-11 1.8.10-11 1.5.10-11 
Pm-143 M 0.005  6.2.10-9 5.0.10-4 5.4.10-9 3.3.10-9 2.2.10-9 1.7.10-9 1.5.10-9 
 S 0.005  5.5.10-9 5.0.10-4 4.8.10-9 3.1.10-9 2.1.10-9 1.7.10-9 1.4.10-9 
Pm-144 M 0.005  3.1.10-8 5.0.10-4 2.8.10-8 1.8.10-8 1.2.10-8 9.3.10-9 8.2.10-9 
 S 0.005  2.6.10-8 5.0.10-4 2.4.10-8 1.6.10-8 1.1.10-8 8.9.10-9 7.5.10-9 
Pm-145 M 0.005  1.1.10-8 5.0.10-4 9.8.10-9 6.4.10-9 4.3.10-9 3.7.10-9 3.6.10-9 
 S 0.005  7.1.10-9 5.0.10-4 6.5.10-9 4.3.10-9 2.9.10-9 2.4.10-9 2.3.10-9 
Pm-146 M 0.005  6.4.10-8 5.0.10-4 5.9.10-8 3.9.10-8 2.6.10-8 2.2.10-8 2.1.10-8 
 S 0.005  5.3.10-8 5.0.10-4 4.9.10-8 3.3.10-8 2.2.10-8 1.9.10-8 1.7.10-8 
Pm-147 M 0.005  2.1.10-8 5.0.10-4 1.8.10-8 1.1.10-8 7.0.10-9 5.7.10-9 5.0.10-9 
 S 0.005  1.9.10-8 5.0.10-4 1.6.10-8 1.0.10-8 6.8.10-9 5.8.10-9 4.9.10-9 
Pm-148 M 0.005  1.5.10-8 5.0.10-4 1.0.10-8 5.2.10-9 3.4.10-9 2.4.10-9 2.0.10-9 
 S 0.005  1.5.10-8 5.0.10-4 1.1.10-8 5.5.10-9 3.7.10-9 2.6.10-9 2.2.10-9 
Pm-148m  M 0.005  2.4.10-8 5.0.10-4 1.9.10-8 1.1.10-8 7.7.10-9 6.3.10-9 5.1.10-9 
 S 0.005  2.5.10-8 5.0.10-4 2.0.10-8 1.2.10-8 8.3.10-9 7.1.10-9 5.7.10-9 
Pm-149 M 0.005  5.0.10-9 5.0.10-4 3.5.10-9 1.7.10-9 1.1.10-9 8.3.10-10 6.7.10-10 
 S 0.005  5.3.10-9 5.0.10-4 3.6.10-9 1.8.10-9 1.2.10-9 9.0.10-10 7.3.10-10 
Pm-150 M 0.005  1.2.10-9 5.0.10-4 7.9.10-10 3.8.10-10 2.4.10-10 1.5.10-10 1.2.10-10 
 S 0.005  1.2.10-9 5.0.10-4 8.2.10-10 3.9.10-10 2.5.10-10 1.6.10-10 1.3.10-10 
Pm-151 M 0.005  3.3.10-9 5.0.10-4 2.5.10-9 1.2.10-9 8.3.10-10 5.3.10-10 4.3.10-10 
 S 0.005  3.4.10-9 5.0.10-4 2.6.10-9 1.3.10-9 7.9.10-10 5.7.10-10 4.6.10-10 
samarium           
Sm-141 M 0.005  1.5.10-10 5.0.10-4 1.0.10-10 4.7.10-11 2.9.10-11 1.8.10-11 1.5.10-11 
Sm-141m  M 0.005  3.0.10-10 5.0.10-4 2.1.10-10 9.7.10-11 6.1.10-11 3.9.10-11 3.2.10-11 
Sm-142 M 0.005  7.5.10-10 5.0.10-4 4.8.10-10 2.2.10-10 1.4.10-10 8.5.10-11 7.1.10-11 
Sm-145 M 0.005  8.1.10-9 5.0.10-4 6.8.10-9 4.0.10-9 2.5.10-9 1.9.10-9 1.6.10-9 
Sm-146 M 0.005  2.7.10-5 5.0.10-4 2.6.10-5 1.7.10-5 1.2.10-5 1.1.10-5 1.1.10-5 
Sm-147 M 0.005  2.5.10-5 5.0.10-4 2.3.10-5 1.6.10-5 1.1.10-5 9.6.10-6 9.6.10-6 
Sm-151 M 0.005  1.1.10-8 5.0.10-4 1.0.10-8 6.7.10-9 4.5.10-9 4.0.10-9 4.0.10-9 
Sm-153 M 0.005  4.2.10-9 5.0.10-4 2.9.10-9 1.5.10-9 1.0.10-9 7.9.10-10 6.3.10-10 - 191 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Sm-155 M 0.005  1.5.10-10 5.0.10-4 9.9.10-11 4.4.10-11 2.9.10-11 2.0.10-11 1.7.10-11 
Sm-156 M 0.005  1.6.10-9 5.0.10-4 1.1.10-9 5.8.10-10 3.5.10-10 2.7.10-10 2.2.10-10 
europium           
Eu-145 M 0.005  3.6.10-9 5.0.10-4 2.9.10-9 1.6.10-9 1.0.10-9 6.8.10-10 5.5.10-10 
Eu-146 M 0.005  5.5.10-9 5.0.10-4 4.4.10-9 2.4.10-9 1.5.10-9 1.0.10-9 8.0.10-10 
Eu-147 M 0.005  4.9.10-9 5.0.10-4 3.7.10-9 2.2.10-9 1.6.10-9 1.3.10-9 1.1.10-9 
Eu-148 M 0.005  1.4.10-8 5.0.10-4 1.2.10-8 6.8.10-9 4.6.10-9 3.2.10-9 2.6.10-9 
Eu-149 M 0.005  1.6.10-9 5.0.10-4 1.3.10-9 7.3.10-10 4.7.10-10 3.5.10-10 2.9.10-10 
Eu-150 M 0.005  1.1.10-7 5.0.10-4 1.1.10-7 7.8.10-8 5.7.10-8 5.3.10-8 5.3.10-8 
Eu-150m  M 0.005  1.6.10-9 5.0.10-4 1.1.10-9 5.2.10-10 3.4.10-10 2.3.10-10 1.9.10-10 
Eu-152 M 0.005  1.1.10-7 5.0.10-4 1.0.10-7 7.0.10-8 4.9.10-8 4.3.10-8 4.2.10-8 
Eu-152m  M 0.005  1.9.10-9 5.0.10-4 1.3.10-9 6.6.10-10 4.2.10-10 2.4.10-10 2.2.10-10 
Eu-154 M 0.005  1.6.10-7 5.0.10-4 1.5.10-7 9.7.10-8 6.5.10-8 5.6.10-8 5.3.10-8 
Eu-155 M 0.005  2.6.10-8 5.0.10-4 2.3.10-8 1.4.10-8 9.2.10-9 7.6.10-9 6.9.10-9 
Eu-156 M 0.005  1.9.10-8 5.0.10-4 1.4.10-8 7.7.10-9 5.3.10-9 4.2.10-9 3.4.10-9 
Eu-157 M 0.005  2.5.10-9 5.0.10-4 1.9.10-9 8.9.10-10 5.9.10-10 3.5.10-10 2.8.10-10 
Eu-158 M 0.005  4.3.10-10 5.0.10-4 2.9.10-10 1.3.10-10 8.5.10-11 5.6.10-11 4.7.10-11 
gadolinium           
Gd-145 F 0.005  1.3.10-10 5.0.10-4 9.6.10-11 4.7.10-11 2.9.10-11 1.7.10-11 1.4.10-11 
 M 0.005  1.8.10-10 5.0.10-4 1.3.10-10 6.2.10-11 3.9.10-11 2.4.10-11 2.0.10-11 
Gd-146 F 0.005  2.9.10-8 5.0.10-4 2.3.10-8 1.2.10-8 7.8.10-9 5.1.10-9 4.4.10-9 
 M 0.005  2.8.10-8 5.0.10-4 2.2.10-8 1.3.10-8 9.3.10-9 7.9.10-9 6.4.10-9 
Gd-147 F 0.005  2.1.10-9 5.0.10-4 1.7.10-9 8.4.10-10 5.3.10-10 3.1.10-10 2.6.10-10 
 M 0.005 2.8.10-9 5.0.10-4 2.2.10-9 1.1.10-9 7.5.10-10 5.1.10-10 4.0.10-10 
Gd-148 F 0.005  8.3.10-5 5.0.10-4 7.6.10-5 4.7.10-5 3.2.10-5 2.6.10-5 2.6.10-5 
 M 0.005  3.2.10-5 5.0.10-4 2.9.10-5 1.9.10-5 1.3.10-5 1.2.10-5 1.1.10-5 
Gd-149 F 0.005  2.6.10-9 5.0.10-4 2.0.10-9 8.0.10-10 5.1.10-10 3.1.10-10 2.6.10-10 
 M 0.005  3.6.10-9 5.0.10-4 3.0.10-9 1.5.10-9 1.1.10-9 9.2.10-10 7.3.10-10 
Gd-151 F 0.005  6.3.10-9 5.0.10-4 4.9.10-9 2.5.10-9 1.5.10-9 9.2.10-10 7.8.10-10 
 M 0.005  4.5.10-9 5.0.10-4 3.5.10-9 2.0.10-9 1.3.10-9 1.0.10-9 8.6.10-10 
Gd-152 F 0.005  5.9.10-5 5.0.10-4 5.4.10-5 3.4.10-5 2.4.10-5 1.9.10-5 1.9.10-5 
 M 0.005  2.1.10-5 5.0.10-4 1.9.10-5 1.3.10-5 8.9.10-6 7.9.10-6 8.0.10-6 
Gd-153 F 0.005  1.5.10-8 5.0.10-4 1.2.10-8 6.5.10-9 3.9.10-9 2.4.10-9 2.1.10-9 
 M 0.005  9.9.10-9 5.0.10-4 7.9.10-9 4.8.10-9 3.1.10-9 2.5.10-9 2.1.10-9 
Gd-159 F 0.005  1.2.10-9 5.0.10-4 8.9.10-10 3.8.10-10 2.3.10-10 1.2.10-10 1.0.10-10 - 192 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.005  2.2.10-9 5.0.10-4 1.5.10-9 7.3.10-10 4.9.10-10 3.4.10-10 2.7.10-10 
terbium           
Tb-147 M 0.005  6.7.10-10 5.0.10-4 4.8.10-10 2.3.10-10 1.5.10-10 9.3.10-11 7.6.10-11 
Tb-149 M 0.005  2.1.10-8 5.0.10-4 1.5.10-8 9.6.10-9 6.6.10-9 5.8.10-9 4.9.10-9 
Tb-150 M 0.005  1.0.10-9 5.0.10-4 7.4.10-10 3.5.10-10 2.2.10-10 1.3.10-10 1.1.10-10 
Tb-151 M 0.005  1.6.10-9 5.0.10-4 1.2.10-9 6.3.10-10 4.2.10-10 2.8.10-10 2.3.10-10 
Tb-153 M 0.005  1.4.10-9 5.0.10-4 1.0.10-9 5.4.10-10 3.6.10-10 2.3.10-10 1.9.10-10 
Tb-154 M 0.005  2.7.10-9 5.0.10-4 2.1.10-9 1.1.10-9 7.1.10-10 4.5.10-10 3.6.10-10 
Tb-155 M 0.005  1.4.10-9 5.0.10-4 1.0.10-9 5.6.10-10 3.4.10-10 2.7.10-10 2.2.10-10 
Tb-156 M 0.005  7.0.10-9 5.0.10-4 5.4.10-9 3.0.10-9 2.0.10-9 1.5.10-9 1.2.10-9 
Tb-156m  M 0.005  1.1.10-9 5.0.10-4 9.4.10-10 4.7.10-10 3.3.10-10 2.7.10-10 2.1.10-10 
Tb-156m’  M 0.005  6.2.10-10 5.0.10-4 4.5.10-10 2.4.10-10 1.7.10-10 1.2.10-10 9.6.10-11 
Tb-157 M 0.005  3.2.10-9 5.0.10-4 3.0.10-9 2.0.10-9 1.4.10-9 1.2.10-9 1.2.10-9 
Tb-158 M 0.005  1.1.10-7 5.0.10-4 1.0.10-7 7.0.10-8 5.1.10-8 4.7.10-8 4.6.10-8 
Tb-160 M 0.005  3.2.10-8 5.0.10-4 2.5.10-8 1.5.10-8 1.0.10-8 8.6.10-9 7.0.10-9 
Tb-161 M 0.005  6.6.10-9 5.0.10-4 4.7.10-9 2.6.10-9 1.9.10-9 1.6.10-9 1.3.10-9 
dysprosium           
Dy-155 M 0.005  5.6.10-10 5.0.10-4 4.4.10-10 2.3.10-10 1.5.10-10 9.6.10-11 7.7.10-11 
Dy-157 M 0.005  2.4.10-10 5.0.10-4 1.9.10-10 9.9.10-11 6.2.10-11 3.8.10-11 3.0.10-11 
Dy-159 M 0.005  2.1.10-9 5.0.10-4 1.7.10-9 9.6.10-10 6.0.10-10 4.4.10-10 3.7.10-10 
Dy-165 M 0.005  5.2.10-10 5.0.10-4 3.4.10-10 1.6.10-10 1.1.10-10 7.2.10-11 6.0.10-11 
Dy-166 M 0.005  1.2.10-8 5.0.10-4 8.3.10-9 4.4.10-9 3.0.10-9 2.3.10-9 1.9.10-9 
holmium           
Ho-155 M 0.005  1.7.10-10 5.0.10-4 1.2.10-10 5.8.10-11 3.7.10-11 2.4.10-11 2.0.10-11 
Ho-157 M 0.005  3.4.10-11 5.0.10-4 2.5.10-11 1.3.10-11 8.0.10-12 5.1.10-12 4.2.10-12 
Ho-159 M 0.005  4.6.10-11 5.0.10-4 3.3.10-11 1.7.10-11 1.1.10-11 7.5.10-12 6.1.10-12 
Ho-161 M 0.005  5.7.10-11 5.0.10-4 4.0.10-11 2.0.10-11 1.2.10-11 7.5.10-12 6.0.10-12 
Ho-162 M 0.005  2.1.10-11 5.0.10-4 1.5.10-11 7.2.10-12 4.8.10-12 3.4.10-12 2.8.10-12 
Ho-162m  M 0.005  1.5.10-10 5.0.10-4 1.1.10-10 5.8.10-11 3.8.10-11 2.6.10-11 2.1.10-11 
Ho-164 M 0.005  6.8.10-11 5.0.10-4 4.5.10-11 2.1.10-11 1.4.10-11 9.9.10-12 8.4.10-12 
Ho-164m  M 0.005  9.1.10-11 5.0.10-4 5.9.10-11 3.0.10-11 2.0.10-11 1.3.10-11 1.2.10-11 
Ho-166 M 0.005  6.0.10-9 5.0.10-4 4.0.10-9 1.9.10-9 1.2.10-9 7.9.10-10 6.5.10-10 
Ho-166m  M 0.005  2.6.10-7 5.0.10-4 2.5.10-7 1.8.10-7 1.3.10-7 1.2.10-7 1.2.10-7 
Ho-167 M 0.005  5.2.10-10 5.0.10-4 3.6.10-10 1.8.10-10 1.2.10-10 8.7.10-11 7.1.10-11 - 193 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
erbium           
Er-161 M 0.005  3.8.10-10 5.0.10-4 2.9.10-10 1.5.10-10 9.5.10-11 6.0.10-11 4.8.10-11 
Er-165 M 0.005  7.2.10-11 5.0.10-4 5.3.10-11 2.6.10-11 1.6.10-11 9.6.10-12 7.9.10-12 
Er-169 M 0.005  4.7.10-9 5.0.10-4 3.5.10-9 2.0.10-9 1.5.10-9 1.3.10-9 1.0.10-9 
Er-171 M 0.005  1.8.10-9 5.0.10-4 1.2.10-9 5.9.10-10 3.9.10-10 2.7.10-10 2.2.10-10 
Er-172 M 0.005  6.6.10-9 5.0.10-4 4.7.10-9 2.5.10-9 1.7.10-9 1.4.10-9 1.1.10-9 
thulium           
Tm-162 M 0.005  1.3.10-10 5.0.10-4 9.6.10-11 4.7.10-11 3.0.10-11 1.9.10-11 1.6.10-11 
Tm-166 M 0.005  1.3.10-9 5.0.10-4 9.9.10-10 5.2.10-10 3.3.10-10 2.2.10-10 1.7.10-10 
Tm-167 M 0.005  5.6.10-9 5.0.10-4 4.1.10-9 2.3.10-9 1.7.10-9 1.4.10-9 1.1.10-9 
Tm-170 M 0.005  3.6.10-8 5.0.10-4 2.8.10-8 1.6.10-8 1.1.10-8 8.5.10-9 7.0.10-9 
Tm-171 M 0.005  6.8.10-9 5.0.10-4 5.7.10-9 3.4.10-9 2.0.10-9 1.6.10-9 1.4.10-9 
Tm-172 M 0.005  8.4.10-9 5.0.10-4 5.8.10-9 2.9.10-9 1.9.10-9 1.4.10-9 1.1.10-9 
Tm-173 M 0.005  1.5.10-9 5.0.10-4 1.0.10-9 5.0.10-10 3.3.10-10 2.2.10-10 1.8.10-10 
Tm-175 M 0.005  1.6.10-10 5.0.10-4 1.1.10-10 5.0.10-11 3.3.10-11 2.2.10-11 1.8.10-11 
ytterbium           
Yb-162 M 0.005  1.1.10-10 5.0.10-4 7.9.10-11 3.9.10-11 2.5.10-11 1.6.10-11 1.3.10-11 
 S 0.005  1.2.10-10 5.0.10-4 8.2.10-11 4.0.10-11 2.6.10-11 1.7.10-11 1.4.10-11 
Yb-166 M 0.005  4.7.10-9 5.0.10-4 3.5.10-9 1.9.10-9 1.3.10-9 9.0.10-10 7.2.10-10 
 S 0.005  4.9.10-9 5.0.10-4 3.7.10-9 2.0.10-9 1.3.10-9 9.6.10-10 7.7.10-10 
Yb-167 M 0.005  4.4.10-11 5.0.10-4 3.1.10-11 1.6.10-11 1.1.10-11 7.9.10-12 6.5.10-12 
 S 0.005  4.6.10-11 5.0.10-4 3.2.10-11 1.7.10-11 1.1.10-11 8.4.10-12 6.9.10-12 
Yb-169 M 0.005  1.2.10-8 5.0.10-4 8.7.10-9 5.1.10-9 3.7.10-9 3.2.10-9 2.5.10-9 
 S 0.005  1.3.10-8 5.0.10-4 9.8.10-9 5.9.10-9 4.2.10-9 3.7.10-9 3.0.10-9 
Yb-175 M 0.005  3.5.10-9 5.0.10-4 2.5.10-9 1.4.10-9 9.8.10-10 8.3.10-10 6.5.10-10 
 S 0.005  3.7.10-9 5.0.10-4 2.7.10-9 1.5.10-9 1.1.10-9 9.2.10-10 7.3.10-10 
Yb-177 M 0.005  5.0.10-10 5.0.10-4 3.3.10-10 1.6.10-10 1.1.10-10 7.8.10-11 6.4.10-11 
 S 0.005  5.3.10-10 5.0.10-4 3.5.10-10 1.7.10-10 1.2.10-10 8.4.10-11 6.9.10-11 
Yb-178 M 0.005  5.9.10-10 5.0.10-4 3.9.10-10 1.8.10-10 1.2.10-10 8.5.10-11 7.0.10-11 
 S 0.005  6.2.10-10 5.0.10-4 4.1.10-10 1.9.10-10 1.3.10-10 9.1.10-11 7.5.10-11 
lutetium           
Lu-169 M 0.005  2.3.10-9 5.0.10-4 1.8.10-9 9.5.10-10 6.3.10-10 4.4.10-10 3.5.10-10 
 S 0.005  2.4.10-9 5.0.10-4 1.9.10-9 1.0.10-9 6.7.10-10 4.8.10-10 3.8.10-10 
Lu-170 M 0.005  4.3.10-9 5.0.10-4 3.4.10-9 1.8.10-9 1.2.10-9 7.8.10-10 6.3.10-10 
 S 0.005  4.5.10-9 5.0.10-4 3.5.10-9 1.8.10-9 1.2.10-9 8.2.10-10 6.6.10-10 - 194 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Lu-171 M 0.005  5.0.10-9 5.0.10-4 3.7.10-9 2.1.10-9 1.2.10-9 9.8.10-10 8.0.10-10 
 S 0.005  4.7.10-9 5.0.10-4 3.9.10-9 2.0.10-9 1.4.10-9 1.1.10-9 8.8.10-10 
Lu-172 M 0.005  8.7.10-9 5.0.10-4 6.7.10-9 3.8.10-9 2.6.10-9 1.8.10-9 1.4.10-9 
 S 0.005  9.3.10-9 5.0.10-4 7.1.10-9 4.0.10-9 2.8.10-9 2.0.10-9 1.6.10-9 
Lu-173 M 0.005  1.0.10-8 5.0.10-4 8.5.10-9 5.1.10-9 3.2.10-9 2.5.10-9 2.2.10-9 
 S 0.005  1.0.10-8 5.0.10-4 8.7.10-9 5.4.10-9 3.6.10-9 2.9.10-9 2.4.10-9 
Lu-174 M 0.005  1.7.10-8 5.0.10-4 1.5.10-8 9.1.10-9 5.8.10-9 4.7.10-9 4.2.10-9 
 S 0.005  1.6.10-8 5.0.10-4 1.4.10-8 8.9.10-9 5.9.10-9 4.9.10-9 4.2.10-9 
Lu-174m  M 0.005  1.9.10-8 5.0.10-4 1.4.10-8 8.6.10-9 5.4.10-9 4.3.10-9 3.7.10-9 
 S 0.005  2.0.10-8 5.0.10-4 1.5.10-8 9.2.10-9 6.1.10-9 5.0.10-9 4.2.10-9 
Lu-176 M 0.005  1.8.10-7 5.0.10-4 1.7.10-7 1.1.10-7 7.8.10-8 7.1.10-8 7.0.10-8 
 S 0.005  1.5.10-7 5.0.10-4 1.4.10-7 9.4.10-8 6.5.10-8 5.9.10-8 5.6.10-8 
Lu-176m  M 0.005  8.9.10-10 5.0.10-4 5.9.10-10 2.8.10-10 1.9.10-10 1.2.10-10 1.1.10-10 
 S 0.005  9.3.10-10 5.0.10-4 6.2.10-10 3.0.10-10 2.0.10-10 1.2.10-10 1.2.10-10 
Lu-177 M 0.005  5.3.10-9 5.0.10-4 3.8.10-9 2.2.10-9 1.6.10-9 1.4.10-9 1.1.10-9 
 S 0.005  5.7.10-9 5.0.10-4 4.1.10-9 2.4.10-9 1.7.10-9 1.5.10-9 1.2.10-9 
Lu-177m  M 0.005  5.8.10-8 5.0.10-4 4.6.10-8 2.8.10-8 1.9.10-8 1.6.10-8 1.3.10-8 
 S 0.005  6.5.10-8 5.0.10-4 5.3.10-8 3.2.10-8 2.3.10-8 2.0.10-8 1.6.10-8 
Lu-178 M 0.005  2.3.10-10 5.0.10-4 1.5.10-10 6.6.10-11 4.3.10-11 2.9.10-11 2.4.10-11 
 S 0.005  2.4.10-10 5.0.10-4 1.5.10-10 6.9.10-11 4.5.10-11 3.0.10-11 2.6.10-11 
Lu-178m  M 0.005  2.6.10-10 5.0.10-4 1.8.10-10 8.3.10-11 5.6.10-11 3.8.10-11 3.2.10-11 
 S 0.005  2.7.10-10 5.0.10-4 1.9.10-10 8.7.10-11 5.8.10-11 4.0.10-11 3.3.10-11 
Lu-179 M 0.005  9.9.10-10 5.0.10-4 6.5.10-10 3.0.10-10 2.0.10-10 1.2.10-10 1.1.10-10 
 S 0.005  1.0.1 0-9 5.0.10-4 6.8.10-10 3.2.10-10 2.1.10-10 1.3.10-10 1.2.10-10 
hafnium           
Hf-170 F 0.02 1.4.10-9 0.002  1.1.10-9 5.4.10-10 3.4.10-10 2.0.10-10 1.6.10-10 
 M 0.02 2.2.10-9 0.002  1.7.10-9 8.7.10-10 5.8.10-10 3.9.10-10 3.2.10-10 
Hf-172 F 0.02 1.5.10-7 0.002  1.3.10-7 7.8.10-8 4.9.10-8 3.5.10-8 3.2.10-8 
 M 0.02 8.1.10-8 0.002  6.9.10-8 4.3.10-8 2.8.10-8 2.3.10-8 2.0.10-8 
Hf-173 F 0.02 6.6.10-10 0.002  5.0.10-10 2.5.10-10 1.5.10-10 8.9.10-11 7.4.10-11 
 M 0.02 1.1.10-9 0.002  8.2.10-10 4.3.10-10 2.9.10-10 2.0.10-10 1.6.10-10 
Hf-175 F 0.02 5.4.10-9 0.002  4.0.10-9 2.1.10-9 1.3.10-9 8.5.10-10 7.2.10-10 
 M 0.02 5.8.10-9 0.002  4.5.10-9 2.6.10-9 1.8.10-9 1.4.10-9 1.2.10-9 
Hf-177m  F 0.02 3.9.10-10 0.002  2.8.10-10 1.3.10-10 8.5.10-11 5.2.10-11 4.4.10-11 
 M 0.02 6.5.10-10 0.002  4.7.10-10 2.3.10-10 1.5.10-10 1.1.10-10 9.0.10-11 - 195 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Hf-178m  F 0.02 6.2.10-7 0.002  5.8.10-7 4.0.10-7 3.1.10-7 2.7.10-7 2.6.10-7 
 M 0.02 2.6.10-7 0.002  2.4.10-7 1.7.10-7 1.3.10-7 1.2.10-7 1.2.10-7 
Hf-179m  F 0.02 9.7.10-9 0.002  6.8.10-9 3.4.10-9 2.1.10-9 1.2.10-9 1.1.10-9 
 M 0.02 1.7.10-8 0.002  1.3.10-8 7.6.10-9 5.5.10-9 4.8.10-9 3.8.10-9 
Hf-180m  F 0.02 5.4.10-10 0.002  4.1.10-10 2.0.10-10 1.3.10-10 7.2.10-11 5.9.10-11 
 M 0.02 9.1.10-10 0.002  6.8.10-10 3.6.10-10 2.4.10-10 1.7.10-10 1.3.10-10 
Hf-181 F 0.02 1.3.10-8 0.002  9.6.10-9 4.8.10-9 2.8.10-9 1.7.10-9 1.4.10-9 
 M 0.02 2.2.10-8 0.002  1.7.10-8 9.9.10-9 7.1.10-9 6.3.10-9 5.0.10-9 
Hf-182 F 0.02 6.5.10-7 0.002  6.2.10-7 4.4.10-7 3.6.10-7 3.1.10-7 3.1.10-7 
 M 0.02 2.4.10-7 0.002  2.3.10-7 1.7.10-7 1.3.10-7 1.3.10-7 1.3.10-7 
Hf-182m  F 0.02 1.9.10-10 0.002  1.4.10-10 6.6.10-11 4.2.10-11 2.6.10-11 2.1.10-11 
 M 0.02 3.2.10-10 0.002  2.3.10-10 1.2.10-10 7.8.10-11 5.6.10-11 4.6.10-11 
Hf-183 F 0.02 2.5.10-10 0.002  1.7.10-10 7.9.10-11 4.9.10-11 2.8.10-11 2.4.10-11 
 M 0.02 4.4.10-10 0.002  3.0.10-10 1.5.10-10 9.8.10-11 7.0.10-11 5.7.10-11 
Hf-184 F 0.02 1.4.10-9 0.002  9.6.10-10 4.3.10-10 2.7.10-10 1.4.10-10 1.2.10-10 
 M 0.02 2.6.10-9 0.002  1.8.10-9 8.9.10-10 5.9.10-10 4.0.10-10 3.3.10-10 
tantalum           
Ta-172 M 0.01 2.8.10-10 0.001  1.9.10-10 9.3.10-11 6.0.10-11 4.0.10-11 3.3.10-11 
 S 0.01 2.9.10-10 0.001  2.0.10-10 9.8.10-11 6.3.10-11 4.2.10-11 3.5.10-11 
Ta-173 M 0.01 8.8.10-10 0.001  6.2.10-10 3.0.10-10 2.0.10-10 1.3.10-10 1.1.10-10 
 S 0.01 9.2.10-10 0.001  6.5.10-10 3.2.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
Ta-174 M 0.01 3.2.10-10 0.001  2.2.10-10 1.1.10-10 7.1.10-11 5.0.10-11 4.1.10-11 
 S 0.01 3.4.10-10 0.001  2.3.10-10 1.1.10-10 7.5.10-11 5.3.10-11 4.3.10-11 
Ta-175 M 0.01 9.1.10-10 0.001  7.0.10-10 3.7.10-10 2.4.10-10 1.5.10-10 1.2.10-10 
 S 0.01 9.5.10-10 0.001  7.3.10-10 3.8.10-10 2.5.10-10 1.6.10-10 1.3.10-10 
Ta-176 M 0.01 1.4.10-9 0.001  1.1.10-9 5.7.10-10 3.7.10-10 2.4.10-10 1.9.10-10 
 S 0.01 1.4.10-9 0.001  1.1.10-9 5.9.10-10 3.8.10-10 2.5.1 0-10 2.0.10-10 
Ta-177 M 0.01 6.5.10-10 0.001  4.7.10-10 2.5.10-10 1.5.10-10 1.2.10-10 9.6.10-11 
 S 0.01 6.9.10-10 0.001  5.0.10-10 2.7.10-10 1.7.10-10 1.3.10-10 1.1.10-10 
Ta-178m  M 0.01 4.4.10-10 0.001  3.3.10-10 1.7.10-10 1.1.10-10 8.0.10-11 6.5.10-11 
 S 0.01 4.6.10-10 0.001  3.4.10-10 1.8.10-10 1.2.10-10 8.5.10-11 6.8.10-11 
Ta-179 M 0.01 1.2.10-9 0.001  9.6.10-10 5.5.10-10 3.5.10-10 2.6.10-10 2.2.10-10 
 S 0.01 2.4.10-9 0.001  2.1.10-9 1.3.10-9 8.3.10-10 6.4.10-10 5.6.10-10 
Ta-180 M 0.01 3.1.10-10 0.001  2.2.10-10 1.1.10-10 7.4.10-11 4.8.10-11 4.4.10-11 
 S 0.01 3.3.10-10 0.001  2.3.10-10 1.2.10-10 7.9.10-11 5.2.10-11 4.2.10-11 - 196 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Ta-182 M 0.01 3.2.10-8 0.001  2.6.10-8 1.5.10-8 1.1.10-8 9.5.10-9 7.6.10-9 
 S 0.01 4.2.10-8 0.001  3.4.10-8 2.1.10-8 1.5.10-8 1.3.10-8 1.0.10-8 
Ta-182m  M 0.01 1.6.10-10 0.001  1.1.10-10 4.9.10-11 3.4.10-11 2.4.10-11 2.0.10-11 
 S 0.01 1.6.10-10 0.001  1.1.10-10 5.2.10-11 3.6.10-11 2.5.10-11 2.1.10-11 
Ta-183 M 0.01 1.0.10-8 0.001  7.4.10-9 4.1.10-9 2.9.10-9 2.4.10-9 1.9.10-9 
 S 0.01 1.1.10-8 0.001  8.0.10-9 4.5.10-9 3.2.10-9 2.7.10-9 2.1.10-9 
Ta-184 M 0.01 3.2.10-9 0.001  2.3.10-9 1.1.10-9 7.5.10-10 5.0.10-10 4.1.10-10 
 S 0.01 3.4.10-9 0.001  2.4.10-9 1.2.10-9 7.9.10-10 5.4.10-10 4.3.10-10 
Ta-185 M 0.01 3.8.10-10 0.001  2.5.10-10 1.2.10-10 7.7.10-11 5.4.10-11 4.5.10-11 
 S 0.01 4.0.10-10 0.001  2.6.10-10 1.2.10-10 8.2.10-11 5.7.10-11 4.8.10-11 
Ta-186 M 0.01 1.6.10-10 0.001  1.1.10-10 4.8.10-11 3.1.10-11 2.0.10-11 1.7.10-11 
 S 0.01 1.6.10-10 0.001  1.1.10-10 5.0.10-11 3.2.10-11 2.1.10-11 1.8.10-11 
wolfram           
W-176 F 0.6 3.3.10-10 0.3 2.7.10-10 1.4.10-10 8.6.10-11 5.0.10-11 4.1.10-11 
W-177 F 0.6 2.0.10-10 0.3 1.6.10-10 8.2.10-11 5.1.10-11 3.0.10-11 2.4.10-11 
W-178 F 0.6 7.2.10-10 0.3 5.4.10-10 2.5.10-10 1.6.10-10 8.7.10-11 7.2.10-11 
W-179 F 0.6 9.3.10-12 0.3 6.8.10-12 3.3.10-12 2.0.10-12 1.2.10-12 9.2.10-13 
W-181 F 0.6 2.5.10-10 0.3 1.9.10-10 9.2.10-11 5.7.10-11 3.2.10-11 2.7.10-11 
W-185 F 0.6 1.4.10-9 0.3 1.0.10-9 4.4.10-10 2.7.10-10 1.4.10-10 1.2.10-10 
W-187 F 0.6 2.0.10-9 0.3 1.5.10-9 7.0.10-10 4.3.10-10 2.3.10-10 1.9.10-10 
W-188 F 0.6 7.1.10-9 0.3 5.0.10-9 2.2.10-9 1.3.10-9 6.8.10-10 5.7.10-10 
rhenium           
Re-177 F 1.0 9.4.10-11 0.8 6.7.10-11 3.2.10-11 1.9.10-11 1.2.10-11 9.7.10-12 
 M 1.0 1.1.10-10 0.8 7.9.10-11 3.9.10-11 2.5.10-11 1.7.10-11 1.4.10-11 
Re-178 F 1.0 9.9.10-11 0.8 6.8.10-11 3.1.10-11 1.9.10-11 1.2.10-11 1.0.10-11 
 M 1.0 1.3.10-10 0.8 8.5.10-11 3.9.10-11 2.6.10-11 1.7.10-11 1.4.10-11 
Re-181 F 1.0 2.0.10-9 0.8 1.4.10-9 6.7.10-10 3.8.10-10 2.3.10-10 1.8.10-10 
 M 1.0 2.1.10-9 0.8 1.5.10-9 7.4.10-10 4.6.10-10 3.1.10-10 2.5.10-10 
Re-182 F 1.0 6.5.10-9 0.8 4.7.10-9 2.2.10-9 1.3.10-9 8.0.10-10 6.4.10-10 
 M 1.0 8.7.10-9 0.8 6.3.10-9 3.4.10-9 2.2.10-9 1.5.10-9 1.2.10-9 
Re-182m  F 1.0 1.3.10-9 0.8 1.0.10-9 4.9.10-10 2.8.10-10 1.7.10-10 1.4.10-10 
 M 1.0 1.4.10-9 0.8 1.1.10-9 5.7.10-10 3.6.10-10 2.5.10-10 2.0.10-10 
Re-184 F 1.0 4.1.10-9 0.8 2.9.10-9 1.4.10-9 8.6.10-10 5.4.10-10 4.4.10-10 
 M 1.0 9.1.10-9 0.8 6.8.10-9 4.0.10-9 2.8.10-9 2.4.10-9 1.9.10-9 
Re-184m  F 1.0 6.6.10-9 0.8 4.6.10-9 2.0.10-9 1.2.10-9 7.3.10-10 5.9.10-10 - 197 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 1.0 2.9.10-8 0.8 2.2.10-8 1.3.10-8 9.3.10-9 8.1.10-9 6.5.10-9 
Re-186 F 1.0 7.3.10-9 0.8 4.7.10-9 2.0.10-9 1.1.10-9 6.6.10-10 5.2.10-10 
 M 1.0 8.7.10-9 0.8 5.7.10-9 2.8.10-9 1.8.10-9 1.4.10-9 1.1.10-9 
Re-186m  F 1.0 1.2.10-8 0.8 7.0.10-9 2.9.10-9 1.7.10-9 1.0.10-9 8.3.10-10 
 M 1.0 5.9.10-8 0.8 4.6.10-8 2.7.10-8 1.8.10-8 1.4.10-8 1.2.10-8 
Re-187 F 1.0 2.6.10-11 0.8 1.6.10-11 6.8.10-12 3.8.10-12 2.3.10-12 1.8.10-12 
 M 1.0 5.7.10-11 0.8 4.1.10-11 2.0.10-11 1.2.10-11 7.5.10-12 6.3.10-12 
Re-188 F 1.0 6.5.10-9 0.8 4.4.10-9 1.9.10-9 1.0.10-9 6.1.10-10 4.6.10-10 
 M 1.0 6.0.10-9 0.8 4.0.10-9 1.8.10-9 1.0.10-9 6.8.10-10 5.4.10-10 
Re-188m  F 1.0 1.4.10-10 0.8 9.1.10-11 4.0.10-11 2.1.10-11 1.3.10-11 1.0.10-11 
 M 1.0 1.3.10-10 0.8 8.6.10-11 4.0.10-11 2.7.10-11 1.6.10-11 1.3.10-11 
Re-189 F 1.0 3.7.10-9 0.8 2.5.10-9 1.1.10-9 5.8.10-10 3.5.10-10 2.7.10-10 
 M 1.0 3.9.10-9 0.8 2.6.10-9 1.2.10-9 7.6.10-10 5.5.10-10 4.3.10-10 
osmium           
Os-180 F 0.02 7.1.10-11 0.01 5.3.10-11 2.6.10-11 1.6.10-11 1.0.10-11 8.2.10-12 
 M 0.02 1.1.10-10 0.01 7.9.10-11 3.9.10-11 2.5.10-11 1.7.10-11 1.4.10-11 
 S 0.02 1.1.10-10 0.01 8.2.10-11 4.1.10-11 2.6.10-11 1.8.10-11 1.5.10-11 
Os-181 F 0.02 3.0.10-10 0.01 2.3.10-10 1.1.10-10 7.0.10-11 4.1.10-11 3.3.10-11 
 M 0.02 4.5.10-10 0.01 3.4.10-10 1.8.10-10 1.1.10-10 7.6.10-11 6.2.10-11 
 S 0.02 4.7.10-10 0.01 3.6.10-10 1.8.10-10 1.2.10-10 8.1.10-11 6.5.10-11 
Os-182 F 0.02 1.6.10-9 0.01 1.2.10-9 6.0.10-10 3.7.10-10 2.1.10-10 1.7.10-10 
 M 0.02 2.5.10-9 0.01 1.9.10-9 1.0.10-9 6.6.10-10 4.5.10-10 3.6.10-10 
 S 0.02 2.6.10-9 0.01 2.0.10-9 1.0.10-9 6.9.10-10 4.8.10-10 3.8.10-10 
Os-185 F 0.02 7.2.10-9 0.01 5.8.10-9 3.1.10-9 1.9.10-9 1.2.10-9 1.1.10-9 
 M 0.02 6.6.10-9 0.01 5.4.1 0-9 2.9.10-9 2.0.10-9 1.5.10-9 1.3.10-9 
 S 0.02 7.0.10-9 0.01 5.8.10-9 3.6.10-9 2.4.10-9 1.9.10-9 1.6.10-9 
Os-189m  F 0.02 3.8.10-11 0.01 2.8.10-11 1.2.10-11 7.0.10-12 3.5.10-12 2.5.10-12 
 M 0.02 6.5.10-11 0.01 4.1.10-11 1.8.10-11 1.1.10-11 6.0.10-12 5.0.10-12 
 S 0.02 6.8.10-11 0.01 4.3.10-11 1.9.10-11 1.2.10-11 6.3.10-12 5.3.10-12 
Os-191 F 0.02 2.8.10-9 0.01 1.9.10-9 8.5.10-10 5.3.10-10 3.0.10-10 2.5.10-10 
 M 0.02 8.0.10-9 0.01 5.8.10-9 3.4.10-9 2.4.10-9 2.0.10-9 1.7.10-9 
 S 0.02 9.0.10-9 0.01 6.5.10-9 3.9.10-9 2.7.10-9 2.3.10-9 1.9.10-9 
Os-191m  F 0.02 3.0.10-10 0.01 2.0.10-10 8.8.10-11 5.4.10-11 2.9.10-11 2.4.10-11 
 M 0.02 7.8.10-10 0.01 5.4.10-10 3.1.10-10 2.1.10-10 1.7.10-10 1.4.10-10 
 S 0.02 8.5.10-10 0.01 6.0.10-10 3.4.10-10 2.4.10-10 2.0.10-10 1.6.10-10 - 198 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Os-193 F 0.02 1.9.10-9 0.01 1.2.10-9 5.2.10-10 3.2.10-10 1.8.10-10 1.6.10-10 
 M 0.02 3.8.10-9 0.01 2.6.10-9 1.3.10-9 8.4.10-10 5.9.10-10 4.8.10-10 
 S 0.02 4.0.10-9 0.01 2.7.10-9 1.3.10-9 9.0.10-10 6.4.10-10 5.2.10-10 
Os-194 F 0.02 8.7.10-8 0.01 6.8.10-8 3.4.10-8 2.1.10-8 1.3.10-8 1.1.10-8 
 M 0.02 9.9.10-8 0.01 8.3.10-8 4.8.10-8 3.1.10-8 2.4.10-8 2.1.10-8 
 S 0.02 2.6.10-7 0.01 2.4.10-7 1.6.10-7 1.1.10-7 8.8.10-8 8.5.10-8 
iridium           
Ir-182 F 0.02 1.4.10-10 0.01 9.8.10-11 4.5.10-11 2.8.10-11 1.7.10-11 1.4.10-11 
 M 0.02 2.1.10-10 0.01 1.4.10-10 6.7.10-11 4.3.10-11 2.8.10-11 2.3.10-11 
 S 0.02 2.2.10-10 0.01 1.5.10-10 6.9.10-11 4.4.10-11 2.9.10-11 2.4.10-11 
Ir-184 F 0.02 5.7.10-10 0.01 4.4.10-10 2.1.10-10 1.3.10-10 7.6.10-11 6.2.10-11 
 M 0.02 8.6.10-10 0.01 6.4.10-10 3.2.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
 S 0.02 8.9.10-10 0.01 6.6.10-10 3.4.10-10 2.2.10-10 1.4.10-10 1.2.10-10 
Ir-185 F 0.02 8.0.10-10 0.01 6.1.10-10 2.9.10-10 1.8.10-10 1.0.10-10 8.2.10-11 
 M 0.02 1.3.10-9 0.01 9.7.1 0-10 4.9.10-10 3.2.10-10 2.2.10-10 1.8.10-10 
 S 0.02 1.4.10-9 0.01 1.0.10-9 5.2.10-10 3.4.10-10 2.3.10-10 1.9.10-10 
Ir-186 F 0.02 1.5.10-9 0.01 1.2.10-9 5.9.10-10 3.6.10-10 2.1.10-10 1.7.10-10 
 M 0.02 2.2.10-9 0.01 1.7.10-9 8.8.10-10 5.8.10-10 3.8.10-10 3.1.10-10 
 S 0.02 2.3.10-9 0.01 1.8.10-9 9.2.10-10 6.0.10-10 4.0.10-10 3.2.10-10 
Ir-186m  F 0.02 2.1.10-10 0.01 1.6.10-10 7.7.10-11 4.8.10-11 2.8.10-11 2.3.10-11 
 M 0.02 3.3.10-10 0.01 2.4.10-10 1.2.10-10 7.7.10-11 5.1.10-11 4.2.10-11 
 S 0.02 3.4.10-10 0.01 2.5.10-10 1.2.10-10 8.1.10-11 5.4.10-11 4.4.10-11 
Ir-187 F 0.02 3.6.10-10 0.01 2.8.10-10 1.4.10-10 8.2.10-11 4.6.10-11 3.7.10-11 
 M 0.02 5.8.10-10 0.01 4.3.10-10 2.2.10-10 1.4.10-10 9.2.10-11 7.4.10-11 
 S 0.02 6.0.10-10 0.01 4.5.10-10 2.3.10-10 1.5.10-10 9.7.10-11 7.9.10-11 
Ir-188 F 0.02 2.0.10-9 0.01 1.6.10-9 8.0.10-10 5.0.10-10 2.9.10-10 2.4.10-10 
 M 0.02 2.7.10-9 0.01 2.1.10-9 1.1.10-9 7.5.10-10 5.0.10-10 4.0.10-10 
 S 0.02 2.8.10-9 0.01 2.2.10-9 1.2.10-9 7.8.10-10 5.2.10-10 4.2.10-10 
Ir-189 F 0.02 1.2.10-9 0.01 8.2.10-10 3.8.10-10 2.4.10-10 1.3.10-10 1.1.10-10 
 M 0.02 2.7.10-9 0.01 1.9.10-9 1.1.10-9 7.7.10-10 6.4.10-10 5.2.10-10 
 S 0.02 3.0.10-9 0.01 2.2.10-9 1.3.10-9 8.7.10-10 7.3.10-10 6.0.10-10 
Ir-190 F 0.02 6.2.10-9 0.01 4.7.10-9 2.4.1 0-9 1.5.10-9 9.1.10-10 7.7.10-10 
 M 0.02 1.1.10-8 0.01 8.6.10-9 4.4.10-9 3.1.10-9 2.7.10-9 2.1.10-9 
 S 0.02 1.1.10-8 0.01 9.4.10-9 4.8.10-9 3.5.10-9 3.0.10-9 2.4.10-9 
Ir-190m’  F 0.02 4.2.10-10 0.01 3.4.10-10 1.7.10-10 1.0.10-10 6.0.10-11 4.9.10-11 - 199 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.02 6.0.10-10 0.01 4.7.10-10 2.4.10-10 1.5.10-10 9.9.10-11 7.9.10-11 
 S 0.02 6.2.10-10 0.01 4.8.10-10 2.5.10-10 1.6.10-10 1.0.10-10 8.3.10-11 
Ir-190m  F 0.02 3.2.10-11 0.01 2.4.10-11 1.2.10-11 7.2.10-12 4.3.10-12 3.6.10-12 
 M 0.02 5.7.10-11 0.01 4.2.10-11 2.0.10-11 1.4.10-11 1.2.10-11 9.3.10-12 
 S 0.02 5.5.10-11 0.01 4.5.10-11 2.2.10-11 1.6.10-11 1.3.10-11 1.0.10-11 
Ir-192 F 0.02 1.5.10-8 0.01 1.1.10-8 5.7.10-9 3.3.10-9 2.1.10-9 1.8.10-9 
 M 0.02 2.3.10-8 0.01 1.8.10-8 1.1.10-8 7.6.10-9 6.4.10-9 5.2.10-9 
 S 0.02 2.8.10-8 0.01 2.2.10-8 1.3.10-8 9.5.10-9 8.1.10-9 6.6.10-9 
Ir-192m  F 0.02 2.7.10-8 0.01 2.3.10-8 1.4.10-8 8.2.10-9 5.4.10-9 4.8.10-9 
 M 0.02 2.3.10-8 0.01 2.1.10-8 1.3.10-8 8.4.10-9 6.6.10-9 5.8.10-9 
 S 0.02 9.2.10-8 0.01 9.1.10-8 6.5.10-8 4.5.10-8 4.0.10-8 3.9.10-8 
Ir-193m  F 0.02 1.2.10-9 0.01 8.4.10-10 3.7.10-10 2.2.10-10 1.2.10-10 1.0.10-10 
 M 0.02 4.8.10-9 0.01 3.5.10-9 2.1.10-9 1.5.10-9 1.4.10-9 1.1.10-9 
 S 0.02 5.4.10-9 0.01 4.0.10-9 2.4.10-9 1.8.10-9 1.6.10-9 1.3.10-9 
Ir-194 F 0.02 2.9.10-9 0.01 1.9.10-9 8.1.10-10 4.9.10-10 2.5.10-10 2.1.10-10 
 M 0.02 5.3.10-9 0.01 3.5.10-9 1.6.10-9 1.0.10-9 6.3.10-10 5.2.10-10 
 S 0.02 5.5.10-9 0.01 3.7.10-9 1.7.10-9 1.1.10-9 6.7.10-10 5.6.10-10 
Ir-194m  F 0.02 3.4.10-8 0.01 2.7.10-8 1.4.10-8 9.5.1 0-9 6.2.10-9 5.4.10-9 
 M 0.02 3.9.10-8 0.01 3.2.10-8 1.9.10-8 1.3.10-8 1.1.10-8 9.0.10-9 
 S 0.02 5.0.10-8 0.01 4.2.10-8 2.6.10-8 1.8.10-8 1.5.10-8 1.3.10-8 
Ir-195 F 0.02 2.9.10-10 0.01 1.9.10-10 8.1.10-11 5.1.10-11 2.9.10-11 2.4.10-11 
 M 0.02 5.4.10-10 0.01 3.6.10-10 1.7.10-10 1.1.10-10 8.1.10-11 6.7.10-11 
 S 0.02 5.7.10-10 0.01 3.8.10-10 1.8.10-10 1.2.10-10 8.7.10-11 7.1.10-11 
Ir-195m  F 0.02 6.9.10-10 0.01 4.8.10-10 2.1.10-10 1.3.10-10 7.2.10-11 6.0.10-11 
 M 0.02 1.2.10-9 0.01 8.6.10-10 4.2.10-10 2.7.10-10 1.9.10-10 1.6.10-10 
 S 0.02 1.3.10-9 0.01 9.0.10-10 4.4.10-10 2.9.10-10 2.0.10-10 1.7.10-10 
platinum           
Pt-186 F 0.02 3.0.10-10 0.01 2.4.10-10 1.2.10-10 7.2.10-11 4.1.10-11 3.3.10-11 
Pt-188 F 0.02 3.6.10-9 0.01 2.7.10-9 1.3.10-9 8.4.10-10 5.0.10-10 4.2.10-10 
Pt-189 F 0.02 3.8.10-10 0.01 2.9.10-10 1.4.10-10 8.4.10-11 4.7.10-11 3.8.10-11 
Pt-191 F 0.02 1.1.10-9 0.01 7.9.10-10 3.7.10-10 2.3.10-10 1.3.10-10 1.1.10-10 
Pt-193 F 0.02 2.2.10-10 0.01 1.6.10-10 7.2.10-11 4.3.10-11 2.5.10-11 2.1.10-11 
Pt-193m  F 0.02 1.6.10-9 0.01 1.0.10-9 4.5.10-10 2.7.10-10 1.4.10-10 1.2.10-10 
Pt-195m  F 0.02 2.2.10-9 0.01 1.5.10-9 6.4.10-10 3.9.10-10 2.1.10-10 1.8.10-10 
Pt-197 F 0.02 1.1.10-9 0.01 7.3.10-10 3.1.10-10 1.9.10-10 1.0.10-10 8.5.10-11 - 200 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Pt-197m  F 0.02 2.8.10-10 0.01 1.8.10-10 7.9.10-11 4.9.10-11 2.8.10-11 2.4.10-11 
Pt-199 F 0.02 1.3.10-10 0.01 8.3.10-11 3.6.10-11 2.3.10-11 1.4.10-11 1.2.10-11 
Pt-200 F 0.02 2.6.10-9 0.01 1.7.10-9 7.2.10-10 5.1.10-10 2.6.10-10 2.2.10-10 
gold          
Au-193 F 0.2 3.7.10-10 0.1 2.8.10-10 1.3.10-10 7.9.10-11 4.3.10-11 3.6.10-11 
 M 0.2 7.5.10-10 0.1 5.6.10-10 2.8.10-10 1.9.10-10 1.4.10-10 1.1.10-10 
 S 0.2 7.9.10-10 0.1 5.9.10-10 3.0.10-10 2.0.10-10 1.5.10-10 1.2.10-10 
Au-194 F 0.2 1.2.10-9 0.1 9.6.10-10 4.9.10-10 3.0.10-10 1.8.10-10 1.4.10-10 
 M 0.2 1.7.10-9 0.1 1.4.10-9 7.1.10-10 4.6.10-10 2.9.10-10 2.3.10-10 
 S 0.2 1.7.10-9 0.1 1.4.10-9 7.3.10-10 4.7.10-10 3.0.10-10 2.4.10-10 
Au-195 F 0.2 7.2.10-10 0.1 5.3.10-10 2.5.10-10 1.5.10-10 8.1.10-11 6.6.10-11 
 M 0.2 5.2.10-9 0.1 4.1.10-9 2.4.10-9 1.6.10-9 1.4.10-9 1.1.10-9 
 S 0.2 8.1.10-9 0.1 6.6.10-9 3.9.10-9 2.6.10-9 2.1.10-9 1.7.10-9 
Au-198 F 0.2 2.4.10-9 0.1 1.7.10-9 7.6.10-10 4.7.10-10 2.5.10-10 2.1.10-10 
 M 0.2 5.0.10-9 0.1 4.1.10-9 1.9.10-9 1.3.10-9 9.7.10-10 7.8.10-10 
 S 0.2 5.4.10-9 0.1 4.4.10-9 2.0.10-9 1.4.10-9 1.1.10-9 8.6.10-10 
Au-198m  F 0.2 3.3.10-9 0.1 2.4.10-9 1.1.10-9 6.9.10-10 3.7.10-10 3.2.10-10 
 M 0.2 8.7.10-9 0.1 6.5.10-9 3.6.10-9 2.6.10-9 2.2.10-9 1.8.10-9 
 S 0.2 9.5.10-9 0.1 7.1.10-9 4.0.10-9 2.9.10-9 2.5.10-9 2.0.10-9 
Au-199 F 0.2 1.1.10-9 0.1 7.9.10-10 3.5.10-10 2.2.10-10 1.1.10-10 9.8.10-11 
 M 0.2 3.4.10-9 0.1 2.5.10-9 1.4.10-9 1.0.10-9 9.0.10-10 7.1.10-10 
 S 0.2 3.8.10-9 0.1 2.8.10-9 1.6.10-9 1.2.10-9 1.0.10-9 7.9.10-10 
Au-200 F 0.2 1.9.10-10 0.1 1.2.10-10 5.2.10-11 3.2.10-11 1.9.10-11 1.6.10-11 
 M 0.2 3.2.10-10 0.1 2.1.10-10 9.3.10-11 6.0.10-11 4.0.10-11 3.3.10-11 
 S 0.2 3.4.10-10 0.1 2.1.10-10 9.8.10-11 6.3.10-11 4.2.10-11 3.5.10-11 
Au-200m  F 0.2 2.7.10-9 0.1 2.1.10-9 1.0.10-9 6.4.1 0-10 3.6.10-10 2.9.10-10 
 M 0.2 4.8.10-9 0.1 3.7.10-9 1.9.10-9 1.2.10-9 8.4.10-10 6.8.10-10 
 S 0.2 5.1.10-9 0.1 3.9.10-9 2.0.10-9 1.3.10-9 8.9.10-10 7.2.10-10 
Au-201 F 0.2 9.0.10-11 0.1 5.7.10-11 2.5.10-11 1.6.10-11 1.0.10-11 8.7.10-12 
 M 0.2 1.5.10-10 0.1 9.6.10-11 4.3.10-11 2.9.10-11 2.0.10-11 1.7.10-11 
 S 0.2 1.5.10-10 0.1 1.0.10-10 4.5.10-11 3.0.10-11 2.1.10-11 1.7.10-11 
mercury           
Hg-193 org.  F 0.8 2.2.10-10 0.4 1.8.10-10 8.2.10-11 5.0.10-11 2.9.10-11 2.4.10-11 
Hg-193 anorg.  F 0.04 2.7.10-10 0.02 2.0.10-10 8.9.10-11 5.5.10-11 3.1.10-11 2.6.10-11 
 M 0.04 5.3.10-10 0.02 3.8.10-10 1.9.10-10 1.3.10-10 9.2.10-11 7.5.10-11 - 201 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Hg-193m org.  F 0.8 8.4.10-10 0.4 7.6.10-10 3.7.10-10 2.2.10-10 1.3.10-10 1.0.10-10 
Hg-193m anorg.  F 0.04 1.1.10-9 0.02 8.5.10-10 4.1.10-10 2.5.10-10 1.4.10-10 1.1.10-10 
 M 0.04 1.9.10-9 0.02 1.4.10-9 7.2.10-10 4.7.10-10 3.2.10-10 2.6.10-10 
Hg-194 org.  F 0.8 4.9.10-8 0.4 3.7.10-8 2.4.10-8 1.9.10-8 1.5.10-8 1.4.10-8 
Hg-194 anorg.  F 0.04 3.2.10-8 0.02 2.9.10-8 2.0.10-8 1.6.1 0-8 1.4.10-8 1.3.10-8 
 M 0.04 2.1.10-8 0.02 1.9.10-8 1.3.10-8 1.0.10-8 8.9.10-9 8.3.10-9 
Hg-195 org.  F 0.8 2.0.10-10 0.4 1.8.10-10 8.5.10-11 5.1.10-11 2.8.10-11 2.3.10-11 
Hg-195 anorg.  F 0.04 2.7.10-10 0.02 2.0.10-10 9.5.10-11 5.7.10-11 3.1.10-11 2.5.10-11 
 M 0.04 5.3.10-10 0.02 3.9.10-10 2.0.10-10 1.3.10-10 9.0.10-11 7.3.10-11 
Hg-195m org.  F 0.8 1.1.10-9 0.4 9.7.10-10 4.4.10-10 2.7.10-10 1.4.10-10 1.2.10-10 
Hg-195m anorg.  F 0.04 1.6.10-9 0.02 1.1.10-9 5.1.10-10 3.1.10-10 1.7.10-10 1.4.10-10 
 M 0.04 3.7.10-9 0.02 2.6.10-9 1.4.10-9 8.5.10-10 6.7.10-10 5.3.10-10 
Hg-197 org.  F 0.8 4.7.10-10 0.4 4.0.10-10 1.8.10-10 1.1.10-10 5.8.10-11 4.7.10-11 
Hg-197 anorg.  F 0.04 6.8.10-10 0.02 4.7.10-10 2.1.10-10 1.3.10-10 6.8.10-11 5.6.10-11 
 M 0.04 1.7.10-9 0.02 1.2.10-9 6.6.10-10 4.6.10-10 3.8.10-10 3.0.10-10 
Hg-197m org.  F 0.8 9.3.10-10 0.4 7.8.10-10 3.4.10-10 2.1.10-10 1.1.10-10 9.6.10-11 
Hg-197m anorg.  F 0.04 1.4.10-9 0.02 9.3.10-10 4.0.10-10 2.5.10-10 1.3.10-10 1.1.10-10 
 M 0.04 3.5.10-9 0.02 2.5.10-9 1.1.1 0-9 8.2.10-10 6.7.10-10 5.3.10-10 
Hg-199m org.  F 0.8 1.4.10-10 0.4 9.6.10-11 4.2.10-11 2.7.10-11 1.7.10-11 1.5.10-11 
Hg-199m anorg.  F 0.04 1.4.10-10 0.02 9.6.10-11 4.2.10-11 2.7.10-11 1.7.10-11 1.5.10-11 
 M 0.04 2.5.10-10 0.02 1.7.10-10 7.9.10-11 5.4.10-11 3.8.10-11 3.2.10-11 
Hg-203 org.  F 0.8 5.7.10-9 0.4 3.7.10-9 1.7.10-9 1.1.10-9 6.6.10-10 5.6.10-10 
Hg-203 anorg.  F 0.04 4.2.10-9 0.02 2.9.10-9 1.4.10-9 9.0.10-10 5.5.10-10 4.6.10-10 
 M 0.04 1.0.10-8 0.02 7.9.10-9 4.7.10-9 3.4.10-9 3.0.10-9 2.4.10-9 
thallium           
Tl-194 F 1.0 3.6.10-11 1.0 3.0.10-11 1.5.10-11 9.2.10-12 5.5.10-12 4.4.10-12 
Tl-194m  F 1.0 1.7.10-10 1.0 1.2.10-10 6.1.10-11 3.8.10-11 2.3.10-11 1.9.10-11 
Tl-195 F 1.0 1.3.10-10 1.0 1.0.10-10 5.3.10-11 3.2.10-11 1.9.10-11 1.5.10-11 
Tl-197 F 1.0 1.3.10-10 1.0 9.7.10-11 4.7.10-11 2.9.10-11 1.7.10-11 1.4.10-11 
Tl-198 F 1.0 4.7.10-10 1.0 4.0.10-10 2.1.10-10 1.3.10-10 7.5.10-11 6.0.10-11 
Tl-198m  F 1.0 3.2.10-10 1.0 2.5.10-10 1.2.10-10 7.5.10-11 4.5.10-11 3.7.10-11 
Tl-199 F 1.0 1.7.10-10 1.0 1.3.10-10 6.4.10-11 3.9.10-11 2.3.10-11 1.9.10-11 
Tl-200 F 1.0 1.0.10-9 1.0 8.7.10-10 4.6.10-10 2.8.10-10 1.6.10-10 1.3.10-10 
Tl-201 F 1.0 4.5.10-10 1.0 3.3.10-10 1.5.10-10 9.4.10-11 5.4.10-11 4.4.10-11 
Tl-202 F 1.0 1.5.10-9 1.0 1.2.10-9 5.9.10-10 3.8.10-10 2.3.10-10 1.9.10-10 - 202 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Tl-204 F 1.0 5.0.10-9 1.0 3.3.10-9 1.5.10-9 8.8.10-10 4.7.10-10 3.9.10-10 
lead          
Pb-195m  F 0.6 1.3.10-10 0.4**  1.0.10-10 4.9.10-11 3.1.10-11 1.9.10-11 1.6.10-11 
 M 0.2 2.0.10-10 0.1 1.5.10-10 7.1.10-11 4.6.10-11 3.1.10-11 2.5.10-11 
 S 0.02 2.1.10-10 0.01 1.5.10-10 7.4.10-11 4.8.10-11 3.2.10-11 2.7.10-11 
Pb-198 F 0.6 3.4.10-10 0.4**  2.9.10-10 1.5.10-10 8.9.10-11 5.2.10-11 4.3.10-11 
 M 0.2 5.0.10-10 0.1 4.0.10-10 2.1.10-10 1.3.10-10 8.3.10-11 6.6.10-11 
 S 0.02 5.4.1 0-10 0.01 4.2.10-10 2.2.10-10 1.4.10-10 8.7.10-11 7.0.10-11 
Pb-199 F 0.6 1.9.10-10 0.4**  1.6.10-10 8.2.10-11 4.9.10-11 2.9.10-11 2.3.10-11 
 M 0.2 2.8.10-10 0.1 2.2.10-10 1.1.10-10 7.1.10-11 4.5.10-11 3.6.10-11 
 S 0.02 2.9.10-10 0.01 2.3.10-10 1.2.10-10 7.4.10-11 4.7.10-11 3.7.10-11 
Pb-200 F 0.6 1.1.10-9 0.4**  9.3.10-10 4.6.10-10 2.8.10-10 1.6.10-10 1.4.10-10 
 M 0.2 2.2.10-9 0.1 1.7.10-9 8.6.10-10 5.7.10-10 4.1.10-10 3.3.10-10 
 S 0.02 2.4.10-9 0.01 1.8.10-9 9.2.10-10 6.2.10-10 4.4.10-10 3.5.10-10 
Pb-201 F 0.6 4.8.10-10 0.4**  4.1.10-10 2.0.10-10 1.2.10-10 7.1.10-11 6.0.10-11 
 M 0.2 8.0.10-10 0.1 6.4.10-10 3.3.10-10 2.1.10-10 1.4.10-10 1.1.10-10 
 S 0.02 8.8.10-10 0.01 6.7.10-10 3.5.10-10 2.2.10-10 1.5.10-10 1.2.10-10 
Pb-202 F 0.6 1.9.10-8 0.4**  1.3.10-8 8.9.10-9 1.3.10-8 1.8.10-8 1.1.10-8 
 M 0.2 1.2.10-8 0.1 8.9.10-9 6.2.10-9 6.7.10-9 8.7.10-9 6.3.10-9 
 S 0.02 2.8.10-8 0.01 2.8.10-8 2.0.10-8 1.4.10-8 1.3.10-8 1.2.10-8 
Pb-202m  F 0.6 4.7.10-10 0.4**  4.0.10-10 2.1.10-10 1.3.10-10 7.5.10-11 6.2.10-11 
 M 0.2 6.9.10-10 0.1 5.6.10-10 2.9.10-10 1.9.10-10 1.2.10-10 9.5.10-11 
 S 0.02 7.3.10-10 0.01 5.8.10-10 3.0.10-10 1.9.10-10 1.3.10-10 1.0.10-10 
Pb-203 F 0.6 7.2.10-10 0.4**  5.8.10-10 2.8.10-10 1.7.10-10 9.9.10-11 8.5.10-11 
 M 0.2 1.3.10-9 0.1 1.0.10-9 5.4.10-10 3.6.10-10 2.5.10-10 2.0.10-10 
 S 0.02 1.5.10-9 0.01 1.1.10-9 5.8.10-10 3.8.10-10 2.8.10-10 2.2.10-10 
Pb-205 F 0.6 1.1.10-9 0.4**  6.9.10-10 4.0.10-10 4.1.10-10 4.3.10-10 3.3.10-10 
 M 0.2 1.1.10-9 0.1 7.7.10-10 4.3.10-10 3.2.10-10 2.9.10-10 2.5.10-10 
 S 0.02 2.9.10-9 0.01 2.7.10-9 1.7.10-9 1.1.10-9 9.2.10-10 8.5.10-10 
Pb-209 F 0.6 1.8.10-10 0.4**  1.2.10-10 5.3.10-11 3.4.10-11 1.9.10-11 1.7.10-11 
 M 0.2 4.0.10-10 0.1 2.7.10-10 1.3.10-10 9.2.10-11 6.9.10-11 5.6.10-11 
 S 0.02 4.4.10-10 0.01 2.9.10-10 1.4.10-10 9.9.10-11 7.5.10-11 6.1.10-11 
Pb-210 F 0.6 4.7.10-6 0.4**  2.9.10-6 1.5.10-6 1.4.10-6 1.3.10-6 9.0.10-7 
 M 0.2 5.0.10-6 0.1 3.7.10-6 2.2.10-6 1.5.10-6 1.3.10-6 1.1.10-6 
 S 0.02 1.8.10-5 0.01 1.8.10-5 1.1.10-5 7.2.10-6 5.9.10-6 5.6.10-6 - 203 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Pb-211 F 0.6 2.5.10-8 0.4**  1.7.10-8 8.7.10-9 6.1.10-9 4.6.10-9 3.9.10-9 
 M 0.2 6.2.10-8 0.1 4.5.10-8 2.5.10-8 1.9.10-8 1.4.10-8 1.1.10-8 
 S 0.02 6.6.10-8 0.01 4.8.10-8 2.7.10-8 2.0.10-8 1.5.10-8 1.2.10-8 
Pb-212 F 0.6 1.9.10-7 0.4**  1.2.10-7 5.4.10-8 3.5.1 0-8 2.0.10-8 1.8.10-8 
 M 0.2 6.2.10-7 0.1 4.6.10-7 3.0.10-7 2.2.10-7 2.2.10-7 1.7.10-7 
 S 0.02 6.7.10-7 0.01 5.0.10-7 3.3.10-7 2.5.10-7 2.4.10-7 1.9.10-7 
Pb-214 F 0.6 2.2.10-8 0.4**  1.5.10-8 6.9.10-9 4.8.10-9 3.3.10-9 2.8.10-9 
 M 0.2 6.4.10-8 0.1 4.6.1 0-8 2.6.10-8 1.9.10-8 1.4.10-8 1.4.10-8 
 S 0.02 6.9.10-8 0.01 5.0.10-8 2.8.10-8 2.1.10-8 1.5.10-8 1.5.10-8 
bismuth           
Bi-200 F 0.1 1.9.10-10 0.05 1.5.10-10 7.4.10-11 4.5.10-11 2.7.10-11 2.2.10-11 
 M 0.1 2.5.10-10 0.05 1.9.10-10 9.9.10-11 6.3.10-11 4.1.10-11 3.3.10-11 
Bi-201 F 0.1 4.0.10-10 0.05 3.1.10-10 1.5.10-10 9.3.10-11 5.4.10-11 4.4.10-11 
 M 0.1 5.5.10-10 0.05 4.1.10-10 2.0.10-10 1.3.10-10 8.3.10-11 6.6.10-11 
Bi-202 F 0.1 3.4.10-10 0.05 2.8.10-10 1.5.10-10 9.0.10-11 5.3.10-11 4.3.10-11 
 M 0.1 4.2.10-10 0.05 3.4.10-10 1.8.10-10 1.1.10-10 6.9.10-11 5.5.10-11 
Bi-203 F 0.1 1.5.10-9 0.05 1.2.10-9 6.4.10-10 4.0.10-10 2.3.10-10 1.9.10-10 
 M 0.1 2.0.10-9 0.05 1.6.10-9 8.2.10-10 5.3.10-10 3.3.10-10 2.6.10-10 
Bi-205 F 0.1 3.0.10-9 0.05 2.4.10-9 1.3.10-9 8.0.10-10 4.7.10-10 3.8.10-10 
 M 0.1 5.5.10-9 0.05 4.4.10-9 2.5.10-9 1.6.10-9 1.2.10-9 9.3.10-10 
Bi-206 F 0.1 6.1.10-9 0.05 4.8.10-9 2.5.10-9 1.6.10-9 9.1.10-10 7.4.10-10 
 M 0.1 1.0.10-8 0.05 8.0.10-9 4.4.10-9 2.9.10-9 2.1.10-9 1.7.10-9 
Bi-207 F 0.1 4.3.10-9 0.05 3.3.10-9 1.7.10-9 1.0.10-9 6.0.10-10 4.9.10-10 
 M 0.1 2.3.10-8 0.05 2.0.10-8 1.2.10-8 8.2.10-9 6.5.10-9 5.6.10-9 
Bi-210 F 0.1 1.1.10-8 0.05 6.9.10-9 3.2.10-9 2.1.10-9 1.3.10-9 1.1.10-9 
 M 0.1 3.9.10-7 0.05 3.0.10-7 1.9.10-7 1.3.10-7 1.1.10-7 9.3.10-8 
Bi-210m  F 0.1 4.1.10-7 0.05 2.6.10-7 1.3.10-7 8.3.10-8 5.6.10-8 4.6.10-8 
 M 0.1 1.5.10-5 0.05 1.1.10-5 7.0.10-6 4.8.10-6 4.1.10-6 3.4.10-6 
Bi-212 F 0.1 6.5.10-8 0.05 4.5.10-8 2.1.10-8 1.5.10-8 1.0.10-8 9.1.10-9 
 M 0.1 1.6.10-7 0.05 1.1.10-7 6.0.10-8 4.4.10-8 3.8.10-8 3.1.10-8 
Bi-213 F 0.1 7.7.10-8 0.05 5.3.10-8 2.5.10-8 1.7.10-8 1.2.10-8 1.0.10-8 
 M 0.1 1.6.10-7 0.05 1.2.10-7 6.0.10-8 4.4.10-8 3.6.10-8 3.0.10-8 
Bi-214 F 0.1 5.0.10-8 0.05 3.5.10-8 1.6.10-8 1.1.10-8 8.2.10-9 7.1.10-9 
 M 0.1 8.7.10-8 0.05 6.1.10-8 3.1.10-8 2.2.10-8 1.7.10-8 1.4.10-8 - 204 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
polonium           
Po-203 F 0.2 1.9.10-10 0.1 1.5.10-10 7.7.10-11 4.7.10-11 2.8.10-11 2.3.10-11 
 M 0.2 2.7.10-10 0.1 2.1.10-10 1.1.10-10 6.7.10-11 4.3.10-11 3.5.10-11 
 S 0.02 2.8.10-10 0.01 2.2.10-10 1.1.10-10 7.0.10-11 4.5.10-11 3.6.10-11 
Po-205 F 0.2 2.6.10-10 0.1 2.1.10-10 1.1.10-10 6.6.10-11 4.1.10-11 3.3.10-11 
 M 0.2 4.0.10-10 0.1 3.1.10-10 1.7.10-10 1.1.10-10 8.1.10-11 6.5.10-11 
 S 0.02 4.2.10-10 0.01 3.2.10-10 1.8.10-10 1.2.10-10 8.5.10-11 6.9.10-11 
Po-207 F 0.2 4.8.10-10 0.1 4.0.10-10 2.1.10-10 1.3.10-10 7.3.10-11 5.8.10-11 
 M 0.2 6.2.10-10 0.1 5.1.10-10 2.6.10-10 1.6.10-10 9.9.10-11 7.8.10-11 
 S 0.02 6.6.10-10 0.01 5.3.10-10 2.7.10-10 1.7.10-10 1.0.10-10 8.2.10-11 
Po-210 F 0.2 7.4.10-6 0.1 4.8.10-6 2.2.10-6 1.3.10-6 7.7.10-7 6.1.10-7 
 M 0.2 1.5.10-5 0.1 1.1.10-5 6.7.10-6 4.6.10-6 4.0.10-6 3.3.10-6 
 S 0.02 1.8.10-5 0.01 1.4.10-5 8.6.10-6 5.9.10-6 5.1.10-6 4.3.10-6 
astatine           
At-207 F 1.0 2.4.10-9 1.0 1.7.10-9 8.9.1 0-10 5.9.10-10 4.0.10-10 3.3.10-10 
 M 1.0 9.2.10-9 1.0 6.7.10-9 4.3.10-9 3.1.10-9 2.9.10-9 2.3.10-9 
At-211 F 1.0 1.4.10-7 1.0 9.7.10-8 4.3.10-8 2.8.10-8 1.7.10-8 1.6.10-8 
 M 1.0 5.2.10-7 1.0 3.7.10-7 1.9.10-7 1.4.10-7 1.3.10-7 1.1.10-7 
francium           
Fr-222 F 1.0 9.1.10-8 1.0 6.3.10-8 3.0.10-8 2.1.10-8 1.6.10-8 1.4.10-8 
Fr-223 F 1.0 1.1.10-8 1.0 7.3.10-9 3.2.10-9 1.9.10-9 1.0.10-9 8.9.10-10 
radium           
Ra-223 F 0.6 3.0.10-6 0.3**  1.0.10-6 4.9.10-7 4.0.10-7 3.3.10-7 1.2.10-7 
 M 0.2 2.8.10-5 0.1 2.1.10-5 1.3.10-5 9.9.10-6 9.4.10-6 7.4.10-6 
 S 0.02 3.2.10-5 0.01 2.4.10-5 1.5.10-5 1.1.10-5 1.1.10-5 8.7.10-6 
Ra-224 F 0.6 1.5.10-6 0.3**  6.0.10-7 2.9.10-7 2.2.10-7 1.7.10-7 7.5.10-8 
 M 0.2 1.1.10-5 0.1 8.2.10-6 5.3.10-6 3.9.10-6 3.7.10-6 3.0.10-6 
 S 0.02 1.2.10-5 0.01 9.2.10-6 5.9.10-6 4.4.10-6 4.2.10-6 3.4.10-6 
Ra-225 F 0.6 4.0.10-6 0.3**  1.2.10-6 5.6.10-7 4.6.10-7 3.8.10-7 1.3.10-7 
 M 0.2 2.4.10-5 0.1 1.8.10-5 1.1.10-5 8.4.10-6 7.9.10-6 6.3.10-6 
 S 0.02 2.8.10-5 0.01 2.2.10-5 1.4.10-5 1.0.10-5 9.8.10-6 7.7.10-6 
Ra-226 F 0.6 2.6.10-6 0.3**  9.4.10-7 5.5.10-7 7.2.10-7 1.3.10-6 3.6.10-7 
 M 0.2 1.5.10-5 0.1 1.1.10-5 7.0.10-6 4.9.10-6 4.5.10-6 3.5.10-6 
 S 0.02 3.4.10-5 0.01 2.9.10-5 1.9.10-5 1.2.10-5 1.0.10-5 9.5.10-6 
Ra-227 F 0.6 1.5.10-9 0.3**  1.2.10-9 7.8.10-10 6.1.10-10 5.3.10-10 4.6.10-10 - 205 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.2 8.0.10-10 0.1 6.7.10-10 4.4.10-10 3.2.10-10 2.9.10-10 2.8.10-10 
 S 0.02 1.0.10-9 0.01 8.5.10-10 4.4.10-10 2.9.10-10 2.4.10-10 2.2.10-10 
Ra-228 F 0.6 1.7.10-5 0.3**  5.7.10-6 3.1.10-6 3.6.10-6 4.6.1 0-6 9.0.10-7 
 M 0.2 1.5.10-5 0.1 1.0.10-5 6.3.10-6 4.6.10-6 4.4.10-6 2.6.10-6 
 S 0.02 4.9.10-5 0.01 4.8.10-5 3.2.10-5 2.0.10-5 1.6.10-5 1.6.10-5 
actinium           
Ac-224 F 0.005  1.3.10-7 5.0.10-4 8.9.10-8 4.7.10-8 3.1.10-8 1.4.10-8 1.1.10-8 
 M 0.005  4.2.10-7 5.0.10-4 3.2.10-7 2.0.10-7 1.5.10-7 1.4.10-7 1.1.10-7 
 S 0.005  4.6.10-7 5.0.10-4 3.5.10-7 2.2.10-7 1.7.10-7 1.6.10-7 1.3.10-7 
Ac-225 F 0.005  1.1.10-5 5.0.10-4 7.7.10-6 4.0.10-6 2.6.10-6 1.1.10-6 8.8.10-7 
 M 0.005  2.8.10-5 5.0.10-4 2.1.10-5 1.3.1 0-5 1.0.10-5 9.3.10-6 7.4.10-6 
 S 0.005  3.1.10-5 5.0.10-4 2.3.10-5 1.5.10-5 1.1.10-5 1.1.10-5 8.5.10-6 
Ac-226 F 0.005  1.5.10-6 5.0.10-4 1.1.10-6 4.0.10-7 2.6.10-7 1.2.10-7 9.6.10-8 
 M 0.005  4.3.10-6 5.0.10-4 3.2.10-6 2.1.10-6 1.5.10-6 1.5.10-6 1.2.10-6 
 S 0.005  4.7.10-6 5.0.10-4 3.5.10-6 2.3.10-6 1.7.10-6 1.6.10-6 1.3.10-6 
Ac-227 F 0.005  1.7.10-3 5.0.10-4 1.6.10-3 1.0.10-3 7.2.10-4 5.6.10-4 5.5.10-4 
 M 0.005  5.7.10-4 5.0.10-4 5.5.10-4 3.9.10-4 2.6.10-4 2.3.10-4 2.2.10-4 
 S 0.005  2.2.10-4 5.0.10-4 2.0.10-4 1.3.10-4 8.7.10-5 7.6.10-5 7.2.10-5 
Ac-228 F 0.005  1.8.10-7 5.0.10-4 1.6.10-7 9.7.10-8 5.7.10-8 2.9.10-8 2.5.10-8 
 M 0.005  8.4.10-8 5.0.10-4 7.3.10-8 4.7.10-8 2.9.10-8 2.0.10-8 1.7.10-8 
 S 0.005  6.4.10-8 5.0.10-4 5.3.10-8 3.3.10-8 2.2.10-8 1.9.10-8 1.6.10-8 
thorium           
Th-226 F 0.005  1.4.10-7 5.0.10-4 1.0.10-7 4.8.10-8 3.4.10-8 2.5.10-8 2.2.10-8 
 M 0.005  3.0.10-7 5.0.10-4 2.1.10-7 1.1.10-7 8.3.10-8 7.0.10-8 5.8.10-8 
 S 0.005  3.1.10-7 5.0.10-4 2.2.10-7 1.2.10-7 8.8.10-8 7.5.10-8 6.1.10-8 
Th-227 F 0.005  8.4.10-6 5.0.10-4 5.2.10-6 2.6.10-6 1.6.10-6 1.0.10-6 6.7.10-7 
 M 0.005  3.2.10-5 5.0.10-4 2.5.10-5 1.6.10-5 1.1.10-5 1.1.10-5 8.5.10-6 
 S 0.005  3.9.10-5 5.0.10-4 3.0.10-5 1.9.10-5 1.4.10-5 1.3.10-5 1.0.10-5 
Th-228 F 0.005  1.8.10-4 5.0.10-4 1.5.10-4 8.3.10-5 5.2.10-5 3.5.10-5 3.0.10-5 
 M 0.005  1.3.10-4 5.0.10-4 1.1.10-4 6.8.10-5 4.6.10-5 3.9.10-5 3.2.10-5 
 S 0.005  1.6.10-4 5.0.10-4 1.3.10-4 8.2.10-5 5.5.10-5 4.7.10-5 4.0.10-5 
Th-229 F 0.005  5.4.10-4 5.0.10-4 5.1.10-4 3.6.10-4 2.9.10-4 2.4.10-4 2.4.10-4 
 M 0.005  2.3.10-4 5.0.10-4 2.1.10-4 1.6.10-4 1.2.10-4 1.1.10-4 1.1.10-4 
 S 0.005  2.1.10-4 5.0.10-4 1.9.10-4 1.3.10-4 8.7.10-5 7.6.10-5 7.1.10-5 
Th-230 F 0.005  2.1.10-4 5.0.10-4 2.0.10-4 1.4.10-4 1.1.10-4 9.9.10-5 1.0.10-4 - 206 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.005  7.7.10-5 5.0.10-4 7.4.10-5 5.5.10-5 4.3.10-5 4.2.10-5 4.3.10-5 
 S 0.005  4.0.10-5 5.0.10-4 3.5.10-5 2.4.10-5 1.6.10-5 1.5.10-5 1.4.10-5 
Th-231 F 0.005  1.1.10-9 5.0.10-4 7.2.10-10 2.6.10-10 1.6.10-10 9.2.10-11 7.8.10-11 
 M 0.005  2.2.10-9 5.0.10-4 1.6.10-9 8.0.1 0-10 4.8.10-10 3.8.10-10 3.1.10-10 
 S 0.005  2.4.10-9 5.0.10-4 1.7.10-9 7.6.10-10 5.2.10-10 4.1.10-10 3.3.10-10 
Th-232 F 0.005  2.3.10-4 5.0.10-4 2.2.10-4 1.6.10-4 1.3.10-4 1.2.10-4 1.1.10-4 
 M 0.005  8.3.10-5 5.0.10-4 8.1.10-5 6.3.10-5 5.0.10-5 4.7.10-5 4.5.10-5 
 S 0.005  5.4.10-5 5.0.10-4 5.0.10-5 3.7.10-5 2.6.10-5 2.5.10-5 2.5.10-5 
Th-234 F 0.005  4.0.10-8 5.0.10-4 2.5.10-8 1.1.10-8 6.1.10-9 3.5.10-9 2.5.10-9 
 M 0.005  3.9.10-8 5.0.10-4 2.9.10-8 1.5.10-8 1.0.10-8 7.9.10-9 6.6.10-9 
 S 0.005  4.1.10-8 5.0.10-4 3.1.10-8 1.7.10-8 1.1.10-8 9.1.10-9 7.7.10-9 
protactinium           
Pa-227 M 0.005  3.6.10-7 5.0.10-4 2.6.10-7 1.4.10-7 1.0.10-7 9.0.10-8 7.4.10-8 
 S 0.005  3.8.10-7 5.0.10-4 2.8.10-7 1.5.10-7 1.1.10-7 8.1.10-8 8.0.10-8 
Pa-228 M 0.005  2.6.10-7 5.0.10-4 2.1.10-7 1.3.10-7 8.8.10-8 7.7.10-8 6.4.10-8 
 S 0.005  2.9.10-7 5.0.10-4 2.4.10-7 1.5.10-7 1.0.10-7 9.1.10-8 7.5.10-8 
Pa-230 M 0.005  2.4.10-6 5.0.10-4 1.8.10-6 1.1.10-6 8.3.10-7 7.6.10-7 6.1.10-7 
 S 0.005  2.9.10-6 5.0.10-4 2.2.10-6 1.4.10-6 1.0.10-6 9.6.10-7 7.6.10-7 
Pa-231 M 0.005  2.2.10-4 5.0.10-4 2.3.10-4 1.9.10-4 1.5.10-4 1.5.10-4 1.4.10-4 
 S 0.005  7.4.10-5 5.0.10-4 6.9.10-5 5.2.10-5 3.9.10-5 3.6.10-5 3.4.10-5 
Pa-232 M 0.005  1.9.10-8 5.0.10-4 1.8.10-8 1.4.10-8 1.1.10-8 1.0.10-8 1.0.10-8 
 S 0.005 1.0.10-8 5.0.10-4 8.7.10-9 5.9.10-9 4.1.10-9 3.7.10-9 3.5.10-9 
Pa-233 M 0.005  1.5.10-8 5.0.10-4 1.1.10-8 6.5.10-9 4.7.10-9 4.1.10-9 3.3.10-9 
 S 0.005  1.7.10-8 5.0.10-4 1.3.10-8 7.5.10-9 5.5.10-9 4.9.10-9 3.9.10-9 
Pa-234 M 0.005  2.8.10-9 5.0.10-4 2.0.1 0-9 1.0.10-9 6.8.10-10 4.7.10-10 3.8.10-10 
 S 0.005  2.9.10-9 5.0.10-4 2.1.10-9 1.1.10-9 7.1.10-10 5.0.10-10 4.0.10-10 
uranium           
U-230 F 0.04 3.2.10-6 0.02 1.5.10-6 7.2.10-7 5.4.10-7 4.1.10-7 3.8.10-7 
 M 0.04 4.9.10-5 0.02 3.7.10-5 2.4.10-5 1.8.1 0-5 1.7.10-5 1.3.10-5 
 S 0.02 5.8.10-5 0.002  4.4.10-5 2.8.10-5 2.1.10-5 2.0.10-5 1.6.10-5 
U-231 F 0.04 1.0.10-9 0.02 6.8.10-10 3.2.10-10 1.5.10-10 1.0.10-10 6.4.10-11 
 M 0.04 2.5.10-9 0.02 2.0.10-9 1.0.10-9 6.9.10-10 5.7.10-10 4.7.10-10 
 S 0.02 2.7.10-9 0.002  2.0.10-9 1.1.10-9 7.7.10-10 6.3.10-10 5.2.10-10 
U-232 F 0.04 1.6.10-5 0.02 1.0.10-5 6.9.10-6 6.8.10-6 7.5.10-6 4.0.10-6 
 M 0.04 3.0.10-5 0.02 2.4.10-5 1.6.10-5 1.1.10-5 1.0.10-5 7.8.10-6 - 207 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.02 1.0.10-4 0.002  9.7.10-5 6.6.10-5 4.3.10-5 3.8.10-5 3.7.10-5 
U-233 F 0.04 2.2.10-6 0.02 1.4.10-6 9.4.10-7 8.4.10-7 8.6.10-7 5.8.10-7 
 M 0.04 1.5.10-5 0.02 1.1.10-5 7.2.10-6 4.9.10-6 4.3.10-6 3.6.10-6 
 S 0.02 3.4.10-5 0.002  3.0.10-5 1.9.10-5 1.2.10-5 1.1.10-5 9.6.10-6 
U-234 F 0.04 2.1.10-6 0.02 1.4.10-6 9.0.10-7 8.0.10-7 8.2.10-7 5.6.10-7 
 M 0.04 1.5.10-5 0.02 1.1.10-5 7.0.10-6 4.8.10-6 4.2.10-6 3.5.10-6 
 S 0.02 3.3.10-5 0.002  2.9.10-5 1.9.10-5 1.2.10-5 1.0.10-5 9.4.10-6 
U-235 F 0.04 2.0.10-6 0.02 1.3.10-6 8.5.10-7 7.5.10-7 7.7.10-7 5.2.10-7 
 M 0.04 1.3.10-5 0.02 1.0.10-5 6.3.10-6 4.3.10-6 3.7.10-6 3.1.10-6 
 S 0.02 3.0.10-5 0.002  2.6.10-5 1.7.10-5 1.1.10-5 9.2.10-6 8.5.10-6 
U-236 F 0.04 2.0.10-6 0.02 1.3.10-6 8.5.10-7 7.5.10-7 7.8.10-7 5.3.10-7 
 M 0.04 1.4.10-5 0.02 1.0.10-5 6.5.10-6 4.5.10-6 3.9.1 0-6 3.2.10-6 
 S 0.02 3.1.10-5 0.002  2.7.10-5 1.8.10-5 1.1.10-5 9.5.10-6 8.7.10-6 
U-237 F 0.04 1.8.10-9 0.02 1.5.10-9 6.6.10-10 4.2.10-10 1.9.10-10 1.8.10-10 
 M 0.04 7.8.10-9 0.02 5.7.10-9 3.3.10-9 2.4.10-9 2.1.10-9 1.7.10-9 
 S 0.02 8.7.10-9 0.002  6.4.1 0-9 3.7.10-9 2.7.10-9 2.4.10-9 1.9.10-9 
U-238 F 0.04 1.9.10-6 0.02 1.3.10-6 8.2.10-7 7.3.10-7 7.4.10-7 5.0.10-7 
 M 0.04 1.2.10-5 0.02 9.4.10-6 5.9.10-6 4.0.10-6 3.4.10-6 2.9.10-6 
 S 0.02 2.9.10-5 0.002  2.5.10-5 1.6.10-5 1.0.10-5 8.7.10-6 8.0.10-6 
U-239 F 0.04 1.0.10-10 0.02 6.6.10-11 2.9.10-11 1.9.10-11 1.2.10-11 1.0.10-11 
 M 0.04 1.8.10-10 0.02 1.2.10-10 5.6.10-11 3.8.10-11 2.7.10-11 2.2.10-11 
 S 0.02 1.9.10-10 0.002  1.2.10-10 5.9.10-11 4.0.10-11 2.9.10-11 2.4.10-11 
U-240 F 0.04 2.4.10-9 0.02 1.6.10-9 7.1.10-10 4.5.10-10 2.3.10-10 2.0.10-10 
 M 0.04 4.6.10-9 0.02 3.1.10-9 1.7.10-9 1.1.10-9 6.5.10-10 5.3.10-10 
 S 0.02 4.9.10-9 0.002  3.3.10-9 1.6.10-9 1.1.10-9 7.0.10-10 5.8.10-10 
neptunium           
Np-232 F 0.005  2.0.10-10 5.0.10-4 1.9.10-10 1.2.10-10 1.1.10-10 1.1.10-10 1.2.10-10 
 M 0.005  8.9.10-11 5.0.10-4 8.1.10-11 5.5.10-11 4.5.10-11 4.7.10-11 5.0.10-11 
 S 0.005  1.2.10-10 5.0.10-4 9.7.10-11 5.8.10-11 3.9.10-11 2.5.10-11 2.4.10-11 
Np-233 F 0.005  1.1.10-11 5.0.10-4 8.7.10-12 4.2.10-12 2.5.10-12 1.4.10-12 1.1.10-12 
 M 0.005  1.5.10-11 5.0.10-4 1.1.10-11 5.5.10-12 3.3.10-12 2.1.10-12 1.6.10-12 
 S 0.005  1.5.10-11 5.0.10-4 1.2.10-11 5.7.10-12 3.4.10-12 2.1.10-12 1.7.10-12 
Np-234 F 0.005  2.9.10-9 5.0.10-4 2.2.10-9 1.1.10-9 7.2.10-10 4.3.10-10 3.5.10-10 
 M 0.005  3.8.10-9 5.0.10-4 3.0.10-9 1.6.10-9 1.0.10-9 6.5.10-10 5.3.10-10 
 S 0.005  3.9.10-9 5.0.10-4 3.1.10-9 1.6.10-9 1.0.10-9 6.8.10-10 5.5.10-10 - 208 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Np-235 F 0.005  4.2.10-9 5.0.10-4 3.5.10-9 1.9.10-9 1.1.10-9 7.5.10-10 6.3.10-10 
 M 0.005  2.3.10-9 5.0.10-4 1.9.10-9 1.1.10-9 6.8.10-10 5.1.10-10 4.2.10-10 
 S 0.005  2.6.10-9 5.0.10-4 2.2.10-9 1.3.10-9 8.3.10-10 6.3.10-10 5.2.10-10 
Np-236 F 0.005  8.9.10-6 5.0.10-4 9.1.10-6 7.2.10-6 7.5.10-6 7.9.10-6 8.0.10-6 
 M 0.005  3.0.10-6 5.0.10-4 3.1.10-6 2.7.10-6 2.7.10-6 3.1.10-6 3.2.10-6 
 S 0.005  1.6.10-6 5.0.10-4 1.6.10-6 1.3.10-6 1.0.10-6 1.0.10-6 1.0.10-6 
Np-236m  F 0.005  2.8.10-8 5.0.10-4 2.6.10-8 1.5.10-8 1.1.10-8 8.9.10-9 9.0.10-9 
 M 0.005  1.6.10-8 5.0.10-4 1.4.10-8 8.9.10-9 6.2.10-9 5.6.10-9 5.3.10-9 
 S 0.005  1.6.10-8 5.0.10-4 1.3.10-8 8.5.10-9 5.7.10-9 4.8.10-9 4.2.10-9 
Np-237 F 0.005  9.8.10-5 5.0.10-4 9.3.10-5 6.0.10-5 5.0.10-5 4.7.10-5 5.0.10-5 
 M 0.005  4.4.10-5 5.0.10-4 4.0.10-5 2.8.10-5 2.2.10-5 2.2.10-5 2.3.10-5 
 S 0.005  3.7.10-5 5.0.10-4 3.2.10-5 2.1.10-5 1.4.10-5 1.3.10-5 1.2.10-5 
Np-238 F 0.005  9.0.10-9 5.0.10-4 7.9.10-9 4.8.10-9 3.7.10-9 3.3.10-9 3.5.10-9 
 M 0.005  7.3.10-9 5.0.10-4 5.8.10-9 3.4.10-9 2.5.10-9 2.2.10-9 2.1.10-9 
 S 0.005  8.1.10-9 5.0.10-4 6.2.10-9 3.2.10-9 2.1.10-9 1.7.10-9 1.5.10-9 
Np-239 F 0.005  2.6.10-9 5.0.10-4 1.4.10-9 6.3.10-10 3.8.10-10 2.1.10-10 1.7.10-10 
 M 0.005  5.9.10-9 5.0.10-4 4.2.10-9 2.0.10-9 1.4.10-9 1.2.10-9 9.3.10-10 
 S 0.005  5.6.10-9 5.0.10-4 4.0.10-9 2.2.10-9 1.6.10-9 1.3.10-9 1.0.10-9 
Np-240 F 0.005  3.6.10-10 5.0.10-4 2.6.10-10 1.2.10-10 7.7.10-11 4.7.10-11 4.0.10-11 
 M 0.005  6.3.10-10 5.0.10-4 4.4.10-10 2.2.10-10 1.4.10-10 1.0.10-10 8.5.10-11 
 S 0.005  6.5.10-10 5.0.10-4 4.6.10-10 2.3.10-10 1.5.10-10 1.1.10-10 9.0.10-11 
plutonium           
Pu-234 F 0.005 3.0.10-8 5.0.10-4 2.0.10-8 9.8.10-9 5.7.10-9 3.6.10-9 3.0.10-9 
 M 0.005  7.8.10-8 5.0.10-4 5.9.10-8 3.7.10-8 2.8.10-8 2.6.10-8 2.1.10-8 
 S 1.0.10-4 8.7.10-8 1.0.10-5 6.6.10-8 4.2.10-8 3.1.10-8 3.0.10-8 2.4.10-8 
Pu-235 F 0.005  1.0.10-11 5.0.10-4 7.9.10-12 3.9.10-12 2.2.10-12 1.3.10-12 1.0.10-12 
 M 0.005  1.3.10-11 5.0.10-4 1.0.10-11 5.0.10-12 2.9.10-12 1.9.10-12 1.4.10-12 
 S 1.0.10-4 1.3.10-11 1.0.10-5 1.0.10-11 5.1.10-12 3.0.10-12 1.9.10-12 1.5.10-12 
Pu-236 F 0.005  1.0.10-4 5.0.10-4 9.5.10-5 6.1.10-5 4.4.10-5 3.7.10-5 4.0.10-5 
 M 0.005  4.8.10-5 5.0.10-4 4.3.10-5 2.9.10-5 2.1.10-5 1.9.10-5 2.0.10-5 
 S 1.0.10-4 3.6.10-5 1.0.10-5 3.1.10-5 2.0.10-5 1.4.10-5 1.2.10-5 1.0.10-5 
Pu-237 F 0.005  2.2.10-9 5.0.10-4 1.6.10-9 7.9.10-10 4.8.10-10 2.9.10-10 2.6.10-10 
 M 0.005  1.9.10-9 5.0.10-4 1.4.10-9 8.2.10-10 5.4.10-10 4.3.10-10 3.5.10-10 
 S 1.0.10-4 2.0.10-9 1.0.10-5 1.5.10-9 8.8.10-10 5.9.10-10 4.8.10-10 3.9.10-10 
Pu-238 F 0.005  2.0.10-4 5.0.10-4 1.9.10-4 1.4.10-4 1.1.10-4 1.0.10-4 1.1.10-4 - 209 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 M 0.005  7.8.10-5 5.0.10-4 7.4.10-5 5.6.10-5 4.4.10-5 4.3.10-5 4.6.10-5 
 S 1.0.10-4 4.5.10-5 1.0.10-5 4.0.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Pu-239 F 0.005  2.1.10-4 5.0.10-4 2.0.10-4 1.5.10-4 1.2.10-4 1.1.10-4 1.2.10-4 
 M 0.005  8.0.10-5 5.0.10-4 7.7.10-5 6.0.1 0-5 4.8.10-5 4.7.10-5 5.0.10-5 
 S 1.0.10-4 4.3.10-5 1.0.10-5 3.9.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Pu-240 F 0.005  2.1.10-4 5.0.10-4 2.0.10-4 1.5.10-4 1.2.10-4 1.1.10-4 1.2.10-4 
 M 0.005  8.0.10-5 5.0.10-4 7.7.10-5 6.0.10-5 4.8.10-5 4.7.10-5 5.0.10-5 
 S 1.0.10-4 4.3.10-5 1.0.10-5 3.9.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Pu-241 F 0.005  2.8.10-6 5.0.10-4 2.9.10-6 2.6.10-6 2.4.10-6 2.2.10-6 2.3.10-6 
 M 0.005  9.1.10-7 5.0.10-4 9.7.10-7 9.2.10-7 8.3.10-7 8.6.10-7 9.0.10-7 
 S 1.0.10-4 2.2.10-7 1.0.10-5 2.3.10-7 2.0.10-7 1.7.10-7 1.7.10-7 1.7.10-7 
Pu-242 F 0.005  2.0.10-4 5.0.10-4 1.9.10-4 1.4.10-4 1.2.10-4 1.1.10-4 1.1.10-4 
 M 0.005  7.6.10-5 5.0.10-4 7.3.10-5 5.7.10-5 4.5.10-5 4.5.10-5 4.8.10-5 
 S 1.0.10-4 4.0.10-5 1.0.10-5 3.6.10-5 2.5.10-5 1.7.10-5 1.6.10-5 1.5.10-5 
Pu-243 F 0.005  2.7.10-10 5.0.10-4 1.9.10-10 8.8.10-11 5.7.10-11 3.5.10-11 3.2.10-11 
 M 0.005  5.6.10-10 5.0.10-4 3.9.10-10 1.9.10-10 1.3.10-10 8.7.10-11 8.3.10-11 
 S 1.0.10-4 6.0.10-10 1.0.10-5 4.1.10-10 2.0.10-10 1.4.10-10 9.2.10-11 8.6.10-11 
Pu-244 F 0.005  2.0.10-4 5.0.10-4 1.9.10-4 1.4.10-4 1.2.10-4 1.1.10-4 1.1.10-4 
 M 0.005  7.4.10-5 5.0.10-4 7.2.10-5 5.6.10-5 4.5.10-5 4.4.10-5 4.7.10-5 
 S 1.0.10-4 3.9.10-5 1.0.10-5 3.5.10-5 2.4.10-5 1.7.10-5 1.5.10-5 1.5.10-5 
Pu-245 F 0.005  1.8.10-9 5.0.10-4 1.3.10-9 5.6.10-10 3.5.10-10 1.9.10-10 1.6.10-10 
 M 0.005  3.6.10-9 5.0.10-4 2.5.10-9 1.2.10-9 8.0.10-10 5.0.10-10 4.0.10-10 
 S 1.0.10-4 3.8.10-9 1.0.10-5 2.6.10-9 1.3.10-9 8.5.10-10 5.4.10-10 4.3.10-10 
Pu-246 F 0.005  2.0.10-8 5.0.10-4 1.4.10-8 7.0.10-9 4.4.10-9 2.8.10-9 2.5.10-9 
 M 0.005  3.5.10-8 5.0.10-4 2.6.10-8 1.5.10-8 1.1.10-8 9.1.10-9 7.4.10-9 
 S 1.0.10-4 3.8.10-8 1.0.10-5 2.8.10-8 1.6.10-8 1.2.10-8 1.0.10-8 8.0.10-9 
americium           
Am-237 F 0.005  9.8.10-11 5.0.10-4 7.3.10-11 3.5.10-11 2.2.10-11 1.3.10-11 1.1.10-11 
 M 0.005  1.7.10-10 5.0.10-4 1.2.10-10 6.2.10-11 4.1.10-11 3.0.10-11 2.5.10-11 
 S 0.005  1.7.10-10 5.0.10-4 1.3.10-10 6.5.10-11 4.3.10-11 3.2.10-11 2.6.10-11 
Am-238 F 0.005  4.1.10-10 5.0.10-4 3.8.10-10 2.5.10-10 2.0.10-10 1.8.10-10 1.9.10-10 
 M 0.005  3.1.10-10 5.0.10-4 2.6.10-10 1.3.10-10 9.6.10-11 8.8.10-11 9.0.10-11 
 S 0.005  2.7.10-10 5.0.10-4 2.2.10-10 1.3.10-10 8.2.10-11 6.1.10-11 5.4.10-11 
Am-239 F 0.005  8.1.10-10 5.0.10-4 5.8.10-10 2.6.10-10 1.6.10-10 9.1.10-11 7.6.10-11 
 M 0.005  1.5.10-9 5.0.10-4 1.1.10-9 5.6.10-10 3.7.10-10 2.7.10-10 2.2.10-10 - 210 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
 S 0.005  1.6.10-9 5.0.10-4 1.1.10-9 5.9.10-10 4.0.10-10 2.5.10-10 2.4.10-10 
Am-240 F 0.005  2.0.10-9 5.0.10-4 1.7.10-9 8.8.10-10 5.7.10-10 3.6.10-10 2.3.10-10 
 M 0.005  2.9.10-9 5.0.10-4 2.2.10-9 1.2.10-9 7.7.10-10 5.3.10-10 4.3.10-10 
 S 0.005  3.0.10-9 5.0.10-4 2.3.10-9 1.2.10-9 7.8.10-10 5.3.10-10 4.3.10-10 
Am-241 F 0.005  1.8.10-4 5.0.10-4 1.8.10-4 1.2.10-4 1.0.10-4 9.2.10-5 9.6.10-5 
 M 0.005  7.3.10-5 5.0.10-4 6.9.10-5 5.1.10-5 4.0.10-5 4.0.10-5 4.2.10-5 
 S 0.005  4.6.10-5 5.0.10-4 4.0.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Am-242 F 0.005  9.2.10-8 5.0.10-4 7.1.10-8 3.5.10-8 2.1.10-8 1.4.10-8 1.1.10-8 
 M 0.005  7.6.10-8 5.0.10-4 5.9.10-8 3.6.10-8 2.4.10-8 2.1.10-8 1.7.10-8 
 S 0.005  8.0.10-8 5.0.10-4 6.2.10-8 3.9.10-8 2.7.10-8 2.4.10-8 2.0.10-8 
Am-242m  F 0.005  1.6.10-4 5.0.10-4 1.5.10-4 1.1.10-4 9.4.10-5 8.8.10-5 9.2.10-5 
 M 0.005  5.2.10-5 5.0.10-4 5.3.10-5 4.1.10-5 3.4.10-5 3.5.10-5 3.7.10-5 
 S 0.005  2.5.10-5 5.0.10-4 2.4.10-5 1.7.10-5 1.2.10-5 1.1.10-5 1.1.10-5 
Am-243 F 0.005  1.8.10-4 5.0.10-4 1.7.10-4 1.2.10-4 1.0.10-4 9.1.10-5 9.6.10-5 
 M 0.005  7.2.10-5 5.0.10-4 6.8.10-5 5.0.10-5 4.0.10-5 4.0.10-5 4.1.10-5 
 S 0.005  4.4.10-5 5.0.10-4 3.9.10-5 2.6.10-5 1.8.10-5 1.6.10-5 1.5.10-5 
Am-244 F 0.005  1.0.10-8 5.0.10-4 9.2.10-9 5.6.10-9 4.1.10-9 3.5.10-9 3.7.10-9 
 M 0.005  6.0.10-9 5.0.10-4 5.0.10-9 3.2.10-9 2.2.10-9 2.0.10-9 2.0.10-9 
 S 0.005  6.1.10-9 5.0.10-4 4.8.10-9 2.4.10-9 1.6.10-9 1.4.10-9 1.2.10-9 
Am-244m  F 0.005  4.6.10-10 5.0.10-4 4.0.10-10 2.4.10-10 1.8.10-10 1.5.10-10 1.6.10-10 
 M 0.005  3.3.10-10 5.0.10-4 2.1.10-10 1.3.10-10 9.2.10-11 8.3.10-11 8.4.10-11 
 S 0.005  3.0.10-10 5.0.10-4 2.2.10-10 1.2.10-10 8.1.10-11 5.5.10-11 5.7.10-11 
Am-245 F 0.005  2.1.10-10 5.0.10-4 1.4.10-10 6.2.10-11 4.0.10-11 2.4.10-11 2.1.10-11 
 M 0.005  3.9.10-10 5.0.10-4 2.6.10-10 1.3.10-10 8.7.10-11 6.4.10-11 5.3.10-11 
 S 0.005  4.1.10-10 5.0.10-4 2.8.10-10 1.3.10-10 9.2.10-11 6.8.10-11 5.6.10-11 
Am-246 F 0.005  3.0.10-10 5.0.10-4 2.0.10-10 9.3.10-11 6.1.10-11 3.8.10-11 3.3.10-11 
 M 0.005  5.0.10-10 5.0.10-4 3.4.10-10 1.6.10-10 1.1.10-10 7.9.10-11 6.6.10-11 
 S 0.005  5.3.10-10 5.0.10-4 3.6.10-10 1.7.10-10 1.2.10-10 8.3.10-11 6.9.10-11 
Am-246m  F 0.005  1.3.10-10 5.0.10-4 8.9.1 0-11 4.2.10-11 2.6.10-11 1.6.10-11 1.4.10-11 
 M 0.005  1.9.10-10 5.0.10-4 1.3.10-10 6.1.10-11 4.0.10-11 2.6.10-11 2.2.10-11 
 S 0.005  2.0.10-10 5.0.10-4 1.4.10-10 6.4.10-11 4.1.10-11 2.7.10-11 2.3.10-11 
curium           
Cm-238 F 0.005  7.7.10-9 5.0.10-4 5.4.10-9 2.6.10-9 1.8.10-9 9.2.10-10 7.8.10-10 
 M 0.005  2.1.10-8 5.0.10-4 1.5.10-8 7.9.10-9 5.9.10-9 5.6.10-9 4.5.10-9 
 S 0.005  2.2.10-8 5.0.10-4 1.6.10-8 8.6.10-9 6.4.10-9 6.1.10-9 4.9.10-9 - 211 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Cm-240 F 0.005  8.3.10-6 5.0.10-4 6.3.10-6 3.2.10-6 2.0.10-6 1.5.10-6 1.3.10-6 
 M 0.005  1.2.10-5 5.0.10-4 9.1.10-6 5.8.10-6 4.2.10-6 3.8.10-6 3.2.10-6 
 S 0.005  1.3.10-5 5.0.10-4 9.9.10-6 6.4.10-6 4.6.10-6 4.3.10-6 3.5.10-6 
Cm-241 F 0.005  1.1.10-7 5.0.10-4 8.9.10-8 4.9.10-8 3.5.10-8 2.8.10-8 2.7.10-8 
 M 0.005  1.3.10-7 5.0.10-4 1.0.10-7 6.6.10-8 4.8.10-8 4.4.10-8 3.7.10-8 
 S 0.005  1.4.10-7 5.0.10-4 1.1.10-7 6.9.10-8 4.9.10-8 4.5.10-8 3.7.10-8 
Cm-242 F 0.005  2.7.10-5 5.0.10-4 2.1.10-5 1.0.10-5 6.1.10-6 4.0.10-6 3.3.10-6 
 M 0.005  2.2.10-5 5.0.10-4 1.8.10-5 1.1.10-5 7.3.10-6 6.4.10-6 5.2.10-6 
 S 0.005  2.4.10-5 5.0.10-4 1.9.10-5 1.2.10-5 8.2.10-6 7.3.10-6 5.9.10-6 
Cm-243 F 0.005  1.6.10-4 5.0.10-4 1.5.10-4 9.5.10-5 7.3.10-5 6.5.10-5 6.9.10-5 
 M 0.005  6.7.10-5 5.0.10-4 6.1.10-5 4.2.10-5 3.1.10-5 3.0.10-5 3.1.10-5 
 S 0.005 4.6.10-5 5.0.10-4 4.0.10-5 2.6.10-5 1.8.10-5 1.6.10-5 1.5.10-5 
Cm-244 F 0.005  1.5.10-4 5.0.10-4 1.3.10-4 8.3.10-5 6.1.10-5 5.3.10-5 5.7.10-5 
 M 0.005  6.2.10-5 5.0.10-4 5.7.10-5 3.7.10-5 2.7.10-5 2.6.10-5 2.7.10-5 
 S 0.005  4.4.10-5 5.0.10-4 3.8.10-5 2.5.10-5 1.7.10-5 1.5.10-5 1.3.10-5 
Cm-245 F 0.005  1.9.10-4 5.0.10-4 1.8.10-4 1.2.10-4 1.0.10-4 9.4.10-5 9.9.10-5 
 M 0.005  7.3.10-5 5.0.10-4 6.9.10-5 5.1.10-5 4.1.10-5 4.1.10-5 4.2.10-5 
 S 0.005  4.5.10-5 5.0.10-4 4.0.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Cm-246 F 0.005  1.9.10-4 5.0.10-4 1.8.10-4 1.2.10-4 1.0.10-4 9.4.10-5 9.8.10-5 
 M 0.005  7.3.10-5 5.0.10-4 6.9.10-5 5.1.10-5 4.1.10-5 4.1.10-5 4.2.10-5 
 S 0.005  4.6.10-5 5.0.10-4 4.0.10-5 2.7.10-5 1.9.10-5 1.7.10-5 1.6.10-5 
Cm-247 F 0.005  1.7.10-4 5.0.10-4 1.6.10-4 1.1.10-4 9.4.10-5 8.6.10-5 9.0.10-5 
 M 0.005  6.7.10-5 5.0.10-4 6.3.10-5 4.7.10-5 3.7.10-5 3.7.10-5 3.9.10-5 
 S 0.005  4.1.10-5 5.0.10-4 3.6.10-5 2.4.10-5 1.7.10-5 1.5.10-5 1.4.10-5 
Cm-248 F 0.005  6.8.10-4 5.0.10-4 6.5.10-4 4.5.10-4 3.7.1 0-4 3.4.10-4 3.6.10-4 
 M 0.005  2.5.10-4 5.0.10-4 2.4.10-4 1.8.10-4 1.4.10-4 1.4.10-4 1.5.10-4 
 S 0.005  1.4.10-4 5.0.10-4 1.2.10-4 8.2.10-5 5.6.10-5 5.0.10-5 4.8.10-5 
Cm-249 F 0.005  1.8.10-10 5.0.10-4 9.8.10-11 5.9.10-11 4.6.10-11 4.0.10-11 4.0.10-11 
 M 0.005  2.4.10-10 5.0.10-4 1.6.10-10 8.2.10-11 5.8.10-11 3.7.10-11 3.3.10-11 
 S 0.005  2.4.10-10 5.0.10-4 1.6.10-10 7.8.10-11 5.3.10-11 3.9.10-11 3.3.10-11 
Cm-250 F 0.005  3.9.10-3 5.0.10-4 3.7.10-3 2.6.10-3 2.1.10-3 2.0.10-3 2.1.10-3 
 M 0.005  1.4.10-3 5.0.10-4 1.3.10-3 9.9.10-4 7.9.10-4 7.9.10-4 8.4.10-4 
 S 0.005  7.2.10-4 5.0.10-4 6.5.10-4 4.4.10-4 3.0.10-4 2.7.10-4 2.6.10-4 
berkelium           
Bk-245 M 0.005  8.8.10-9 5.0.10-4 6.6.10-9 4.0.10-9 2.9.10-9 2.6.10-9 2.1.10-9 - 212 - 
 
 Element  Typ
e f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide   Age < 1 year  > 1 
year  1 year  5 years  10 
years  15 years  adult  
Bk-246 M 0.005  2.1.10-9 5.0.10-4 1.7.10-9 9.3.10-10 6.0.10-10 4.0.10-10 3.3.10-10 
Bk-247 M 0.005  1.5.10-4 5.0.10-4 1.5.10-4 1.1.10-4 7.9.10-5 7.2.10-5 6.9.10-5 
Bk-249 M 0.005  3.3.10-7 5.0.10-4 3.3.10-7 2.4.10-7 1.8.10-7 1.6.10-7 1.6.10-7 
Bk-250 M 0.005  3.4.10-9 5.0.10-4 3.1.10-9 2.0.1 0-9 1.3.10-9 1.1.10-9 1.0.10-9 
californium           
Cf-244 M 0.005  7.6.10-8 5.0.10-4 5.4.10-8 2.8.10-8 2.0.10-8 1.6.10-8 1.4.10-8 
Cf-246 M 0.005  1.7.10-6 5.0.10-4 1.3.10-6 8.3.10-7 6.1.10-7 5.7.10-7 4.5.10-7 
Cf-248 M 0.005  3.8.10-5 5.0.10-4 3.2.10-5 2.1.10-5 1.4.10-5 1.0.10-5 8.8.10-6 
Cf-249 M 0.005  1.6.10-4 5.0.10-4 1.5.10-4 1.1.10-4 8.0.10-5 7.2.10-5 7.0.10-5 
Cf-250 M 0.005  1.1.10-4 5.0.10-4 9.8.10-5 6.6.10-5 4.2.10-5 3.5.10-5 3.4.10-5 
Cf-251 M 0.005  1.6.10-4 5.0.10-4 1.5.10-4 1.1.10-4 8.1.10-5 7.3.10-5 7.1.10-5 
Cf-252 M 0.005  9.7.10-5 5.0.10-4 8.7.10-5 5.6.10-5 3.2.10-5 2.2.10-5 2.0.10-5 
Cf-253 M 0.005  5.4.10-6 5.0.10-4 4.2.10-6 2.6.10-6 1.9.10-6 1.7.10-6 1.3.10-6 
Cf-254 M 0.005  2.5.10-4 5.0.10-4 1.9.10-4 1.1.10-4 7.0.10-5 4.8.10-5 4.1.10-5 
einsteinium           
Es-250m  M 0.005  2.0.10-9 5.0.10-4 1.8.10-9 1.2.10-9 7.8.10-10 6.4.10-10 6.3.10-10 
Es-251 M 0.005  7.9.10-9 5.0.10-4 6.0.10-9 3.9.10-9 2.8.10-9 2.6.10-9 2.1.10-9 
Es-253 M 0.005  1.1.10-5 5.0.10-4 8.0.10-6 5.1.10-6 3.7.10-6 3.4.10-6 2.7.10-6 
Es-254 M 0.005  3.7.10-5 5.0.10-4 3.1.10-5 2.0.10-5 1.3.10-5 1.0.10-5 8.6.10-6 
Es-254m  M 0.005  1.7.10-6 5.0.10-4 1.3.10-6 8.4.10-7 6.3.10-7 5.9.10-7 4.7.10-7 
fermium           
Fm-252 M 0.005  1.2.10-6 5.0.10-4 9.0.10-7 5.8.10-7 4.3.10-7 4.0.10-7 3.2.10-7 
Fm-253 M 0.005  1.5.10-6 5.0.10-4 1.2.10-6 7.3.10-7 5.4.10-7 5.0.10-7 4.0.10-7 
Fm-254 M 0.005  3.2.10-7 5.0.10-4 2.3.10-7 1.3.10-7 9.8.10-8 7.6.10-8 6.1.10-8 
Fm-255 M 0.005  1.2.10-6 5.0.10-4 7.3.10-7 4.7.10-7 3.5.10-7 3.4.10-7 2.7.10-7 
Fm-257 M 0.005  3.3.10-5 5.0.10-4 2.6.10-5 1.6.10-5 1.1.10-5 8.8.10-6 7.1.10-6 
mendelevium           
Md-257 M 0.005  1.0.10-7 5.0.10-4 8.2.10-8 5.1.10-8 3.6.10-8 3.1.10-8 2.5.10-8 
Md-258 M 0.005  2.4.10-5 5.0.10-4 1.9.10-5 1.2.10-5 8.6.10-6 7.3.10-6 5.9.10-6 
 
Legend:  
* - For adults f 1 = 0.1  
** - For adults f 1 = 0.2  
X - For adults f 1 = 0.3  
 
Conversion factors h inh listed in the table are used to convert intake of radionuclides to the committed effective 
dose for inhalation of radioactive aerosols by an individual from the population.  
Conversion factors h inh for intake via inhalation are listed depending on the type of absorption in the lungs.  - 213 - 
 
 For unidentified radionuclides and chemical forms of radioactive substances or characteristics of inhaled aerosol, 
activity is attrib uted to those radionuclides and their forms or such an aerosol for which the table stipulates the 
highest conversion factor.  - 214 - 
 
 Conversion factors h inh for intake of radioactive fumes by inhalation by an individual 
from the population or radiation worker  
 
Element  
Substance  f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide  Age < 1 year  ≥ 1 
year  1 year  5 years  10 years  15 years  adult  
hydrogen           
H-3 org. bound  1.0 1.1.10-10 1.0 1.1.10-10 7.0.10-11 5.5.10-11 4.1.10-11 4.1.10-11 
 HT 1.0 6.4.10-15 1.0 4.8.10-15 3.1.10-15 2.3.10-15 1.8.10-15 1.8.10-15 
 CH 3T 1.0 6.4.10-13 1.0 4.8.10-13 3.1.10-13 2.3.10-13 1.8.10-13 1.8.10-13 
 tritiated water 
vapour  1.0 6.4.10-11 1.0 4.8.10-11 3.1.10-11 2.3.10-11 1.8.10-11 1.8.10-11 
carbon           
C-11 CO 2 1.0 1.8.10-11 1.0 1.2.1 0-11 6.5.10-12 4.1.10-12 2.5.10-12 2.2.10-12 
 CO 1.0 1.0.10-11 1.0 6.7.10-12 3.5.10-12 2.2.10-12 1.4.10-12 1.2.10-12 
 CH 4 1.0 2.3.10-13 1.0 1.5.10-13 8.1.10-14 5.1.10-14 3.2.10-14 2.7.10-14 
 vapours  1.0a 2.8.10-11 1.0 1.8.10-11 9.7.10-12 6.1.10-12 3.8.1 0-12 3.2.10-12 
C-14 CO 2 1.0 1.9.10-11 1.0 1.9.10-11 1.1.10-11 8.9.10-12 6.3.10-12 6.2.10-12 
 CO 1.0 9.1.10-12 1.0 5.7.10-12 2.8.10-12 1.7.10-12 9.9.10-13 8.0.10-13 
 CH 4 1.0 6.6.10-12 1.0 7.8.10-12 4.9.10-12 4.0.10-12 2.9.10-12 2.9.10-12 
 vapours  1.0a 1.3.10-09 1.0 1.6.10-09 9.7.10-10 7.9.10-10 5.7.10-10 5.8.10-10 
sulphur           
S-35 SO 2 1.0 9.4.10-10 0.8 6.6.10-10 3.4.10-10 2.1.10-10 1.3.10-10 1.1.10-10 
 CS2 1.0 6.9.10-09 0.8 4.8.10-09 2.4.10-09 1.4.10-09 8.6.10-10 7.0.10-10 
nickel           
Ni-56 tetracarbonyl  0.1 6.8.10-09 0.05 5.2.10-09 3.2.10-09 2.1.10-09 1.4.10-09 1.2.10-09 
Ni-57 tetracarbonyl  0.1 3.1.10-09 0.05 2.3.10-09 1.4.10-09 9.2.10-10 6.5.10-10 5.6.10-10 
Ni-59 tetracarbonyl  0.1 4.0.10-09 0.05 3.3.10-09 2.0.10-09 1.3.10-09 9.1.10-10 8.3.10-10 
Ni-63 tetracarbonyl  0.1 9.5.10-09 0.05 8.0.10-09 4.8.10-09 3.0.10-09 2.2.10-09 2.0.10-09 
Ni-65 tetracarbonyl  0.1 2.0.10-09 0.05 1.4.10-09 8.1.10-10 5.6.10-10 4.0.10-10 3.6.10-10 
Ni-66 tetracarbonyl  0.1 1.0.10-08 0.05 7.1.10-09 4.0.10-09 2.7.10-09 1.8.10-09 1.6.10-09 
ruthenium           
Ru-94 RuO 4 0.1 5.5.10-10 0.05 3.5.10-10 1.8.10-10 1.1.10-10 7.0.10-11 5.6.10-11 
Ru-97 RuO 4 0.1 8.7.10-10 0.05 6.2.10-10 3.4.10-10 2.2.10-10 1.4.10-10 1.2.10-10 
Ru-103 RuO 4 0.1 9.0.10-09 0.05 6.2.10-09 3.3.10-09 2.1.10-09 1.3.10-09 1.1.10-09 
Ru-105 RuO 4 0.1 1.6.10-09 0.05 1.0.10-09 5.3.10-10 3.2.10-10 2.2.10-10 1.8.10-10 
Ru-106 RuO 4 0.1 1.6.10-07 0.05 1.1.10-07 6.1.10-08 3.7.10-08 2.2.10-08 1.8.10-08 
tellurium           
Te-116 vapours  0.6 5.9.10-10 0.3 4.4.10-10 2.5.10-10 1.6.10-10 1.1.10-10 8.7.10-11 - 215 - 
 
 Element  
Substance  f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide  Age < 1 year  ≥ 1 
year  1 year  5 years  10 years  15 years  adult  
Te-121 vapours  0.6 3.0.10-09 0.3 2.4.10-09 1.4.10-09 9.6.10-10 6.7.10-10 5.1.10-10 
Te-121m  vapours  0.6 3.5.10-08 0.3 2.7.10-08 1.6.10-08 9.8.10-09 6.6.10-09 5.5.10-09 
Te-123 vapours  0.6 2.8.10-08 0.3 2.5.10-08 1.9.10-08 1.5.10-08 1.3.10-08 1.2.10-08 
Te-123m  vapours  0.6 2.5.10-08 0.3 1.8.10-08 1.0.10-08 5.7.10-09 3.5.10-09 2.9.10-09 
Te-125m  vapours  0.6 1.5.10-08 0.3 1.1.10-08 5.9.10-09 3.2.10-09 1.9.10-09 1.5.10-09 
Te-127 vapours  0.6 6.1.10-10 0.3 4.4.10-10 2.3.10-10 1.4.10-10 9.2.10-11 7.7.10-11 
Te-127m  vapours  0.6 5.3.10-08 0.3 3.7.10-08 1.9.10-08 1.0.10-08 6.1.10-09 4.6.10-09 
Te-129 vapours  0.6 2.5.10-10 0.3 1.7.10-10 9.4.10-11 6.2.10-11 4.3.10-11 3.7.10-11 
Te-129m  vapours  0.6 4.8.10-08 0.3 3.2.10-08 1.6.1 0-08 8.5.10-09 5.1.10-09 3.7.10-09 
Te-131 vapours  0.6 5.1.10-10 0.3 4.5.10-10 2.6.10-10 1.4.10-10 9.5.10-11 6.8.10-11 
Te-131m  vapours  0.6 2.1.10-08 0.3 1.9.10-08 1.1.10-08 5.6.10-09 3.7.10-09 2.4.10-09 
Te-132 vapours  0.6 5.4.10-08 0.3 4.5.10-08 2.4.10-08 1.2.10-08 7.6.10-09 5.1.10-09 
Te-133 vapours  0.6 5.5.10-10 0.3 4.7.10-10 2.5.10-10 1.2.10-10 8.1.10-11 5.6.10-11 
Te-133m  vapours  0.6 2.3.10-09 0.3 2.0.10-09 1.1.10-09 5.0.10-10 3.3.10-10 2.2.10-10 
Te-134 vapours  0.6 6.8.10-10 0.3 5.5.10-10 3.0.10-10 1.6.10-10 1.1.10-10 8.4.10-11 
iodine           
I-120 CH 3I 1.0 2.3.10-09 1.0 1.9.10-09 1.0.10-09 4.8.10-10 3.1.10-10 2.0.10-10 
 I2 1.0 3.0.10-09 1.0 2.4.10-09 1.3.10-09 6.4.10-10 4.3.10-10 3.0.10-10 
I-120m  CH 3I 1.0 1.0.10-09 1.0 8.7.10-10 4.6.10-10 2.2.10-10 1.5.10-10 1.0.10-10 
 I2 1.0 1.5.10-09 1.0 1.2.10-09 6.4.10-10 3.4.10-10 2.3.10-10 1.8.10-10 
I-121 CH 3I 1.0 4.2.10-10 1.0 3.8.10-10 2.2.10-10 1.2.10-10 8.3.10-11 5.6.10-11 
 I2 1.0 5.7.10-10 1.0 5.1.10-10 3.0.10-10 1.7.10-10 1.2.10-10 8.6.10-11 
I-123 CH 3I 1.0 1.6.10-09 1.0 1.4.10-09 7.7.10-10 3.6.10-10 2.4.10-10 1.5.10-10 
 I2 1.0 2.1.10-09 1.0 1.8.10-09 1.0.10-09 4.7.10-10 3.2.10-10 2.1.10-10 
I-124 CH 3I 1.0 8.5.10-08 1.0 8.0.10-08 4.5.10-08 2.2.10-08 1.4.10-08 9.2.10-09 
 I2 1.0 1.1.10-07 1.0 1.0.10-07 5.8.10-08 2.8.10-08 1.8.10-08 1.2.10-08 
I-125 CH 3I 1.0 3.7.10-08 1.0 4.0.10-08 2.9.10-08 2.2.10-08 1.6.10-08 1.1.10-08 
 I2 1.0 4.7.10-08 1.0 5.2.10-08 3.7.10-08 2.8.10-08 2.0.10-08 1.4.10-08 
I-126 CH 3I 1.0 1.5.10-07 1.0 1.5.10-07 9.0.10-08 4.8.10-08 3.2.10-08 2.0.10-08 
 I2 1.0 1.9.10-07 1.0 1.9.10-07 1.1.10-07 6.2.10-08 4.1.10-08 2.6.10-08 
I-128 CH 3I 1.0 1.5.10-10 1.0 1.2.10-10 6.3.10-11 3.0.10-11 1.9.10-11 1.3.10-11 
 I2 1.0 4.2.10-10 1.0 2.8.10-10 1.6.10-10 1.0.10-10 7.5.10-11 6.5.10-11 
I-129 CH 3I 1.0 1.3.10-07 1.0 1.5.10-07 1.2.10-07 1.3.10-07 9.9.10-08 7.4.10-08 
 I2 1.0 1.7.10-07 1.0 2.0.10-07 1.6.10-07 1.7.10-07 1.3.10-07 9.6.10-08 
I-130 CH 3I 1.0 1.5.10-08 1.0 1.3.10-08 7.2.10-09 3.3.10-09 2.2.10-09 1.4.10-09 - 216 - 
 
 Element  
Substance  f1 hinh 
[Sv/Bq]  f1 hinh [Sv/Bq]  
Nuclide  Age < 1 year  ≥ 1 
year  1 year  5 years  10 years  15 years  adult  
 I2 1.0 1.9.10-08 1.0 1.7.10-08 9.2.10-09 4.3.10-09 2.8.10-09 1.9.10-09 
I-131 CH 3I 1.0 1.3.10-07 1.0 1.3.10-07 7.4.10-08 3.7.10-08 2.4.10-08 1.5.10-08 
 I2 1.0 1.7.10-07 1.0 1.6.10-07 9.4.10-08 4.8.10-08 3.1.10-08 2.0.10-08 
I-132 CH 3I 1.0 2.0.10-09 1.0 1.8.10-09 9.5.10-10 4.4.10-10 2.9.10-10 1.9.10-10 
 I2 1.0 2.8.10-09 1.0 2.3.10-09 1.3.10-09 6.4.10-10 4.3.10-10 3.1.10-10 
I-132m  CH 3I 1.0 1.8.10-09 1.0 1.6.10-09 8.3.10-10 3.9.10-10 2.5.10-10 1.6.10-10 
 I2 1.0 2.4.10-09 1.0 2.1.10-09 1.1.10-09 5.6.10-10 3.8.10-10 2.7.10-10 
I-133 CH 3I 1.0 3.5.10-08 1.0 3.2.10-08 1.7.10-08 7.6.10-09 4.9.10-09 3.1.10-09 
 I2 1.0 4.5.10-08 1.0 4.1.10-08 2.1.10-08 9.7.10-09 6.3.10-09 4.0.10-09 
I-134 CH 3I 1.0 5.1.10-10 1.0 4.3.10-10 2.3.10-10 1.1.10-10 7.4.10-11 5.0.10-11 
 I2 1.0 8.7.10-10 1.0 6.9.10-10 3.9.10-10 2.2.10-10 1.6.10-10 1.5.10-10 
I-135 CH 3I 1.0 7.5.10-09 1.0 6.7.10-09 3.5.10-09 1.6.10-09 1.1.10-09 6.8.10-10 
 I2 1.0 9.7.10-09 1.0 8.5.10-09 4.5.10-09 2.1.10-09 1.4.10-09 9.2.10-10 
mercury           
Hg-193 vapours  1.0 4.2.10-09 1.0 3.4.10-09 2.2.10-09 1.6.10-09 1.2.10-09 1.1.10-09 
Hg-193m  vapours  1.0 1.2.10-08 1.0 9.4.10-09 6.1.10-09 4.5.10-09 3.4.10-09 3.1.10-09 
Hg-194 vapours  1.0 9.4.10-08 1.0 8.3.10-08 6.2.10-08 5.0.10-08 4.3.10-08 4.0.10-08 
Hg-195 vapours  1.0 5.3.10-09 1.0 4.3.10-09 2.8.1 0-09 2.1.10-09 1.6.10-09 1.4.10-09 
Hg-195m  vapours  1.0 3.0.10-08 1.0 2.5.10-08 1.6.10-08 1.2.10-08 8.8.10-09 8.2.10-09 
Hg-197 vapours  1.0 1.6.10-08 1.0 1.3.10-08 8.4.10-09 6.3.10-09 4.7.10-09 4.4.10-09 
Hg-197m  vapours  1.0 2.1.10-08 1.0 1.7.10-08 1.1.10-08 8.2.10-09 6.2.10-09 5.8.10-09 
Hg-199m  vapours  1.0 6.5.10-10 1.0 5.3.10-10 3.4.10-10 2.5.10-10 1.9.10-10 1.8.10-10 
Hg-203 vapours  1.0 3.0.10-08 1.0 2.3.10-08 1.5.10-08 1.0.10-08 7.7.10-09 7.0.10-09 
 
Legend:  
 
Conversion factors h inh listed in the table  are used to convert intake of radionuclides to the committed effective 
dose for inhalation of radioactive fumes.  
Conversion factors for a radiation worker and the adult members of the population are the same.An exception is 
the value for sulphur S -35 in t he form SO 2, for a radiation worker h inh = 1.2 x 10-10 Sv/Bq.  - 217 - 
 
 Annex No  4 to Decree No. …/….Sb.  
 
Representative characteristics considered when selecting optimal radiation protection 
alternatives  
 
When selecting the optimal variant in the optimisation proce ss, the following aspects and 
details must be taken into account:  
 
1. The level of the exposure of persons for the purposes of comparing options to reduce 
planned or already received doses to individuals or groups of the population that is 
expressed or charac terised by  
1.1. Breaking down the exposure of all persons in time and space depending on the type 
of source of ionising radiation, both in the workplace and in its vicinity, taking into 
account the results of real -world measurements, if available, or estimates based on 
calculation models.  
1.2. The results of the measurement of personal doses, if they are available for the given 
exposure situation, which includes the average individual dose, the lowest and highest 
personal dose, number of irradiated individuals, the c ollective total dose and the 
distribution of individual doses, i.e. the distribution of individual doses at stipulated 
individual dose intervals.  
1.3. The probability of potential exposure, which is an estimate of the possible frequency 
of occurrence of differe nt levels of potential exposures in case of an emergency 
exposure situation.  
1.4. Initial radiological conditions during the optimisation process, which especially 
include the degree of exposure to natural background radiation or increased exposure 
levels due t o previous activities and accidents.  
2. Dose optimisation limits or reference levels for a given activity, if they are stipulated, 
which serve as the upper limit for the exposure of individuals that are exposed to radiation 
in the given situation, where out o f the possible variants of the radiation protection 
preference should be given to those that ensure that the stipulated dose optimisation limits 
or reference levels are not exceeded during the given activity.  
3. Examples of best practice  
3.1. Examples of best prac tice must be taken into account, if they are available for the 
given activity.  
3.2. For similar activities with a source of ionising radiation, procedures or methods for 
ensuring radiation protection established as best practice must be taken into account.  
4. Tech nical, organisational, and economic aspects  
4.1. When choosing the best economic provision of radiation protection in the relevant 
situation, one can use procedures that weigh the benefits of the implemented radiation 
protection measure, usually expressed as th e avoided collective dose in the form of its 
financial equivalent, against the financial costs of this measure.  
4.2. Consideration of a solution according to the principle of best available technology, 
which means the assessment of the existence and availabilit y of the best and most 
effective technologies in the considered area and the possibility of their use, taking 
account of the costs of their deployment or acquisition, which may be high, but may 
increase radiation protection significantly.  - 218 - 
 
 Annex  5 to Decree  No …/….Sb.  
 
Procedures for performing conservative estimates of irradiation of a representative 
individual  
 
1. Determination of a representative individual and assessment of their exposure must be 
carried out based on information on the source of ionising ra diation, including  
1.1. expected radionuclides released during the calendar year into the environment from 
the workplace and their activities, and  
1.2. dose rates as a result of radiation emitted into the vicinity of the workplace.  
2. The content of radionuclides in co mponents of the environment must be determined by  
2.1. direct measurement, or  
2.2. use of a suitable model for radionuclide propagation in the vicinity of the workplace 
subject to ionising radiation, taking into account long -term knowledge of parameters 
characterisi ng the meteorological or hydrological situation in the vicinity of the 
workplace with the source of ionising radiation.  
3. It is necessary to take into account the possible accumulation of radionuclides with a long 
half-life in the environment during the expe cted period of operation of a workplace with a 
source of ionising radiation.  
4. Data regarding the living habits of the population in residential areas where the highest 
content of radionuclides is measured or calculated in components of the environment 
(here inafter the ‘selected group of people’) must be investigated to the extent of 
information about the location, eating habits and lifestyle, while taking into account 
physiological factors, especially age.Data on individuals with extreme habits must be 
exclu ded from data on the living habits of the selected group of people.The data on the 
living habits of the selected group of people must be applicable over the long term.If it is 
impossible obtain data on the living habits of the local population, information  from the 
appropriate regional or national statistics must be used, and for the amount of air inhaled 
and water ingested, data pursuant to § 70(3).  
5. Based on data on the content of radionuclides in components of the environment and on 
the living habits of t he selected group of people, it is necessary to stipulate the annual 
intake of individual radionuclides via all expected avenues of irradiation for individuals 
from the selected group of people.  
6. To convert the activities of radionuclides taken in to the an nual committed effective dose, 
conversion factors pursuant to Annex  3 to this Decree must be used for the selected group 
of people that guarantee protection of the individual given his or her lifetime exposure 
regardless of the amount of years for which th e individual is exposed to ionising 
radiation.The conversion must be performed for the age range:  
6.1. 0 to 5 years by using the conversion factor for an age of 1 year;  
6.2. 6 to 15 years by using the conversion factor for age 10;  
6.3. 16 to 70 years by using the convers ion factor for an adult.  
7. For the selected group of people, the effective dose from external exposure due to 
exposure to radionuclides in components of the environment or irradiation that penetrates 
the shielding of a source of ionising radiation and is dis persed in its vicinity.The total 
effective dose per calendar year for individuals from the selected group of people is the 
sum of the annual committed effective dose from the intake of radionuclides and the 
effective dose from external radiation.  
8. The indiv idual with the highest effective dose for the calendar year from the selected 
group of people specified pursuant to points  1 to 7 is the representative person.When 
comparing the annual doses of an authorised representative person with the authorised - 219 - 
 
 limit,  it is necessary to use the actual types of radionuclides and their activity released in 
the relevant calendar year into the environment from the workplace containing a source of 
ionising radiation or as dose rates due to radiation dispersing into the vici nity of the 
workplace.If the annual doses of the representative person are determined using a 
radionuclide dispersal model, the data on the meteorological or hydrological situation in 
the relevant calendar year must be used.  - 220 - 
 
 Annex  6 to Decree No …/….Sb.  
 
The contents of an optimisation study for stipulating the authorised exposure limit for a 
representative person  
 
An optimisation study for stipulating the authorised exposure limit for a representative person 
must:  
1. stipulate the representative person and es timate his or her exposure using the procedure 
pursuant to Annex  5 to this Decree;  
2. list circumstances affecting exposure of the representative person that are related to the 
amount of radioactive substances and ionising radiation released into the environm ent and 
conditions of their dispersal in the vicinity of a workplace containing a source of ionising 
radiation;  
3. include a document certifying that radionuclides released during the calendar year into the 
environment from the workplace containing a source o f ionising radiation dispersing into 
the vicinity of the workplace correspond to the planned exposure situation resulting from 
the expected operation of this workplace; this document must take into account available 
technical and organisational measures to  reduce the amount of radioactive substances or 
ionising radiation released into the environment;  
4. contain the expected profile of radionuclide release into the environment during the 
calendar year, including consideration of the possibility of releasing th e entire activity of 
some radionuclide during a short period of time all at once; and  
5. contain a justified choice of conditions for radionuclide dispersal in the atmosphere or 
hydrosphere that will be used to stipulate the proposed values of the authorised limit 
taking into the expected radionuclide release profile pursuant to point  4. 
 
Legend:  
 
In choosing parameters pursuant to points 3 to 5, an approach must be used that is  
1. deterministic, which must use a justified conservative approach to select the set of parameters leading to the 
highest authorised limit value, or  
2. probabilistic, wherein  
a. the scope of parameters must be taken into account, and  
b. the resulting probability that the representative person will be exposed to a degree exceeding the 
proposed autho rised limit is at most 5  %. - 221 - 
 
 Annex  7 to Decree No …/….Sb.  
 
Exemption and clearance levels  
 
Specific activity exemption levels and clearance levels for any amount and type of solid 
radioactive substance  
 
 
Nuclide  Specific 
activity  
[kBq/kg]  
H-3 100 
Be-7 10 
C-14 1 
F-18 10 
Na-22 0.1 
Na-24 1 
Si-31 1000  
P-32 1000  
P-33 1000  
S-35 100 
Cl-36 1 
Cl-38 10 
K-42 100 
K-43 10 
K-40 10 
Ca-45 100 
Ca-47 10 
Sc-46 0.1 
Sc-47 100 
Sc-48 1 
V-48 1 
Cr-51 100 
Mn-51 10 
Mn-52 1 
Mn-52m 10 
Mn-53 100 
Mn-54 0.1 
Mn-56 10 
Fe-52* 10 
Fe-55 1000  
Fe-59 1 Nuclide  Specific 
activity  
[kBq/kg]  
Co-55 10 
Co-56 0.1 
Co-57 1 
Co-58 1 
Co-58m 10000  
Co-60 0.1 
Co-60m 1000  
Co-61 100 
Co-62m 10 
Ni-59 100 
Ni-63 100 
Ni-65 10 
Cu-64 100 
Zn-65 0.1 
Zn-69 1000  
Zn-69m*  10 
Ga-72 10 
Ge-71 10000  
As-73 1000  
As-74 10 
As-76 10 
As-77 1000  
Se-75 1 
Br-82 1 
Rb-86 100 
Sr-85 1 
Sr-85m 100 
Sr-87m 100 
Sr-89 1000  
Sr-90* 1 
Sr-91* 10 Nuclide  Specific 
activity  
[kBq/kg]  
Sr-92 10 
Y-90 1000  
Y-91 100 
Y-91m 100 
Y-92 100 
Y-93 100 
Zr-93 10 
Zr-95* 1 
Zr-97* 10 
Nb-93m 10 
Nb-94 0.1 
Nb-95 1 
Nb-97* 10 
Nb-98 10 
Mo-90 10 
Mo-93 10 
Mo-99* 10 
Mo-101*  10 
Tc-96 1 
Tc-96m 1000  
Tc-97 10 
Tc-97m 100 
Tc-99 1 
Tc-99m 100 
Ru-97 10 
Ru-103*  1 
Ru-105*  10 
Ru-106*  0.1 
Rh-103m  10000  
Rh-105 100 
Pd-103*  1000  - 222 - 
 
 Nuclide  Specific 
activity  
[kBq/kg]  
Pd-109*  100 
Ag-105 1 
Ag-110m*  0.1 
Ag-111 100 
Cd-109*  1 
Cd-115*  10 
Cd-115m*  100 
In-111 10 
In-113m  100 
In-114m*  10 
In-115m  100 
Sn-113*  1 
Sn-125 10 
Sb-122 10 
Sb-124 1 
Sb-125*  0.1 
Te-123m  1 
Te-125m  1000  
Te-127 1000  
Te-127m*  10 
Te-129 100 
Te-129m*  10 
Te-131 100 
Te-131m*  10 
Te-132*  1 
Te-133 10 
Te-133m  10 
Te-134 10 
I-123 100 
I-125 100 
I-126 10 
I-129 0.01 
I-130 10 
I-131 10 
I-132 10 
I-133 10 Nuclide  Specific 
activity  
[kBq/kg]  
I-134 10 
I-135 10 
Cs-129 10 
Cs-131 1000  
Cs-132 10 
Cs-134 0.1 
Cs-134m  1000  
Cs-135 100 
Cs-136 1 
Cs-137*  0.1 
Cs-138 10 
Ba-131 10 
Ba-140 1 
La-140 1 
Ce-139 1 
Ce-141 100 
Ce-143 10 
Ce-144*  10 
Pr-142 100 
Pr-143 1000  
Nd-147 100 
Nd-149 100 
Pm-147 1000  
Pm-149 1000  
Sm-151 1000  
Sm-153 100 
Eu-152 0.1 
Eu-152m  100 
Eu-154 0.1 
Eu-155 1 
Gd-153 10 
Gd-159 100 
Tb-160 1 
Dy-165 1000  
Dy-166 100 
Ho-166 100 Nuclide  Specific 
activity  
[kBq/kg]  
Er-169 1000  
Er-171 100 
Tm-170 100 
Tm-171 1000  
Yb-175 100 
Lu-177 100 
Hf-181 1 
Ta-182 0.1 
W-181 10 
W-185 1000  
W-187 10 
Re-186 1000  
Re-188 100 
Os-185 1 
Os-191 100 
Os-191m  1000  
Os-193 100 
Ir-190 1 
Ir-192 1 
Ir-194 100 
Pt-191 10 
Pt-193m  1000  
Pt-197 1000  
Pt-197m  100 
Au-198 10 
Au-199 100 
Hg-197 100 
Hg-197m  100 
Hg-203 10 
Tl-200 10 
Tl-201 100 
Tl-202 10 
Tl-204 1 
Pb-203 10 
Bi-206 1 
Bi-207 0.1 - 223 - 
 
 Nuclide  Specific 
activity  
[kBq/kg]  
Po-203 10 
Po-205 10 
Po-207 10 
At-211 1000  
Ra-225 10 
Ra-227 100 
Th-226 1000  
Th-229 0.1 
Th-232 1 
Pa-230 10 
Pa-233 10 
U-230 10 
U-231 100 
U-232*  0.1 
U-233 1 
U-236 10 
U-237 100 
U-238 1 
U-239 100 
U-240*  100 
Np-237*  1 
Np-239 100 
Np-240 10 
Pu-234 100 
Pu-235 100 
Pu-236 1 
Pu-237 100 
Pu-238 0.1 
Pu-239 0.1 
Pu-240 0.1 
Pu-241 10 
Pu-242 0.1 
Pu-243 1000  
Pu-244*  0.1 
Am-241 0.1 
Am-242 1000  Nuclide  Specific 
activity  
[kBq/kg]  
Am-242m*  0.1 
Am-243*  0.1 
Cm-242 10 
Cm-243 1 
Cm-244 1 
Cm-245 0.1 
Cm-246 0.1 
Cm-247*  0.1 
Cm-248 0.1 
Bk-249 100 
Cf-246 1000  
Cf-248 1 
Cf-249 0.1 
Cf-250 1 
Cf-251 0.1 
Cf-252 1 
Cf-253 100 
Cf-254 1 
Es-253 100 
Es-254*  0.1 
Es-254m*  10 
Fm-254 10000  
Fm-255 100 
 - 224 - 
 
 Legend:  
 
Specific activity values for nuclides marked with * (parent nuclides) also include their decay by -products 
(daughter nuclides) with which they  are in radioactive equilibrium.  
Daughter nuclides that are in radioactive equilibrium with their parent nuclide are not assessed independently.  - 225 - 
 
 Parent and corresponding daughter nuclides in radioactive equilibrium  
 
Parent nuclide  Daughter nuclides  
Fe-52 Mn-52m 
Zn-69m Zn-69 
Sr-90 Y-90 
Sr-91 Y-91m 
Zr-95 Nb-95 
Zr-97 Nb-97m, Nb -97 
Nb-97 Nb-97m 
Mo-99 Tc-99m 
Mo-101 Tc-101 
Ru-103 Rh-103m  
Ru-105 Rh-105m  
Ru-106 Rh-106 
Pd-103 Rh-103m  
Pd-109 Ag-109m  
Ag-110m  Ag-110 
Cd-109 Ag-109m  
Cd-115 In-115m  
Cd-115m In-115m  
In-114m  In-114 
Sn-113 In-113m  
Sb-125 Te-125m  
Te-127m  Te-127 
Te-129m  Te-129 
Te-131m  Te-131 
Te132  I-132 
Cs-137 Ba-137m  
Ce-144 Pr-144, Pr -144m  
U-232 Th-228, Ra -224, Rn -220, Po -216, Pb -212, Bi -212, Tl -208 
U-240 Np-240m, Np -240 
Np-237 Pa-233 
Pu-244 U-240, Np -240m, Np -240 
Am-242m  Np-238 
Am-243 Np-239 
Cm-247 Pu-243 
Es-254 Bk-250 
Es-254m  Fm-254 - 226 - 
 
 Specific activity exemption levels for a small amount of radioactive substance and 
activity exemption levels  
 
 
Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
H-3 106 109 
Be-7 103 107 
Be-10 104 106 
C-11 10 106 
C-14 104 107 
N-13 102 109 
Ne-19 102 109 
O-15 102 109 
F-18 10 106 
Na-22 10 106 
Na-24 10 105 
Mg-28 10 105 
Al-26 10 105 
Si-31 103 106 
Si-32 103 106 
P-32 103 105 
P-33 105 108 
S-35 105 108 
Cl-36 104 106 
Cl-38 10 105 
Cl-39 10 105 
Ar-37 106 108 
Ar-39 107 104 
Ar-41 102 109 
K-40 102 106 
K-42 102 106 
K-43 10 106 
K-44 10 105 
K-45 10 105 
Ca-41 105 107 
Ca-45 104 107 
Ca-47 10 106 
Sc-43 10 106 
Sc-44 10 105 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Sc-45 102 107 
Sc-46 10 106 
Sc-47 102 106 
Sc-48 10 105 
Sc-49 103 105 
Ti-44 10 105 
Ti-45 10 106 
V-47 10 105 
V-48 10 105 
V-49 104 107 
Cr-48 102 106 
Cr-49 10 106 
Cr-51 103 107 
Mn-51 10 105 
Mn-52 10 105 
Mn-52m 10 105 
Mn-53 104 109 
Mn-54 10 106 
Mn-56 10 105 
Fe-52 10 106 
Fe-55 104 106 
Fe-59 10 106 
Fe-60 102 105 
Co-55 10 106 
Co-56 10 105 
Co-57 102 106 
Co-58 10 106 
Co-58m 104 107 
Co-60 10 105 
Co-60m 103 106 
Co-61 102 106 
Co-62m 10 105 
Ni-56 10 106 
Ni-57 10 106 - 227 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Ni-59 104 108 
Ni-63 105 108 
Ni-65 10 106 
Ni-66 104 107 
Cu-60 10 105 
Cu-61 10 106 
Cu-64 102 106 
Cu-67 102 106 
Zn-62 102 106 
Zn-63 10 105 
Zn-65 10 106 
Zn-69 104 106 
Zn-69m 102 106 
Zn-71m 10 106 
Zn-72 102 106 
Ga-65 10 105 
Ga-66 10 105 
Ga-67 102 106 
Ga-68 10 105 
Ga-70 102 106 
Ga-72 10 105 
Ga-73 102 106 
Ge-66 10 106 
Ge-67 10 105 
Ge-68* 10 105 
Ge-69 10 106 
Ge-71 104 108 
Ge-75 103 106 
Ge-77 10 105 
Ge-78 102 106 
As-69 10 105 
As-70 10 105 
As-71 10 106 
As-72 10 105 
As-73 103 107 
As-74 10 106 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
As-76 102 105 
As-77 103 106 
As-78 10 105 
Se-70 10 106 
Se-73 10 106 
Se-73m 102 106 
Se-75 102 106 
Se-79 104 107 
Se-81 103 106 
Se-81m 103 107 
Se-83 10 105 
Br-74 10 105 
Br-74m 10 105 
Br-75 10 106 
Br-76 10 105 
Br-77 102 106 
Br-80 102 105 
Br-80m 103 107 
Br-82 10 106 
Br-83 103 106 
Br-84 10 105 
Kr-74 102 109 
Kr-76 102 109 
Kr-77 102 109 
Kr-79 103 105 
Kr-81 104 107 
Kr-81m 103 1010 
Kr-83m 105 1012 
Kr-85 105 104 
Kr-85m 103 1010 
Kr-87 102 109 
Kr-88 102 109 
Rb-79 10 105 
Rb-81 10 106 
Rb-81m 103 107 
Rb-82m 10 106 - 228 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Rb-83* 102 106 
Rb-84 10 106 
Rb-86 102 105 
Rb-87 103 107 
Rb-88 102 105 
Rb-89 102 105 
Sr-80 103 107 
Sr-81 10 105 
Sr-82* 10 105 
Sr-83 10 106 
Sr-85 102 106 
Sr-85m 102 107 
Sr-87m 102 106 
Sr-89 103 106 
Sr-90* 102 104 
Sr-91 10 105 
Sr-92 10 106 
Y-86 10 105 
Y-86m 102 107 
Y-87* 10 106 
Y-88 10 106 
Y-90 103 105 
Y-90m 10 106 
Y-91 103 106 
Y-91m 102 106 
Y-92 102 105 
Y-93 102 105 
Y-94 10 105 
Y-95 10 105 
Zr-86 102 107 
Zr-88 102 106 
Zr-89 10 106 
Zr-93* 103 107 
Zr-95 10 106 
Zr-97* 10 105 
Nb-88 10 105 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Nb-89 10 105 
Nb-89m 10 105 
Nb-90 10 105 
Nb-93m 104 107 
Nb-94 10 106 
Nb-95 10 106 
Nb-95m 102 107 
Nb-96 10 105 
Nb-97 10 106 
Nb-98 10 105 
Mo-90 10 106 
Mo-93 103 108 
Mo-93m 10 106 
Mo-99 102 106 
Mo-101 10 106 
Tc-93 10 106 
Tc-93m 10 106 
Tc-94 10 106 
Tc-94m 10 105 
Tc-95 10 106 
Tc-95m 10 106 
Tc-96 10 106 
Tc-96m 103 107 
Tc-97 103 108 
Tc-97m 103 107 
Tc-98 10 106 
Tc-99 104 107 
Tc-99m 102 107 
Tc-101 102 106 
Tc-104 10 105 
Ru-94 102 106 
Ru-97 102 107 
Ru-103 102 106 
Ru-105 10 106 
Ru-106*  102 105 
Rh-99 10 106 - 229 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Rh-99m 10 106 
Rh-100 10 106 
Rh-101 102 107 
Rh-101m  102 107 
Rh-102 10 106 
Rh-102m  102 106 
Rh-103m  104 108 
Rh-105 102 107 
Rh-106m  10 105 
Rh-107 102 106 
Pd-100 102 107 
Pd-101 102 106 
Pd-103 103 108 
Pd-107 105 108 
Pd-109 103 106 
Ag-102 10 105 
Ag-103 10 106 
Ag-104 10 106 
Ag-104m  10 106 
Ag-105 102 106 
Ag-106 10 106 
Ag-106m  10 106 
Ag-108m*  10 106 
Ag-110m  10 106 
Ag-111 103 106 
Ag-112 10 105 
Ag-115 10 105 
Cd-104 102 107 
Cd-107 103 107 
Cd-109 104 106 
Cd-113 103 106 
Cd-113m  103 106 
Cd-115 102 106 
Cd-115m  103 106 
Cd-117 10 106 
Cd-117m  10 106 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
In-109 10 106 
In-110 10 106 
In-110m  10 105 
In-111 102 106 
In-112 102 106 
In-113m  102 106 
In-114 103 105 
In-114m  102 106 
In-115 103 105 
In-115m  102 106 
In-116m  10 105 
In-117 10 106 
In-117m  102 106 
In-119m  102 105 
Sn-110 102 107 
Sn-111 102 106 
Sn-113 103 107 
Sn-117m  102 106 
Sn-119m  103 107 
Sn-121 105 107 
Sn-121m*  103 107 
Sn-123 103 106 
Sn-123m  102 106 
Sn-125 102 105 
Sn-126*  10 105 
Sn-127 10 106 
Sn-128 10 106 
Sb-115 10 106 
Sb-116 10 106 
Sb-116m  10 105 
Sb-117 102 107 
Sb-118m  10 106 
Sb-119 103 107 
Sb-120 102 106 
Sb-120m  10 106 
Sb-122 102 104 - 230 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Sb-124 10 106 
Sb-124m  102 106 
Sb-125 102 106 
Sb-126 10 105 
Sb-126m  10 105 
Sb-127 10 106 
Sb-128 10 105 
Sb-128m  10 105 
Sb-129 10 106 
Sb-130 10 105 
Sb-131 10 106 
Te-116 102 107 
Te-121 10 106 
Te-121m  102 106 
Te-123 103 106 
Te-123m  102 107 
Te-125m  103 107 
Te-127 103 106 
Te-127m  103 107 
Te-129 102 106 
Te-129m  103 106 
Te-131 102 105 
Te-131m  10 106 
Te-132 102 107 
Te-133 10 105 
Te-133m  10 105 
Te-134 10 106 
I-120 10 105 
I-120m  10 105 
I-121 102 106 
I-123 102 107 
I-124 10 106 
I-125 103 106 
I-126 102 106 
I-128 102 105 
I-129 102 105 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
I-130 10 106 
I-131 102 106 
I-132 10 105 
I-132m  102 106 
I-133 10 106 
I-134 10 105 
I-135 10 106 
Xe-120 102 109 
Xe-121 102 109 
Xe-122*  102 109 
Xe-123 102 109 
Xe-125 103 109 
Xe-127 103 105 
Xe-129m  103 104 
Xe-131m  104 104 
Xe-133m  103 104 
Xe-133 103 104 
Xe-135 103 1010 
Xe-135m  102 109 
Xe-138 102 109 
Cs-125 10 104 
Cs-127 102 105 
Cs-129 102 105 
Cs-130 102 106 
Cs-131 103 106 
Cs-132 10 105 
Cs-134m  103 105 
Cs-134 10 104 
Cs-135 104 107 
Cs-135m  10 106 
Cs-136 10 105 
Cs-137*  10 104 
Cs-138 10 104 
Ba-126 102 107 
Ba-128 102 107 
Ba-131 102 106 - 231 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Ba-131m  102 107 
Ba-133 102 106 
Ba-133m  102 106 
Ba-135m  102 106 
Ba-137m  10 106 
Ba-139 102 105 
Ba-140*  10 105 
Ba-141 102 105 
Ba-142 102 106 
La-131 10 106 
La-132 10 106 
La-135 103 107 
La-137 103 107 
La-138 10 106 
La-140 10 105 
La-141 102 105 
La-142 10 105 
La-143 102 105 
Ce-134*  103 107 
Ce-135 10 106 
Ce-137 103 107 
Ce-137m  103 106 
Ce-139 102 106 
Ce-141 102 107 
Ce-143 102 106 
Ce-144*  102 105 
Pr-136 10 105 
Pr-137 102 106 
Pr-138m  10 106 
Pr-139 102 107 
Pr-142 102 105 
Pr-142m 107 109 
Pr-143 104 106 
Pr-144 102 105 
Pr-145 103 105 
Pr-147 10 105 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Nd-136 102 106 
Nd-138 103 107 
Nd-139 102 106 
Nd-139m  10 106 
Nd-141 102 107 
Nd-147 102 106 
Nd-149 102 106 
Nd-151 10 105 
Pm-141 10 105 
Pm-143 102 106 
Pm-144 10 106 
Pm-145 103 107 
Pm-146 10 106 
Pm-147 104 107 
Pm-148 10 105 
Pm-148m  10 106 
Pm-149 103 106 
Pm-150 10 105 
Pm-151 102 106 
Sm-141 10 105 
Sm-141m  10 106 
Sm-142 102 107 
Sm-145 102 107 
Sm-146 10 105 
Sm-147 10 104 
Sm-151 104 108 
Sm-153 102 106 
Sm-155 102 106 
Sm-156 102 106 
Eu-145 10 106 
Eu-146 10 106 
Eu-147 102 106 
Eu-148 10 106 
Eu-149 102 107 
Eu-150 10 106 
Eu-150m  103 106 - 232 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Eu-152 10 106 
Eu-152m  102 106 
Eu-154 10 106 
Eu-155 102 107 
Eu-156 10 106 
Eu-157 102 106 
Eu-158 10 105 
Gd-145 10 105 
Gd-146* 10 106 
Gd-147 10 106 
Gd-148 10 104 
Gd-149 102 106 
Gd-151 102 107 
Gd-152 10 104 
Gd-153 102 107 
Gd-159 103 106 
Tb-147 10 106 
Tb-149 10 106 
Tb-150 10 106 
Tb-151 10 106 
Tb-153 102 107 
Tb-154 10 106 
Tb-155 102 107 
Tb-156 10 106 
Tb-156m (24,4 h) 103 107 
Tb-156m' (5 h)  104 107 
Tb-157 104 107 
Tb-158 10 106 
Tb-160 10 106 
Tb-161 103 106 
Dy-155 10 106 
Dy-157 102 106 
Dy-159 103 107 
Dy-165 103 106 
Dy-166 103 106 
Ho-155 102 106 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Ho-157 102 106 
Ho-159 102 106 
Ho-161 102 107 
Ho-162 102 107 
Ho-162m  10 106 
Ho-164 103 106 
Ho-164m  103 107 
Ho-166 103 105 
Ho-166m  10 106 
Ho-167 102 106 
Er-161 10 106 
Er-165 103 107 
Er-169 104 107 
Er-171 102 106 
Er-172 102 106 
Tm-162 10 106 
Tm-166 10 106 
Tm-167 102 106 
Tm-170 103 106 
Tm-171 104 108 
Tm-172 102 106 
Tm-173 102 106 
Tm-175 10 106 
Yb-162 102 107 
Yb-166 102 107 
Yb-167 102 106 
Yb-169 102 107 
Yb-175 103 107 
Yb-177 102 106 
Yb-178 103 106 
Lu-169 10 106 
Lu-170 10 106 
Lu-171 10 106 
Lu-172 10 106 
Lu-173 102 107 
Lu-174 102 107 - 233 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Lu-174m 102 107 
Lu-176 102 106 
Lu-176m  103 106 
Lu-177 103 107 
Lu-177m  10 106 
Lu-178 102 105 
Lu-178m  10 105 
Lu-179 103 106 
Hf-170 102 106 
Hf-172*  10 106 
Hf-173 102 106 
Hf-175 102 106 
Hf-177m  10 105 
Hf-178m  10 106 
Hf-179m  10 106 
Hf-180m  10 106 
Hf-181 10 106 
Hf-182 102 106 
Hf-182m  10 106 
Hf-183 10 106 
Hf-184 102 106 
Ta-172 10 106 
Ta-173 10 106 
Ta-174 10 106 
Ta-175 10 106 
Ta-176 10 106 
Ta-177 102 107 
Ta-178 10 106 
Ta-179 103 107 
Ta-180 10 106 
Ta-180m  103 107 
Ta-182 10 104 
Ta-182m  102 106 
Ta-183 102 106 
Ta-184 10 106 
Ta-185 102 105 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Ta-186 10 105 
W-176 102 106 
W-177 10 106 
W-178*  10 106 
W-179 102 107 
W-181 103 107 
W-185 104 107 
W-187 102 106 
W-188*  102 105 
Re-177 10 106 
Re-178 10 106 
Re-181 10 106 
Re-182 10 106 
Re-182m  10 106 
Re-184 10 106 
Re-184m  102 106 
Re-186 103 106 
Re-186m  103 107 
Re-187 106 109 
Re-188 102 105 
Re-188m  102 107 
Re-189*  102 106 
Os-180 102 107 
Os-181 10 106 
Os-182 102 106 
Os-185 10 106 
Os-189m  104 107 
Os-191 102 107 
Os-191m  103 107 
Os-193 102 106 
Os-194 102 105 
Ir-182 10 105 
Ir-184 10 106 
Ir-185 10 106 
Ir-186 10 106 
Ir-186m  10 106 - 234 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Ir-187 102 106 
Ir-188 10 106 
Ir-189*  102 107 
Ir-190 10 106 
Ir-190m (3,1 h)  10 106 
Ir-190m' (1,2 h)  104 107 
Ir-192 10 104 
Ir-192m  102 107 
Ir-193m  104 107 
Ir-194 102 105 
Ir-194m  10 106 
Ir-195 102 106 
Ir-195m  102 106 
Pt-186 10 106 
Pt-188*  10 106 
Pt-189 102 106 
Pt-191 102 106 
Pt-193 104 107 
Pt-193m  103 107 
Pt-195m  102 106 
Pt-197 103 106 
Pt-197m  102 106 
Pt-199 102 106 
Pt-200 102 106 
Au-193 102 107 
Au-194 10 106 
Au-195 102 107 
Au-198 102 106 
Au-198m  10 106 
Au-199 102 106 
Au-200 102 105 
Au-200m  10 106 
Au-201 102 106 
Hg-193 102 106 
Hg-193m  10 106 
Hg-194*  10 106 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Hg-195 102 106 
Hg-195m*  102 106 
Hg-197 102 107 
Hg-197m  102 106 
Hg-199m 102 106 
Hg-203 102 105 
Tl-194 10 106 
Tl-194m  10 106 
Tl-195 10 106 
Tl-197 102 106 
Tl-198 10 106 
Tl-198m  10 106 
Tl-199 102 106 
Tl-200 10 106 
Tl-201 102 106 
Tl-202 102 106 
Tl-204 104 104 
Pb-195m  10 106 
Pb-198 102 106 
Pb-199 10 106 
Pb-200 102 106 
Pb-201 10 106 
Pb-202 103 106 
Pb-202m  10 106 
Pb-203 102 106 
Pb-205 104 107 
Pb-209 105 106 
Pb-210*  10 104 
Pb-211 102 106 
Pb-212*  10 105 
Pb-214 102 106 
Bi-200 10 106 
Bi-201 10 106 
Bi-202 10 106 
Bi-203 10 106 
Bi-205 10 106 - 235 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Bi-206 10 105 
Bi-207 10 106 
Bi-210 103 106 
Bi-210m*  10 105 
Bi-212*  10 105 
Bi-213 102 106 
Bi-214 10 105 
Po-203 10 106 
Po-205 10 106 
Po-206 10 106 
Po-207 10 106 
Po-208 10 104 
Po-209 10 104 
Po-210 10 104 
At-207 10 106 
At-211 103 107 
Fr-222 103 105 
Fr-223 102 106 
Rn-220*  104 107 
Rn-222*  10 108 
Ra-223*  102 105 
Ra-224*  10 105 
Ra-225 102 105 
Ra-226*  10 104 
Ra-227 102 106 
Ra-228*  10 105 
Ac-224 102 106 
Ac-225*  10 104 
Ac-226 102 105 
Ac-227*  0.1 103 
Ac-228 10 106 
Th-226*  103 107 
Th-227 10 104 
Th-228* 1 104 
Th-229*  1 103 
Th-230 1 104 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Th-231 103 107 
Th-232 10 104 
Thpřír 1 103 
Th-234*  103 105 
Pa-227 10 106 
Pa-228 10 106 
Pa-230 10 106 
Pa-231 1 103 
Pa-232 10 106 
Pa-233 102 107 
Pa-234 10 106 
U-230*  10 105 
U-231 102 107 
U-232*  1 103 
U-233 10 104 
U-234 10 104 
U-235*  10 104 
U-236 10 104 
U-237 102 106 
U-238*  10 104 
Upřír* 1 103 
U-239 102 106 
U-240 103 107 
U-240*  10 106 
Np-232 10 106 
Np-233 102 107 
Np-234 10 106 
Np-235 103 107 
Np-236 102 105 
Np-236m  103 107 
Np-237*  1 103 
Np-238 102 106 
Np-239 102 107 
Np-240 10 106 
Pu-234 102 107 
Pu-235 102 107 - 236 - 
 
 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Pu-236 10 104 
Pu-237 103 107 
Pu-238 1 104 
Pu-239 1 104 
Pu-240 1 103 
Pu-241 102 105 
Pu-242 1 104 
Pu-243 103 107 
Pu-244 1 104 
Pu-245 102 106 
Pu-246 102 106 
Am-237 102 106 
Am-238 10 106 
Am-239 102 106 
Am-240 10 106 
Am-241 1 104 
Am-242 103 106 
Am-242m*  1 104 
Am-243*  1 103 
Am-244 10 106 
Am-244m  104 107 
Am-245 103 106 
Am-246 10 105 
Am-246m  10 106 
Cm-238 102 107 
Cm-240 102 105 
Cm-241 102 106 
Cm-242 102 105 
Cm-243 1 104 
Cm-244 10 104 
Cm-245 1 103 
Cm-246 1 103 
Cm-247 1 104 
Cm-248 1 103 
Cm-249 103 106 
Cm-250 0.1 103 Nuclide  Specific 
activity  
[kBq/ kg] Activity  
[Bq]  
Bk-245 102 106 
Bk-246 10 106 
Bk-247 1 104 
Bk-249 103 106 
Bk-250 10 106 
Cf-244 104 107 
Cf-246 103 106 
Cf-248 10 104 
Cf-249 1 103 
Cf-250 10 104 
Cf-251 1 103 
Cf-252 10 104 
Cf-253 102 105 
Cf-254 1 103 
Es-250 102 106 
Es-251 102 107 
Es-253 102 105 
Es-254 10 104 
Es-254m  102 106 
Fm-252 103 106 
Fm-253 102 106 
Fm-254 104 107 
Fm-255 103 106 
Fm-257 10 105 
Md-257 102 107 
Md-258 102 105 
 - 237 - 
 
Legend:  
 
A small amount of radioactive substance is considered to be an  amount less than 1  tonne.  
Specific activity and activity values for nuclides marked with * (parent nuclides) also include their decay by -
products (daughter nuclides) with which they are in radioactive equilibrium.  
Daughter nuclides that are in radioactive  equilibrium with their parent nuclide are not assessed independently.  - 238 - 
 
 Parent nuclides and corresponding daughter nuclides in radioactive equilibrium  
 
Parent nuclide  Daughter nuclides  
Ge-68 Ga-68 
Rb-83 Kr-83m 
Sr-82 Rb-82 
Sr-90 Y-90 
Y-87 Sr-87m 
Zr-93 Nb-93m 
Zr-97 Nb-97 
Ru-106 Rh-106 
Ag-108m  Ag-108 
Sn-121m  Sn-121 (0.776)  
Sn-126 Sb-126m  
Xe-122 I-122 
Cs-137 Ba-137m  
Ba-140 La-140 
Ce-134 La-134 
Ce-144 Pr-144 
Gd-146 Eu-146 
Hf-172 Lu-172 
W-178 Ta-178 
W-188 Re-188 
Re-189 Os-189m (0.241)  
Ir-189 Os-189m  
Pt-188 Ir-188 
Hg-194 Au-194 
Hg-195m  Hg-195 (0.542)  
Pb-210 Bi-210, Po -210 
Pb-212 Bi-212, Tl -208 (0.36), Po -212 (0.64)  
Bi-210m  Tl-206 
Bi-212 Tl-208 (0.36), Po -212 (0.64)  
Rn-220 Po-216 
Rn-222 Po-218, Pb -214, Bi -214, Po -214 
Ra-223 Rn-219, Po -215, Pb -211, Bi -211, Tl -207 
Ra-224 Rn-220, Po -216, Pb -212, Bi -212, Tl -208 (0.36), Po -212 (0.64)  
Ra-226 Rn-222, Po -218, Pb -214, Bi -214, Po -214, Pb -210, Bi -210, Po -210 
Ra-228 Ac-228 
Ac-225 Fr-221, At -217, Bi -213, Po -213 (0.978), Tl -209 (0.0216), Pb -209 ( 0.978)  - 239 - 
 
 Parent nuclide  Daughter nuclides  
Ac-227 Fr-223 (0.0138)  
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-229 Ra-225, Ac -225, Fr -221, At -217, Bi -213, Po -213, Pb -209 
Thpřír Ra-228, Ac -228, Th -228, Ra -224, Rn -220, Po -216, Pb -212, Bi -212, Tl -208 (0.36), Po -
212 (0.64)  
Th-234 Pa-234m  
U-230 Th-226, Ra -222, Rn -218, Po -214 
U-232 Th-228, Ra -224, Rn -220, Po -216, Pb -212, Bi -212, Tl -208 (0.36), Po -212 (0.64)  
U-235 Th-231 
U-238 Th-234, Pa -234m  
Upřír Th-234, Pa -234m, U -234, Th -230, Ra -226, Rn -222, Po -218, Pb -214, Bi -214, Po -214, 
Pb-210, Bi -210, Po -210 
U-240 Np-240m  
Np-237 Pa-233 
Am-242m  Am-242 
Am-243 Np-239 
 
CELEX:32013L0059  
 
Surface activity exemption levels for surface co ntamination of items  
 
Radionuclide source type  Surface activity  
[Bq/cm2] 
Radionuclide sources emitting beta or gamma radiation, and low -toxicity 
radionuclide sources emitting alpha radiation  0.4 
Other radionuclide sources emitting alpha radiation  0.04 
 
Legend:  
 
Low-toxic radionuclide sources emitting alpha radiation are as follows:  
1. natural uranium, depleted uranium, natural thorium, Th -228, Th -230, Th -232, U -235, and U -238 is 
contained in ores or chemical concentrates, or  
2. radioactive source emitting alph a radiation with a half -life of less than ten days.  - 240 - 
 
 Annex  8 to Decree No .../….Sb.  
 
Activity levels of highly active sources  
 
Element (atomic number)  Radionuclide  The activity level defining 
the highly active source 
[TBq]  
Americium (95)  Am-241 6. 10-2 
 Am-241/Be -9 (1) 6. 10-2 
Californium (98)  Cf-252 2. 10-2 
Curium (96)  Cm-244 5. 10-2 
Cobalt (27)  Co-60 3. 10-2 
Caesium (55)  Cs-137 1. 10-1 
Gadolinium (64)  Gd-153 1. 100 
Iridium (77)  Ir-192 8. 10-2 
Promethium (61)  Pm-147 4. 101 
Plutonium (94)  Pu-238 6. 10-2 
 Pu-239/Be -9(1) 6. 10-2 
Radium (88)  Ra-226 4. 10-2 
Selenium (34)  Se-75 2. 10-1 
Strontium (38)  Sr-90 (Y -90) 1. 100 
Thulium (69)  Tm-170 2. 101 
Ytterbium (70)  Yb-169 3. 10-1 
 
 
Legend:  
 
(1) Activity is the activity of a radionuclide emitting alph a radiation.  
For radionuclides not listed in the table, the relevant activity is the same as the D -value specified in Annex  1 to 
this Decree.  
CELEX:32013L0059  - 241 - 
 
 Annex  9 to Decree No …/….Sb.  
 
Workplace with an open radionuclide source  
 
Standard equipment requ irements for a workplace with an open radionuclide source for purposes of its 
categorisation  
 
Workplace category  Requirements for standard workplace ventilation, insulation, 
and shading devices and sewer system design  
I. Like a normal chemical laboratory,  walls and ceiling with a 
washable and non -porous surface, floor covered with a durable, 
easy-to-clean floor material, for example PVC, work surfaces 
made of easy -to-clean material, especially laminate or stainless 
steel, solid and seamless, sinks from eas y-to-clean material, can be 
directly connected to the sewer system.  
II. Like a well -equipped chemical laboratory, in addition to the 
requirements for Category  I workplaces, also sealed joints between 
floor, walls, ceiling, and work surfaces, exhaust hood,  drains 
usually connected to a separate retention tank.  
III. Like a very well -equipped chemical laboratory, in addition to 
requirements for a Category  II workplace, also equipped with 
vacuum chambers and drains connected to a separate retention 
tank.  
 
 
The highest activities processed in a workplace with standard equipment  
 
Workplace 
category  Characteristics of substances and methods of working with them  
Normal  Under wet 
conditions  Volatile liquids  Potentially dusty  
Category  I 60 Sv/h inh 3 000 Sv/h inh 1 Sv/h inh 3 Sv/h inh 
Category II  600 Sv/h inh 30 000 Sv/h inh 150 Sv/h inh 600 Sv/h inh 
Category III  8 000 Sv/h inh 300 000 Sv/h inh 1 600 Sv/h inh 8 000 Sv/h inh 
Category  IV unspecified  unspecified  unspecified  unspecified  
 
Legend:  
 
1. For natural uranium and thor ium, depleted and enriched uranium, radionuclides Sm -147, Th -232, U -235, 
and U -238, ten times the values listed in the table will be used.  
2. Conversion factors h inh for intake via inhalation are stipulated in Annex  3 to this Decree.  
3. The characteristics of ma terials and working with them are provided in the table below.  
4. If workplace equipment does not conform to the standard facilities of a workplace of the given category, the 
highest activity that can be processed at such a workplace is determined by multiply ing the appropriate 
activity from the previous table by a workplace availability coefficient according to the table below.  
5. If multiple radionuclides are processed simultaneously at one workplace, the sum of shares of processed 
activities of individual radi onuclides and their maximum processed activities must not be greater than 1.  
6. If work at a Category  III workplace involves only an open radionuclide source fixed on a permanent 
medium, activity restriction does not apply.  
 
 - 242 - 
 
 Characteristics of materials and work with them depending on the physical characteristics of the 
processed materials and on the difficulty and potential risk level of work activities  
 
Characteristics of materials 
and work with them  Physical characteristics of materials processing the diff iculty and 
potential risk level of work activities  
Normal  Work activities with dry solid radioactive materials, especially weighing, 
separation, heating, breeding of laboratory animals with applied 
radionuclides.  
Under wet conditions  Work activities with  radioactive materials in solution, aside from volatile 
liquids.  
Volatile liquids  Work activities with tritiated liquids, marked organic liquids, solutions 
with radioactive iodine, or with other liquids where there is a possibility of 
radioactive fumes or  air contamination.  
Potentially dusty  Work activities with dry solid radioactive materials, where there is the 
possibility of significant quantities of respirable dust, in particular 
grinding, crushing, or milling of substances and pouring of dry dusty 
materials.  
 
 
Workplace equipment coefficients  
 
Workplace equipment  Workplace category  
I. II. III. 
Hermetic vacuum chamber 
with gloves or manipulators  10 10 1 
Semi -hermetic vacuum 
chamber  10 1 0.1 
A closed elution or similar 
system, radiochemical fume 
hood, a laminar flow chamber  1 1 0.1 
An open surface or worktable 
in a room with downward 
laminar flow  0.1 0.1 0.01 
A normal chemical fume hood, 
chamber without ventilation, 
especially protective shield, 
tent 0.1 0.01 0.001  
Open area, work table  0.01 0.001 0.0001  - 243 - 
 
 Annex  10 to Decree No …/….Sb.  
 
Procedures for verifying the seal on a sealed radionuclide source  
 
1. The seal on a sealed radionuclide source must be tested by:  
1.1. immersing it in a liquid;  
1.2. wiping the sealed radionuclide source;  
1.3. wiping it on a substit ute surface; or  
1.4. performing an emanation test.  
2. A leak test of a sealed radionuclide source that is part of acceptance testing or long -term 
stability testing of equipment with a sealed radionuclide source performed pursuant to 
§ 28(2)(d)(5) or §  30(1)(c)(5) must be performed by wiping it on a substitute surface.  
3. Unless a different value is recommended, a sealed radionuclide source is considered to 
leak if during the leak test the following limit values for test media activity were 
exceeded:  
3.1. for the liquid imm ersion test, 200  Bq; 
3.2. for a wipe test of a sealed radionuclide source, 200  Bq; 
3.3. for a wipe test on a substitute test surface, 20  Bq; or  
3.4. for an emanation test, 200  Bq over twelve hours.  - 244 - 
 
 Annex  11 to Regulation No …/....Sb.  
 
Frequency of the long -term stability  test for a sealed radionuclide source  
 
Frequency of the long -term stability test for a sealed radionuclide source for which the recommended 
duration of use has not expired  
 
Enclosed radionuclide source type  Conditions of use  
Light *1 Normal *2 Difficult  *3 
Flat sealed radionuclide source emitting alpha radiation  5 years  36 months  12 months  
Flat sealed radionuclide source emitting beta radiation 
with activity greater than 40  MBq/cm2 10 years  5 years  24 months  
Flat sealed radionuclide source emitting be ta radiation 
with activity less than 40  MBq/cm2, and with a thick 
overlay  15 years  10 years  36 months  
Single -layer sealed radioactive source emitting gamma 
radiation with lower activity  15 years  10 years  36 months  
Double -layer sealed radioactive source  15 years  10 years  36 months  
Sealed radionuclide source emitting low -energy photons  10 years  5 years  24 months  
 
Legend:  
 
*1 - Light conditions of use (a non -aggressive environment in an inaccessible area, without risk of physical 
damage, for example survei llance radionuclide dosimetry sources);  
*2 - normal conditions of use (a non -aggressive industrial environment, for example charge eliminators or 
thickness meters in the textile, paper, or plastics industry);  
*3 - difficult conditions of use (an aggressive  environment or an increased risk of physical damage, for example 
rubber factories).  
 
Frequency of the long -term stability test for a sealed radionuclide source for which the recommended 
duration of use has expired  
 
Enclosed radionuclide source type  All co nditions of use  
Single -layer sealed radioactive source  12 months  
Double -layer sealed radioactive source  24 months  - 245 - 
 
 Annex  12 to Decree No …/….Sb.  
 
Categorisation of defects identified during a long -term stability test  
 
1. Defects discovered in a source of io nising radiation used in medical irradiation in 
radiotherapy are as follows:  
1.1. very serious defects, as follows:  
1.1.1.  leakage of the sealed radionuclide source; or  
1.1.2.  a serious defect or a serious combination of defects that could pose a risk to 
patient or worker he alth or that violate the principles of radiation protection in a 
serious manner; or  
1.2. less serious defects, as follows:  
1.2.1.  visible damage to the sealed radionuclide source that could lead to a leak in the 
near future and that is not a very serious defect; or  
1.2.2.  other defects found during a long -term stability test not specified in points  1.1 or 
1.2.1.  
2. Defects discovered in a source of ionising radiation used in medical irradiation in 
radiodiagnostics or interventional radiology are as follows:  
2.1. very serious defects,  as follows:  
2.1.1.  a functional defect or combination of defects that could pose a direct risk to the 
health of the patient;  
2.1.2.  the occurrence of significant artefacts completely precluding diagnostic reading 
of the image;  
2.1.3.  for radiography and skiascopy X -ray device s, the first half -thickness at 80  kV of 
less than 2.3  mm Al;  
2.1.4.  on radiographic X -ray equipment  
2.1.4.1.  a voltage deviation from the nominal value of more than 20  %; 
2.1.4.2.  with a film image receptor without automatic exposure, short -term 
absorbed dose reproducibility durin g identical exposure parameters greater 
than 20  %; 
2.1.4.3.  with a film image receptor, reproducibility of exposure automation greater 
than 40  %; or  
2.1.4.4.  spatial resolution of less than 1.6  lp/mm;  
2.1.5.  for fluoroscopic X -ray devices  
2.1.5.1.  the sum of the deviations of the edges of the X -ray field and image 
receptor on all sides greater than 10  % of the distance from the point of 
focus to the image receptor;  
2.1.5.2.  low contrast detectability greater than 4  %; or  
2.1.5.3.  spatial resolution less than 1.6  lp/mm;  
2.1.6.  on computed tomography devices, a decli ne of the dose index by 70  % or more 
from the baseline value at the same exposure parameters; or  
2.1.7.  a serious defect or a serious combination of defects that could pose a risk to 
patient or worker health or that violate the principles of radiation protection in a 
serious manner; or  
2.2. less serious defects, these being other defects discovered during the long -term 
stability test not mentioned in point  2.1. - 246 - 
 
 3. Defects discovered in a source of ionising radiation used in defectoscopy and well logging 
are as follows:  
3.1. very serious defects, as follows:  
3.1.1.  leakage of the sealed radionuclide source; or  
3.1.2.  a serious defect or a serious combination of defects that could pose a risk to the 
health or workers or other individuals or that violate the principles of radiation 
protection i n a serious manner; or  
3.2. less serious defects, these being other defects discovered during the long -term 
stability test not mentioned in point  3.1. 
4. Defects found in other sources of ionising radiation not mentioned in points  1 to 3 are as 
follows:  
4.1. very serio us defects, as follows:  
4.1.1.  a functional defect or combination of defects that could pose a direct risk to the 
health of workers or other individuals;  
4.1.2.  leakage of the sealed radionuclide source; or  
4.1.3.  a serious defect or a serious combination of defects that could  pose a risk to the 
health or workers or other individuals or that violate the principles of radiation 
protection in a serious manner; or  
4.2. less serious defects, as follows:  
4.2.1.  visible damage to the sealed radionuclide source that could lead to a leak in the 
near future and that is not a very serious defect; or  
4.2.2.  other defects found during a long -term stability test not specified in points  4.1 or 
4.2.1.  
 
Legend:  
 
An artefact is an undesirable presence on an image that is not related to the imaged object, but that impairs its  
Visibility  
CELEX:32013L0059  - 247 - 
 
 Annex  13 to Decree No …/….Sb.  
 
Performance constancy tests  performed by the registrant  
 
The registrant must carry out performance constancy tests  
1. of intra -oral dental x -ray equipment  
1.1. with a film image receptor, via v isual comparison of a dental phantom image taken 
with the exposure parameters commonly used for an adult's upper molar with a 
reference image  
1.1.1.  at least once a month;  
1.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
1.1.3.  upon a change that is important in terms of radiation protection;  
1.1.4.  after more than 1 month of inactivity;  
1.1.5.  after changing films or chemicals;  
1.1.6.  if a deviation is detected during tests carried out within the scope of points  1.1.1 
to 1.1.5; and  
1.1.7.  if a deviation u nder point  1.1.6 is confirmed, after corrective measures, using 
modified exposure parameters resulting from the corrective measures;  
1.2. with direct digitisation  
1.2.1.  via visual comparison of a dental phantom image taken with the exposure 
parameters commonly used f or an adult's upper molar with a reference image  
1.2.1.1.  at least once a year;  
1.2.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
1.2.1.3.  upon a change that is important in terms of radiation protection;  
1.2.1.4.  after more than 1 year of i nactivity;  
1.2.1.5.  if a deviation is detected during tests carried out within the scope of 
points  1.2.1.1 to 1.2.1.4; and  
1.2.1.6.  if a deviation under point  1.2.1.5 is confirmed, after corrective measures, 
using modified exposure parameters resulting from the corrective 
measures;  
1.2.2.  via a visual check of the cleanliness of the monitor used for clinical diagnosis;  
1.2.2.1.  once per month; and  
1.2.2.2.  if monitor contamination is found under point  1.2.2.1, after corrective 
measures;  
1.3. with indirect digitisation  
1.3.1.  via visual comparison of a dental ph antom image taken with the exposure 
parameters commonly used for an adult's upper molar with a reference image  
1.3.1.1.  at least once a year;  
1.3.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
1.3.1.3.  upon a change that is important  in terms of radiation protection;  
1.3.1.4.  after more than 1 year of inactivity;  
1.3.1.5.  if a deviation is detected during tests carried out within the scope of 
points  1.3.1.1 to 1.3.1.4; and  
1.3.1.6.  if a deviation under point  1.3.1.5 is confirmed, after corrective measures, 
using modified exposure parameters resulting from the corrective 
measures;  
1.3.2.  via a visual check of the cleanliness of the monitor used for clinical diagnosis;  - 248 - 
 
 1.3.2.1.  once per month; and  
1.3.2.2.  if monitor contamination is found under point  1.3.2.1, after corrective 
measures;  
1.3.3.  via a visual check whether on dental phantom images taken, all indirect 
digitisation films used do not show significant artefacts affecting the diagnostic 
reading of images;  
1.3.3.1.  once per month; and  
1.3.3.2.  after acquiring new indirect digitisation films;  
2. of panoramic d ental X -ray equipment  
2.1. with direct digitisation  
2.1.1.  with a jaw phantom imaging test performed according to the equipment 
manufacturer's instructions, or if the manufacturer did not provide such 
instructions, according to the instructions of the person who perfo rmed the long -
term stability test or acceptance test  
2.1.1.1.  once every 6 months;  
2.1.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
2.1.1.3.  upon a change that is important in terms of radiation protection;  
2.1.1.4.  after more than 6 months  of inactivity; and  
2.1.1.5.  if shortcomings are found within the scope of points  2.1.1.1 to 2.1.1.4, 
after corrective measures;  
2.1.2.  via a visual check of the cleanliness of the monitor used for clinical diagnosis;  
2.1.2.1.  once per month; and  
2.1.2.2.  if monitor contamination is found under point  2.1.2.1, after corrective 
measures;  
2.2. with a jaw phantom film imaging test performed according to the equipment 
manufacturer's instructions, or if the manufacturer did not provide such instructions, 
according to the instructions of the person who  performed the long -term stability test 
or acceptance test  
2.2.1.  once every 3 months;  
2.2.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
2.2.3.  upon a change that is important in terms of radiation protection;  
2.2.4.  after more than 3 months of inactivity; and  
2.2.5.  if shortcomings are found within the scope of points  2.2.1 to 2.2.4, after 
corrective measures;  
2.3. with indirect digitisation  
2.3.1.  with a jaw phantom imaging test performed according to the equipment 
manufacturer's instructions, or if the  manufacturer did not provide such 
instructions, according to the instructions of the person who performed the long -
term stability test or acceptance test  
2.3.1.1.  once every 3 months;  
2.3.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imagi ng process;  
2.3.1.3.  upon a change that is important in terms of radiation protection;  
2.3.1.4.  after more than 3 months of inactivity; and  
2.3.1.5.  if shortcomings are found within the scope of points  2.3.1.1 to 2.3.1.4, 
after corrective measures;  
2.3.2.  via a visual check of the cleanlin ess of the monitor used for clinical diagnosis;  
2.3.2.1.  once per month; and  - 249 - 
 
 2.3.2.2.  if monitor contamination is found under point  2.3.2.1, after corrective 
measures;  
2.3.3.  via a visual check whether on images taken, all indirect digitisation films used 
do not show significant a rtefacts affecting the diagnostic reading of images;  
2.3.3.1.  once every 3 months; and  
2.3.3.2.  after acquiring new indirect digitisation films;  
3. of dental X -ray equipment for which a negatoscope is used to evaluate images, tests 
pursuant to point  1 or 2 plus a visual check of negatoscope cleanliness;  
3.1. once per month; and  
3.2. if negatoscope contamination is found under point  3.1, after corrective measures;  
4. of dental computed tomography equipment  
4.1. with a jaw phantom imaging test performed according to the equipment 
manufacturer's in structions, or if the manufacturer did not provide such instructions, 
according to the instructions of the person who performed the long -term stability test 
or acceptance test;  
4.1.1.  once every 6 months;  
4.1.2.  upon each suspected malfunction of the ionising radiation source or of the 
imaging process;  
4.1.3.  upon a change that is important in terms of radiation protection;  
4.1.4.  after more than 6 months of inactivity; and  
4.1.5.  if shortcomings are found within the scope of points  4.1.1 to 4.1.4, after 
corrective measures;  
4.2. via a visual che ck of the cleanliness of the monitor used for clinical diagnosis;  
4.2.1.  once per month; and  
4.2.2.  if monitor contamination is found under point  4.2.1, after corrective measures;  
5. of veterinary X -ray equipment  
5.1. by checking the condition and integrity of protective aids  
5.1.1.  once per year,  
5.1.2.  after repairs and  
5.1.3.  after the acquisition of new protective aids,  
5.2. of veterinary radiography equipment via a test of alignment of the light field with the 
X-ray field  
5.2.1.  once every 6 months;  
5.2.2.  upon a change that is important in terms of radiation pro tection; and  
5.2.3.  in the case of unsatisfactory results of tests pursuant to points  5.2.1 and 5.2.2, 
after corrective measures are performed;  
5.3. of veterinary skiascopic equipment via a test of x -ray field alignment with the image 
receptor  
5.3.1.  once every 6 months;  
5.3.2.  upon a change that is important in terms of radiation protection; and  
5.3.3.  in the case of unsatisfactory results of tests pursuant to points  5.3.1 and 5.3.2, 
after corrective measures are performed;  
5.4. of veterinary X -ray equipment not listed in points  5.2 and 5.3 to  the extent and 
frequency stipulated  
5.4.1.  by the manufacturer; or  
5.4.2.  by the person who performed the acceptance test or long -term stability test;  
6. of an X -ray bone densitometer to the extent stipulated by the manufacturer  
6.1. prior to first use;  
6.2. after servicing;  
6.3. with t he frequency as stipulated by the manufacturer; and  - 250 - 
 
 6.4. if a discrepancy is found during a test pursuant to points  6.1 to 6.3, after corrective 
measures.  
CELEX:32013L0059  - 251 - 
 
 Annex  14 to Decree No .../…Sb.  
 
Information regarding a Category A radiation worker and i nformation characterising 
his or her expected exposure  
 
1. Identification of the permit holder, for whom the radiation worker performs work during 
which he or she is occupationally irradiated: the name and address of the permit holder 
and the name and address  of the workplace;  
2. the radiation worker's name and surname;  
3. the radiation worker's title;  
4. the radiation worker's education;  
5. birth number, or in the case of foreign nationals, residency permit number;  
6. date of birth;  
7. place of birth;  
8. the date of commencement of work with sources of ionising radiation and total time 
working with sources of ionising radiation;  
9. the date work with sources of ionising radiation began at this workplace and the date 
work with sources of ionising radiation ended at this workplace;  
10. the date monitoring of the worker began;  
11. the date monitoring of the worker ended;  
12. the workplace number assigned by the personal dosimetry permit holder;  
13. dosimeter type and number, including information on the duration of the assessment 
period;  
14. information reg arding what type of dosimeter the worker is equipped with, and, in the 
case of internal exposure, how this exposure is assessed;  
15. information on the healthcare provider providing preventive examinations of the 
radiation worker;  
16. information on what type of i onising radiation the worker is working with;  
17. information regarding the type of radiation the worker is exposed to;  
18. information on the radiation worker's profession;  
19. information on whether he or she is a full -time employee of the permit holder;  
20. the date up  to which this information is valid; and  
21. the supervisor's name, the date, and the supervisor's signature.  - 252 - 
 
 Annex  15 to Decree No .../…Sb.  
 
Sample personal radiation badge  
 
 - 253 - 
 
  
 
 
 
 - 254 - 
 
  
- 255 - 
 
 
- 256 - 
 
 
- 257 - 
 
 
- 258 - 
 
 
- 259 - 
 
 
- 260 - 
 
 
- 261 - 
 
 
- 262 - 
 
 
- 263 - 
 
 
- 264 - 
 
 
265 
 
 Annex  16 to Decree No …/….Sb.  
 
Information on a source of ionisi ng radiation sent to the Office by the holder of a permit 
for handling a sou rce of ionising radiation  and by the  registrant  
 
The holder of a permit to handle a source of ionising radiation must send the Office the 
following information about the source of ionising radiation for the list of sources:  
 
1.1. the reference number of the holder of a permit to handle the source of ionising radiation;  
1.2. information on the owner of the source of ionising radiation, if different from the holder 
of the permit to handle the s ource of ionising radiation, as follows:  
1.2.1.  its name, in the case of a legal entity, or name and surname, in the case of a natural 
person;  
1.2.2.  ID number, if assigned, or date of birth, in the case of a private individual; and  
1.2.3.  registered address, in the case of a legal entity, or residential address, in the case of 
a natural person;  
1.3. in the event of the transfer of a source of ionising radiation, information regarding the 
person to whom it was transferred, as follows:  
1.3.1.  its name, in the case of a legal entity, or name  and surname, in the case of a natural 
person;  
1.3.2.  ID number, if assigned, or date of birth, in the case of a private individual;  
1.3.3.  registered address, in the case of a legal entity, or residential address, in the case of 
a natural person; and  
1.3.4.  the transfer date;  
1.4. the name and address of the workplace where the source of ionising radiation is situated;  
1.5. the category of the source of ionising radiation (insignificant, minor, simple, significant, 
very significant);  
1.6. area of application (industry, medicine, veterinary m edicine, education, research, 
military, other);  
1.7. the category of the source of ionising radiation (insignificant, minor, simple, significant, 
very significant);  
1.8. status (actively used in the Czech Republic, outside the Czech Republic, in a warehouse, 
awaitin g disposal, servicing, long -term repairs, unspecified);  
1.9. technical adaptation;  
1.10. type-approval information (yes/no, document type and its number);  
1.11. information on the manufacturer;  
1.12. date of manufacture and serial number;  
1.13. acceptance test date and acceptance cert ificate number;  
1.14. start date for the handling of the source of ionizing radiation; and  
1.15. the date until which this information is valid;  
2. in the case of a radiation generator, also  
2.1. the type (especially X -ray, accelerator);  
2.2. fixation (stationary, mobile, portable ); 
2.3. type name;  
2.4. parts information;  266 
 
 2.5. disposal (returned for disposal outside the Czech Republic, destroyed (disposal), 
unregulated destruction, export outside the Czech Republic or distribution in another 
Member State of the European Union); and  
2.6. the date of di sposal;  
3. in the case of a sealed radionuclide source, also  
3.1. the type catalogue code;  
3.2. certificate number of the sealed radionuclide source and its date of issue;  
3.3. the date of receipt of the machine;  
3.4. the radionuclide's specifications and its activity, and the d ate on which the activity was 
established;  
3.5. resistance to external effects;  
3.6. recommended duration of use;  
3.7. disposal method (consumption, decrease in activity under the limit, permanent storage, 
conversion into another sour ce of ionising radiation (reconstruct ion), returned for 
disposal outside the Czech Republic, destroyed (disposal), unregulated destruction, 
export abroad); and  
3.8. the date of disposal;  
4. in the case of equipment with a sealed radionuclide source, also  
4.1. fixation (stationary, mobile, portable);  
4.2. type name;  
4.3. the total number of sealed radionuclide sources;  
4.4. parts information;  
4.5. disposal method (returned for disposal outside the Czech Republic, destroyed (disposal), 
unregulated destruction, export outside the Czech Republic or distribution in another 
Member State of the European Union);  
4.6. the date of disposal; and  
4.7. information on sealed radionuclide sources in devices to the extent defined under to 
point  3. 
 
A registrant must send the Office the following information about the source of ionising 
radiation for th e list of sources:  
1.1. information about the owner of the source of ionising radiation, in the event that the 
registrant is not the owner; as follows:  
1.1.1.  its name, in the case of a legal entity, or name and surname, in the case of a natural 
person;  
1.1.2.  ID number, if assigned, or date of birth, in the case of a private individual; and  
1.1.3.  registered address, in the case of a legal entity, or residential address, in the case of 
a natural person;  
1.2. the name and address of the workplace where it is situated, if different from t he 
registrant's registered address or place of residence;  
1.3. area of application (industry, medicine, veterinary medicine, education, research, 
military, other);  
1.4. technical adaptation (dental intraoral x -ray devices, dental panoramic x -ray equipment, 
dental co mputer tomograph, veterinary radioscopy or skiascopic equipment, veterinary 
computing tomograph, bone density meter);  
1.5. fixation (stationary, mobile, portable);  267 
 
 1.6. type name;  
1.7. type approval information (yes/no, document type and its number);  
1.8. the manufacturer’s n ame,  
1.9. year of manufacture and serial number;  
1.10. status (actively used in the Czech Republic, outside the Czech Republic, in a warehouse, 
awaiting disposal, servicing, long -term repairs, unspecified);  
1.11. date of acceptance test or last long -term stability test and  the test certificate number;  
1.12. start date for the handling of the source of ionising radiation;  
1.13. in the case of disposal of the source of ionising radiation, its date; and  
1.14. in the case of the transfer of a source of ionising radiation, information regarding t he 
person to whom it was transferred, as follows:  
1.14.1.  its name, in the case of a legal entity, or name and surname, in the case of a 
natural person;  
1.14.2.  ID number, if assigned, or date of birth, in the case of a private individual;  
1.14.3.  registered address, in the case of a legal entity, or residential address, in the case 
of a natural person; and  
1.14.4.  the date of transfer of the source of ionising radiation.  268 
 
 Annex  17 to Decree No …/….Sb.  
 
An overview of manufactured, imported, distributed, or exported sources of ionising 
radiation sources that is sent to the Office  
 
The holder of a permit to manufacture, import, distribute, and export of sources of ionising 
radiation must send the Office the following information on manufactured, imported, distributed, 
and exported sources of  ionising radiation:  
1. information on the person to whom the source of ionizing radiation was transferred, as 
follows:  
1.1.1.  its name, in the case of a legal entity, or name and surname, in the case of a natural 
person;  
1.1.2.  ID number, if assigned, or date of birth, in  the case of a private individual; and  
1.1.3.  registered address, in the case of a legal entity, or residential address, in the case of 
a natural person;  
2. the transfer date;  
3. in the case of equipment with a sealed radionuclide source transferred without this source : 
3.1. type name;  
3.2. type approval information (yes/no, document type and its number); and  
3.3. serial number;  
4. in the case of equipment with a sealed radionuclide source transferred with this source:  
4.1. type name;  
4.2. type approval information (yes/no, document type and its n umber);  
4.3. serial number;  
4.4. the radionuclide's specifications;  
4.5. the serial number of the sealed radionuclide source;  
4.6. the certificate number of the sealed radionuclide source and its date of issue; and  
4.7. the radionuclide's activity and the date on which it was esta blished;  
5. in the case of a sealed radionuclide source transferred separately:  
5.1. serial number;  
5.2. the radionuclide's specifications;  
5.3. the certificate number of the sealed radionuclide source and its date of issue; and  
5.4. the radionuclide's activity and the date on w hich it was established; and  
6. in the case of an open radionuclide source:  
6.1. the radionuclide's specifications;  
6.2. the radionuclide's activity and the date on which it was established; and  
6.3. information on the quantity of the radionuclide.  
 
A registrant must send t he Office the following information on imported, exported, and 
distributed generators of radiation:  
1. information on an imported, exported, and distributed generator of radiation:  
1.1. type name and manufacturer;  
1.2. type approval information (document type and its n umber);  
1.3. serial number;  269 
 
 1.4. information on the person to whom it was transferred, as follows:  
1.4.1.  its name, in the case of a legal entity, or name and surname, in the case of a natural 
person;  
1.4.2.  ID number, if assigned, or date of birth, in the case of a private indiv idual; and  
1.4.3.  registered address, in the case of a legal entity, or residential address, in the case of 
a natural person; and  
1.5. the transfer date.  270 
 
 Annex  18 to Decree No …/….Sb.  
 
Surface activity values for surface contamination  
 
Contamination location  Radionucl ide source type  Surface activity  
[Bq/cm2] 
The surface of floors, walls, ceilings, 
furniture, equipment, etc. in the 
monitored area of the workplace  
The outer surface of personal protective 
aids A radionuclide source emitting beta or 
gamma radiation, and a  low toxicity 
radionuclide source emitting alpha 
radiation  4 
A different radioactive source emitting 
alpha radiation  0.4 
The inner surface of personal protective 
aids 
Workplace surfaces outside the 
monitored zone  A radionuclide source emitting beta or 
gamma radiation, and a low -toxicity 
radionuclide source emitting alpha 
radiation  0.4 
A different radioactive source emitting 
alpha radiation  0.04 
 
Legend:  
 
A low -toxicity radionuclide source emitting alpha radiation is  
1. natural uranium, depleted uranium, natural thorium, Th -228, Th -230, Th -232, U -235, and U -238 is contained in 
ores or chemical concentrates;  
2. radioactive source emitting alpha radiation with a half -life of less than ten days.  
 
Surface activity values apply only to unfixed contamination, if su rface contamination on floors, walls, ceilings, 
furniture and other equipment in the monitored zone of the workplace occurred as a result of the expected ways of 
using sources of ionising radiation.  271 
 
 Annex  19 to Decree No .../….Sb.  
 
The contents of document ation for authorised activities within the scope of exposure 
situations  
 
1. Documentation for evaluation of the properties of a source of ionising radiation must contain:  
1.1. in the case of proof of ability to measure and verify properties of a source of ionising  
radiation:  
1.1.1.  stipulation of a natural person managing the acceptance test and the long -term 
stability test and proof of their special professional competence;  
1.1.2.  proof of special professional competence of the natural person performing the 
acceptance test and the long -term stability test;  
1.1.3.  specifications and acquisition method for measuring aids and measuring 
instruments used in tests that are not the property of the permit holder;  
1.2. in the case of methodologies, procedures, and sample measurement records:  
1.2.1.  the acc eptance test and long -term stability test:  
1.2.1.1.  identification of the holder of the permit for assessment of the properties of 
the ionising radiation source;  
1.2.1.2.  the name(s) and surname of the person who drew up the document;  
1.2.1.3.  the date of the document’s creation;  
1.2.1.4.  the type of test for which the document has been drawn up;  
1.2.1.5.  the kind and type of source of ionising radiation for which the document has 
been drawn up, and a description of its routine use;  
1.2.1.6.  a list of documentation for the source of ionizing radiation required  to 
perform the test, as follows:  
1.2.1.6.1.  records of acceptance tests, of the previous long -term stability test, and 
of constancy tests;  
1.2.1.6.2.  servicing and defect records;  
1.2.1.6.3.  a user manual;  
1.2.1.7.  in the case of radiodiagnostics and interventional radiology, the procedure for 
calibration and tests of the constancy of the operating meter, if they are to be 
performed as part of the acceptance test or long -term stability test;  
1.2.1.8.  the procedure in the event that one of the tests detects a borderline result, an 
atypical result, or non -conformity with tolerances or recommended values;  
1.2.1.9.  information on tests of accessories that have an impact on radiation 
protection, in particular  
1.2.1.9.1.  the radiotherapy planning system;  
1.2.1.9.2.  the radiotherapy recording and verification system;  
1.2.1.9.3.  the primary pair of diagnos tic monitors for mammography X -ray 
equipment with image digitisation;  
1.2.1.9.4.  protective aids for x -ray equipment used in veterinary medicine;  
1.2.1.10.  clear specification of specialised concepts, quantities, units, or abbreviations 
used in the methodology or sample record  in the event that their ambiguous 
interpretation is possible;  
1.2.1.11.  methodologies for individual tests that include  
1.2.1.11.1.  the characteristics of the measured parameter;  
1.2.1.11.2.  the type of measuring instrument and aids;  272 
 
 1.2.1.11.3.  the measurement procedure and method of obtaining measu rement 
results, in particular the description of the measurement, measurement 
set-up geometry, irradiator configuration, quantities and units used, 
and how they are interpreted;  
1.2.1.11.4.  calculations, algorithms, and how they are interpreted;  
1.2.1.11.5.  a description of how b enchmarks that are compared with measured 
values are stipulated;  
1.2.1.11.6.  for the tests referred to in §  28(2(c)(2), §  28(2)(d)(4) and (5), 
§ 28(2)(e)(4), §  30(1)(c)(4) and (5), and §  30(1)(d)(4), stipulation of 
measurement uncertainties;  
1.2.1.11.7.  tolerances of measured par ameters;  
1.2.1.11.8.  how final evaluation of a given test is performed;  
1.2.2.  in the case of a sample acceptance test record and long -term stability test record:  
1.2.2.1.  identification of the permit holder who performed the test;  
1.2.2.2.  the test record number;  
1.2.2.3.  indication of whether it is an acceptance test, a test of long -term stability, or a 
partial test of long -term stability, and why it was performed;  
1.2.2.4.  identification of the natural person that performed the test, and the natural 
person that managed the test;  
1.2.2.5.  for radiotherapy, identificat ion and position of the individual who represented 
the operator of the source of ionising radiation during the test;  
1.2.2.6.  the date and time of the beginning and end of the test;  
1.2.2.7.  the date by which another periodic long -term stability test must be performed 
on th e source of ionising radiation;  
1.2.2.8.  the type, modality and method of use of the tested source of ionising 
radiation, including the kind of image receptor used;  
1.2.2.9.  identification of the licensee or registrant using the source of ionizing 
radiation;  
1.2.2.10.  information abo ut the location of sources of ionising radiation;  
1.2.2.11.  identification of the tested source of ionising radiation, including:  
1.2.2.11.1.  the model and serial number of the source of ionising radiation;  
1.2.2.11.2.  the model and serial number of equipment with a sealed radionuclide 
source; 
1.2.2.11.3.  the model and serial number of a sealed radionuclide source;  
1.2.2.11.4.  the model and serial number of a radiation generator;  
1.2.2.11.5.  the model and serial number of an X -ray tube and its cover;  
1.2.2.11.6.  the model and serial number of an image receptor that is a fixed part 
of a r adiodiagnostic, interventional or veterinary source of ionising 
radiation;  
1.2.2.11.7.  the year of manufacture of the source of ionising radiation;  
1.2.2.11.8.  specification of the focal length and filtration of radiodiagnostic, 
interventional or veterinary sources of ionising ra diation;  
1.2.2.11.9.  specification of other important parts of sources of ionising radiation, 
including the modalities and auxiliary systems in radiotherapy;  
1.2.2.11.10.  specification of the radionuclide contained in a sealed radionuclide 
source, including its activity;  273 
 
 1.2.2.12.  the recor d number of the previous test of long -term stability or acceptance 
test, and if it was performed by another permit holder, the identification of 
the permit holder who performed it;  
1.2.2.13.  information whether a source of ionizing radiation is used in radiodiagnost ic 
medicine, interventional radiology or veterinary imaging features the 
following:  
1.2.2.13.1.  automatic exposure;  
1.2.2.13.2.  classical tomography;  
1.2.2.13.3.  digital subtraction angiography;  
1.2.2.13.4.  a cephalostat;  
1.2.2.14.  information whether  
1.2.2.14.1.  mammography X -ray equipment is used to perform mammography 
screening;  
1.2.2.14.2.  is radiographic or skiascopic X -ray equipment or computed 
tomography equipment used in radiotherapy, including details of this 
use; 
1.2.2.14.3.  computed tomography equipment used in radiodiagnostic medicine or 
interventional radiology allows skiascopic imaging  mode;  
1.2.2.15.  information whether the source of ionizing radiation is  
1.2.2.15.1.  stationary,  
1.2.2.15.2.  mobile,  
1.2.2.15.3.  portable,  
1.2.2.16.  in radiodiagnostic medicine, interventional radiology, and in veterinary 
imaging, identification of accessories to sources of ionising radiation that 
have an impac t on radiation protection, especially  
1.2.2.16.1.  examination tools used;  
1.2.2.16.2.  automatic developing equipment or indirect digitisation reader;  
1.2.2.16.3.  cassettes, indirect digitisation films, X -ray films, and amplification 
films used, including their sensitivity and information whe ther this 
involves a green or blue programme or high -speed film;  
1.2.2.16.4.  a diagnostic monitor that was checked during testing or used to assess 
tests;  
1.2.2.17.  in radiotherapy, identification of accessories to sources of ionising radiation 
that have an impact on radiation protection, especially  
1.2.2.17.1.  a planning, recording and verification system;  
1.2.2.17.2.  a system for transmitting data from the source of ionising radiation to 
the planning system and to the recording and verification system;  
1.2.2.18.  in methods of using a source of ionising radiati on other than as defined 
under points  1.2.2.16 and 1.2.2.17, identification of accessories to sources of 
ionising radiation that have an impact on radiation protection, especially 
sealed radionuclide source applicators used;  
1.2.2.19.  assessment of the presence of d ocumentation for the source of ionizing 
radiation required to perform the test in the workplace;  274 
 
 1.2.2.20.  information on  
1.2.2.20.1.  technical changes that occurred within a source of ionising radiation 
and its accessories that have an impact on radiation protection since 
the last test, and that could affect the performance of the test;  
1.2.2.20.2.  restrictions on the scope of the test and the justification;  
1.2.2.20.3.  a change to test procedures that occurred during the test, including its 
justification;  
1.2.2.20.4.  operating conditions affecting the test being  performed;  
1.2.2.21.  information on instruments and aids used, including the date of the last 
verification of specified measuring instruments;  
1.2.2.22.  assessment whether a source of ionising radiation that is used for the 
medical irradiation or the workplace where it is us ed meets the requirements 
of § 78 to 80;  
1.2.2.23.  a record of the calibration or constancy testing of a working measuring 
instrument, if performed as part of the test;  
1.2.2.24.  records of tests performed as part of the testing, including records of tests 
performed during te sting beyond the scope of the methodology, containing  
1.2.2.24.1.  the number and name of the test that matches the common sample test 
record;  
1.2.2.24.2.  information on the conditions of measurement that affect the tested 
parameters;  
1.2.2.24.3.  the list of measured values and resultant para meters, including 
calibration coefficients and correction factors used;  
1.2.2.24.4.  measurement uncertainties, if their specification is required;  
1.2.2.24.5.  assessment of test results;  
1.2.2.24.6.  tolerances and recommended values for verified parameters;  
1.2.2.24.7.  in the event of failure to meet to lerances or recommended values of 
verified parameters, or in the event of borderline results, comments 
describing this failure or borderline results, including recommendation 
of a solution;  
1.2.2.24.8.  in the event of divergence from the methodology, a record and 
detailed description of the divergence and its justification;  
1.2.2.25.  a summary overview of the results of individual tests, containing:  
1.2.2.25.1.  a table with the numbers and names of tests performed along with 
their evaluation;  
1.2.2.25.2.  comments regarding all tests where a defect, a b orderline or atypical 
result, or conflict with recommendations was found;  
1.2.2.25.3.  deadlines for elimination of less serious defects;  
1.2.2.25.4.  specification of very serious defects, with a warning that due to this 
very serious malfunction, the source of ionising radiation m ay not be 
used until said malfunction has been demonstrably eliminated;  
1.2.2.25.5.  for radiographic X -ray devices used for medical irradiation, 
specification whether the device is suitable for imaging children up to 
3 years of age;  275 
 
 1.2.2.25.6.  in the case of a sealed radionuclid e source and equipment with a 
sealed radionuclide source, a description of visible damage to the 
source, particularly cracks, notches, corrosion, or abrasion;  
1.2.2.26.  in the case of an acceptance test or long -term stability test that has shown 
the current scope or  frequency of operating constancy to be insufficient, the 
proposed scope and frequency of operating constancy tests, except for tests 
performed for a registrant;  
1.2.2.27.  the proposed scope of long -term stability tests in the case of acceptance 
testing of a source of ionising radiation not used in radiodiagnostics, 
interventional radiology, and in veterinary imaging;  
1.2.2.28.  in the case of an acceptance test or long -term stability test performed after 
servicing that could have an effect on dispersed or leaking radiation, or  after 
significant changes to routine operation that could affect personal dosages of 
radiation workers or the population, a record of measurement of dispersed or 
leaking ionising radiation in the vicinity of the source of ionising radiation, 
which contain s: 
1.2.2.28.1.  readings in work sites in the vicinity of sources of ionising radiation;  
1.2.2.28.2.  readings behind shielding that prove shielding efficacy;  
1.2.2.28.3.  exposure parameters used and positions of the source of ionising 
radiation during measurement that correspond to routinely used 
exposure parameters;  
1.2.2.28.4.  estimates of the number and durations of exposures for one calendar 
year;  
1.2.2.28.5.  estimates of dose quantities at measured workplaces and behind 
shielding for one calendar year, calculated from data pursuant to 
points  1.2.2.28.1 to 1.2.2. 28.4;  
1.2.2.28.6.  a description and diagram of the vicinity of the source of ionising 
radiation, including a description of shielding and distances of 
measurement points from the source of ionising radiation and from the 
floor;  
1.2.2.28.7.  in the case of a portable veterinary and  industrial source of ionising 
radiation, information on how far from the source of ionising radiation 
warning tape should be located during routine imaging;  
1.2.2.29.  if a defect is eliminated prior to the issue of the test record:  
1.2.2.29.1.  results of the measurements made on the equipment prior to the 
elimination of the defect;  
1.2.2.29.2.  a description of measures implemented after the fault was detected 
and how it was eliminated;  
1.2.2.29.3.  measurement results after elimination of the fault;  
1.3. in the case of an overview of equipment and arrangeme nts for carrying out the proposed 
services:  
1.3.1.  a list of measuring instruments used during tests, including type and serial number;  
1.3.2.  a list of aids used during tests;  
1.4. in the case of a plan to ensure measurement of quantities:  
1.4.1.  identification information for ite ms on the list pursuant to point  1.3 that are 
specified measuring instruments, and a plan for their metrological provisioning;  276 
 
 1.4.2.  identification information for items on the list pursuant to point  1.3 that are 
operating measuring instruments, and a plan for t heir metrological provisioning.  
2. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically performance of personal dosimetry, must contain  
2.1. in the case of methodologies and procedures:  
2.1.1.  a sampl e contract with customers, to whom the personal dosimetry service will be 
provided;  
2.1.2.  sample instructions for customers;  
2.1.3.  how and how often customers will be given personal monitoring results;  
2.1.4.  a sample of the document that will be used to give customers perso nal monitoring 
results;  
2.1.5.  how and how often the Office will be given personal monitoring results;  
2.1.6.  a description of the process of evaluating personal doses, including quantities that 
will be stipulated, how they are calculated, and their inaccuracies;  
2.1.7.  a desc ription of the assessment method for eye lens exposure;  
2.1.8.  a description of the effective dose calculation method;  
2.1.9.  a description of the assessment of personal doses when protective aids are used, 
including calculation of evaluated quantities when multiple per sonal dosimeters are 
used;  
2.1.10.  a description of how the effect of known systematic inaccuracies is eliminated, 
including energy and directional dependencies;  
2.1.11.  a description of how a dosimeter irradiated in an abnormal manner is assessed;  
2.1.12.  a description of how do ses that exceed derived or personal limits are assessed;  
2.2. in the case of an overview of equipment and arrangements for carrying out the proposed 
services:  
2.2.1.  a list of devices and aids used in performing the personal dosimetry services;  
2.2.2.  descriptions and drawin gs of personal dosimeters;  
2.2.3.  conditions for the use of personal dosimeters;  
2.3. in the case of a plan to ensure measurement of quantities:  
2.3.1.  items on the list under point  2.2 that are specified measuring instruments, and a 
plan for their metrological provisioning;  
2.3.2.  items on the list under point  2.2 that are operating measuring instruments, and a 
plan for their metrological provisioning;  
2.3.3.  a plan for metrological provisioning of the assessment process for personal 
dosimetry as a whole;  
2.3.4.  a plan for participation in inter national comparative measurements in the area of 
personal dosimetry.  
3. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically stipulation of personal doses of workers in the workplace, 
with the possibility of increased radiation exposure from natural sources of radiation pursuant 
to § 93(1)(b) of the Atomic Act and in workplaces with possible increased exposure from 
radon pursuant to §  96(1) of the Atomic Act, must contain:  
3.1. in the case of me thodologies and procedures:  
3.1.1.  the methodology for measurement of radon activity concentration and the 
procedure for determining the effective dose due to the inhalation of radon and its 
decay products;  277 
 
 3.1.2.  the methodology for measurement of spatial dose equivale nt rate and procedures for 
stipulating personal doses due to external gamma irradiation;  
3.1.3.  the methodology for measurement and stipulation of the effective dose due to 
inhalation of natural radionuclides other than radon and its decay products;  
3.1.4.  the methodolo gy for measurement and stipulation of personal doses due to 
exposure of the skin, eye lens, and limbs to a natural radionuclide;  
3.1.5.  how measurements are performed and results evaluated in relation to values 
specified in §  91(2);  
3.1.6.  how measurements are performed  and results evaluated in relation to the value 
specified in §  91(1);  
3.1.7.  how repeat measurements are performed and results evaluated in relation to values 
specified in §  91(4)(b);  
3.1.8.  how measurements are performed and results evaluated in relation to the value 
specified in §  91(2);  
3.1.9.  how measurements are performed and results evaluated in relation to exposure 
limits specified in §  91(1);  
3.1.10.  personal monitoring procedures;  
3.1.11.  a description of instrumentation;  
3.1.12.  description of the content of the record on establishing person al doses, including  
3.1.12.1.  number;  
3.1.12.2.  identification of the permit holder;  
3.1.12.3.  identification of the individual that performed the measurement;  
3.1.12.4.  identification of who ordered the measurement;  
3.1.12.5.  identification of the workplace operator;  
3.1.12.6.  name and address of the workplace;  
3.1.12.7.  workplace classification pursuant to §  93(1)(b) of the Atomic Act and §  91 
or pursuant to §  96(1) of the Atomic Act;  
3.1.12.8.  a description of the site and technologies used;  
3.1.12.9.  the measurement methodology used and the purpose of the measurements;  
3.1.12.10.  the date of the measur ements;  
3.1.12.11.  analysis of possible scenarios of increased exposure of workers to natural 
radiation sources;  
3.1.12.12.  identification of workers in the workplace;  
3.1.12.13.  justification of the scope of measurements with reference to the decree and 
the methodology used;  
3.1.12.14.  a list of de vices and aids used, for specified measuring instruments, their 
verification sheets and their expiry dates;  
3.1.12.15.  information on measurement locations;  
3.1.12.16.  a description of measurement conditions;  
3.1.12.17.  measurement results;  
3.1.12.18.  assessment of measurement results;  
3.1.12.19.  a conclusion with proposed further steps;  
3.1.12.20.  the date the record was drawn up;  
3.1.12.21.  the signature of an individual with appropriate professional qualifications 
and authority who ensures fulfilment of duties during measurement, and of 
the statutory body of the permit holder per forming the measurements.  278 
 
 4. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically measurement and assessment of exposure to a natural source 
of radiation in a building for purposes pursuan t to §  98 and § 99 of the Atomic Act, must 
contain:  
4.1. in the case of methodologies and procedures:  
4.1.1.  methodologies for measuring the radon activity concentration in occupied and 
unoccupied buildings and under different exposure conditions, including  
4.1.1.1.  procedures  for measuring radon activity concentration;  
4.1.1.2.  a description of exposure conditions for measurement in occupied and 
unoccupied buildings;  
4.1.1.3.  a description of the selection of measurement points;  
4.1.1.4.  a description of instrumentation;  
4.1.1.5.  how measurement results are pres ented;  
4.1.2.  the methodology for measurement of spatial dose equivalent rate, including:  
4.1.2.1.  the measurement procedure;  
4.1.2.2.  a description of the selection of measurement points;  
4.1.2.3.  a description of instrumentation;  
4.1.2.4.  how measurement results are presented;  
4.1.3.  the procedure for m easuring temperature in the building;  
4.1.4.  a description of how measurement results are assessed for both occupied and 
unoccupied buildings and different exposure conditions in relation to reference 
levels specified in §  100(1) and (2);  
4.1.5.  a description of the rec ord of measurement and assessment of natural radiation in a 
building, including:  
4.1.5.1.  number;  
4.1.5.2.  identification of the permit holder;  
4.1.5.3.  identification of the individual that performed the measurement;  
4.1.5.4.  identification of who ordered the measurement;  
4.1.5.5.  the date of the me asurements;  
4.1.5.6.  information on the measured building and its type;  
4.1.5.7.  a description of the building and its use at the time of measurement, including 
a site plan showing the measurement sites;  
4.1.5.8.  the measurement methodology used and the purpose of the measurements;  
4.1.5.9.  a description of the measuring conditions in the building, including its usage 
at the time of measurement and weather conditions at the time of 
measurement;  
4.1.5.10.  a list of devices and aids used, for specified measuring instruments, their 
verification sheets and  their expiry dates;  
4.1.5.11.  measurement results;  
4.1.5.12.  assessment of measurement results;  
4.1.5.13.  a conclusion with proposed further steps;  
4.1.5.14.  the date the record was drawn up;  
4.1.5.15.  the signature of an individual with appropriate professional qualifications 
and authority who ensures f ulfilment of duties during measurement, and of 
the statutory body of the permit holder performing the measurements.  279 
 
 5. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically stipulation of t he radon index for parcel of land for purposes 
pursuant to §  98 of the Atomic Act, must contain:  
5.1. in the case of methodologies and procedures:  
5.1.1.  the methodology for determining the radon index of the parcel of land, including:  
5.1.1.1.  how to measure the activity conc entration of radon in soil air;  
5.1.1.2.  how to sample soil air;  
5.1.1.3.  how to determine the gas permeability of soils;  
5.1.1.4.  how to use local indicators and the general characteristics of subsoil affecting 
the direction and rate of radon movement in foundation soil;  
5.1.1.5.  how to det ermine the radon index of a parcel of land;  
5.1.1.6.  a description of instrumentation;  
5.1.1.7.  a description of the results assessment method pursuant to §  99(4);  
5.1.2.  a description of the content of the record on determining the radon index of a parcel 
of land, including  
5.1.2.1.  numbe r; 
5.1.2.2.  identification of the permit holder;  
5.1.2.3.  identification of the individual that performed the measurement;  
5.1.2.4.  identification of who ordered the measurement;  
5.1.2.5.  identification of the measured land parcel including a map on which 
measured areas, sampling sites, and soil probes are shown;  
5.1.2.6.  identification of the future building for which the determination is taking 
place;  
5.1.2.7.  the date of the measurements;  
5.1.2.8.  the methodology used and the purpose of the measurements;  
5.1.2.9.  a description of the measurement conditions, layout of measuri ng points, their 
number and grid, weather conditions at the time of measurement, description 
of the land parcel, including a regional geological description and its 
geological characteristics, a list of buildings and other things present on the 
land parcel  at the time of the measurement;  
5.1.2.10.  in the case of sampling of soil air, information on equipment used, the 
amount of air sampled, and the sampling depth;  
5.1.2.11.  a description of how to determine the gas permeability of soils;  
5.1.2.12.  a list of devices and aids used, for sp ecified measuring instruments, their 
verification sheets and their expiry dates;  
5.1.2.13.  the results of measurements of radon activity concentration including 
statistical characteristics;  
5.1.2.14.  the determined gas permeability of soils;  
5.1.2.15.  the determined radon index of the land parcel;  
5.1.2.16.  a conclusion with information on further steps;  
5.1.2.17.  the date the record was drawn up;  
5.1.2.18.  the signature of an individual with appropriate professional qualifications 
and authority who ensures fulfilment of duties during measurement, and of 
the statuto ry body of the permit holder performing the measurements.  
6. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically measurement and assessment of the content of natural 280 
 
 radionuclides in cons truction material for purposes pursuant to §  101(2)(a) of the Atomic 
Act, must contain:  
6.1. in the case of methodologies and procedures:  
6.1.1.  sampling and sample treatment;  
6.1.2.  the contents of the sampling record;  
6.1.3.  a description of sampling locations and frequency;  
6.1.4.  a description of instrumentation;  
6.1.5.  how to measure and process measurement results for specific activities of Ra -226, 
Th-228, and K -40, including measurement uncertainties and how to express 
measurement results;  
6.1.6.  how to calculate the specific activity index, incl uding its uncertainties;  
6.1.7.  how the specific activity index result is assessed in relation to values specified in 
§ 105(2) and (4);  
6.1.8.  a description of the record of measurement and assessment of natural radionuclides 
in construction material, including:  
6.1.8.1.  number;  
6.1.8.2.  identification of the permit holder;  
6.1.8.3.  identification of who ordered the measurement;  
6.1.8.4.  identification of the construction material manufacturer or importer;  
6.1.8.5.  specification of the measurement methodology;  
6.1.8.6.  the sample number under which the sample is recorded in  the measurement 
laboratory;  
6.1.8.7.  information on the sampled construction material;  
6.1.8.8.  the purpose of the sampled construction material;  
6.1.8.9.  the date of manufacture or import of the sampled construction material;  
6.1.8.10.  the sampling location;  
6.1.8.11.  the sampling date;  
6.1.8.12.  the sampling method;  
6.1.8.13.  identification of the individual that took the sample;  
6.1.8.14.  information regarding treatment of the sample for measurement outside the 
measurement laboratory;  
6.1.8.15.  a list of devices and aids used, for specified measuring instruments, their 
verification sheets  and their expiry dates;  
6.1.8.16.  identification of the individual that performed the measurement;  
6.1.8.17.  the place and date of measurement;  
6.1.8.18.  measurement results;  
6.1.8.19.  assessment of measurement results;  
6.1.8.20.  if values specified in §  105(2) and (4) are exceeded, information regarding  
further steps;  
6.1.8.21.  the date the record was issued;  
6.1.8.22.  the signature of an individual with appropriate professional qualifications 
and authority who ensures fulfilment of duties during measurement, and of 
the statutory body of the permit holder performing the mea surements.  
7. Documentation for the performance of services that are important from the perspective of 
radiation protection, specifically measurement and assessment of the content of natural 
radionuclides in water for purposes pursuant to §  100(2)(a) of the A tomic Act, must contain:  281 
 
 7.1. in the case of methodologies and procedures:  
7.1.1.  sampling and sample treatment;  
7.1.2.  the contents of the sampling record;  
7.1.3.  a description of sampling locations and frequency;  
7.1.4.  a description of instrumentation;  
7.1.5.  how to measure and process measur ement results, including measurement 
uncertainties and how to express measurement results for:  
7.1.5.1.  total alpha activity concentration;  
7.1.5.2.  total beta activity concentration;  
7.1.5.3.  radon activity concentration;  
7.1.5.4.  the activity concentrations of other natural radionuclides;  
7.1.5.5.  the activity concentration of K -40; 
7.1.6.  the method of calculating the indicative dose, including uncertainties of its 
determination and expression of the result;  
7.1.7.  how measurement results are evaluated in relation to values specified in §  101(1), 
(2), and (6);  
7.2. a description of the record of measurement and assessment of natural radionuclides in 
water, including:  
7.2.1.  number;  
7.2.2.  identification of the permit holder;  
7.2.3.  identification of who ordered the measurement;  
7.2.4.  identification of the drinking water supplier and bottled wat er producer or importer;  
7.2.5.  identification of the water main;  
7.2.6.  the measurement methodology used and the purpose of the measurements;  
7.2.7.  the sample number under which the sample is recorded in the measurement 
laboratory;  
7.2.8.  information on the type of water, including  information regarding the removal of 
natural radionuclides from the water;  
7.2.9.  the sampling location;  
7.2.10.  the sampling date;  
7.2.11.  the sampling method;  
7.2.12.  identification of the individual that took the sample;  
7.2.13.  information regarding treatment of the sample for measurement outside the 
measurement laboratory;  
7.2.14.  a list of devices and aids used, for specified measuring instruments, their 
verification sheets and their expiry dates;  
7.2.15.  identification of the individual that performed the measurement;  
7.2.16.  the place and date of measurement;  
7.2.17.  measurement results;  
7.2.18.  assessment of measurement results;  
7.2.19.  if values specified in §  101(1), (2), and (6) are exceeded, information regarding 
further steps;  
7.2.20.  the date the record was issued;  
7.2.21.  the signature of an individual with appropriate professional qualificat ions and 
authority who ensures fulfilment of duties during measurement, and of the 
statutory body of the permit holder performing the measurements.  282 
 
 8. Documentation for the performance of services that are important from the perspective of 
radiation protectio n, specifically measurement and assessment of radionuclide content in a 
radioactive substance released from a workplace with the possibility of increased exposure 
form a natural source of radiation for purposes pursuant to §  95(1)(b) of the Atomic Act, 
must contain:  
8.1. in the case of methodologies and procedures:  
8.1.1.  sampling and sample treatment;  
8.1.2.  the contents of the sampling record;  
8.1.3.  a description of sampling locations and frequency;  
8.1.4.  a description of instrumentation;  
8.1.5.  a description of how to measure and process mea surement results, including 
measurement uncertainties and how to express measurement results for:  
8.1.5.1.  total alpha activity concentration;  
8.1.5.2.  total beta activity concentration;  
8.1.5.3.  specific activity/activity concentration of natural radionuclides from the U -
238 and Th -232 series;  
8.1.5.4.  specific activity/activity concentration of K -40; 
8.1.6.  calculation models and methods for an effective dose caused by release of a 
radioactive substance;  
8.1.7.  how to evaluate measurement results in relation to values specified in §  108(4) and 
§ 95(3) of  the Atomic Act;  
8.2. a description of the record of measurement and assessment of the content of 
radionuclides in a substance released from a workplace with possible increased exposure 
from a natural source of radiation, including:  
8.2.1.  number;  
8.2.2.  identification of th e permit holder;  
8.2.3.  identification of who ordered the measurement;  
8.2.4.  identification of the individual releasing the radioactive substance;  
8.2.5.  identification of the workplace form which the radioactive substance is being 
released;  
8.2.6.  the measurement methodology used a nd the purpose of the measurements;  
8.2.7.  the sample number under which the sample is recorded in the measurement 
laboratory;  
8.2.8.  identification of the sampled released radioactive substance;  
8.2.9.  how the sampled released radioactive substance is being released;  
8.2.10.  the samp ling location;  
8.2.11.  the sampling date;  
8.2.12.  the sampling method;  
8.2.13.  identification of the individual that took the sample;  
8.2.14.  information regarding treatment of the sample for measurement outside the 
measurement laboratory;  
8.2.15.  a list of devices and aids used, for specified m easuring instruments, their 
verification sheets and their expiry dates;  
8.2.16.  identification of the individual that performed the measurement;  
8.2.17.  the place and date of measurement;  
8.2.18.  measurement results;  283 
 
 8.2.19.  assessment of measurement results;  
8.2.20.  a conclusion with proposed f urther steps;  
8.2.21.  the date the record was issued;  
8.2.22.  the signature of an individual with appropriate professional qualifications and 
authority who ensures fulfilment of duties during measurement, and of the 
statutory body of the permit holder performing the measu rements.  284 
 
 Annex  20 to Decree No …/….Sb.  
 
Procedures for ensuring radiation protection by a registrant when using a source of 
ionising radiation  
 
1. General requirements  
1.1. The registrant must send the Office a copy of the record of  
1.1.1.  the acceptance test of a newly acquired source of ionising radiation prior to 
commencing its use;  
1.1.2.  a long -term stability test of a source of ionising radiation that has been placed back 
into operation after a long period of idleness, within 1 month of it being placed 
back into operation;  and 
1.1.3.  the acceptance test of a fixed source of ionising radiation that has been moved prior 
to commencing its re -use. 
1.2. Within one month, a registrant must:  
1.2.1.  notify the Office of the model and serial number of a source of ionising radiation 
handed over for dis posal, and furnish the Office with confirmation of disposal 
issued by the person that performed it;  
1.2.2.  notify the Office of the model and serial number of a source of ionising radiation 
sold or otherwise transferred to another person; and  
1.2.3.  notify the Office of  the model and serial number of a source of ionising radiation 
that has been taken out of operation for the long term.  
1.3. During the acceptance test and long -term stability test, the registrant must ensure that the 
person securing the registrant's radiation p rotection  
1.3.1.  cooperates with the person performing this test, especially in providing information 
on the source of ionising radiation and its accessories, its use, and on the results of 
operating constancy tests; and  
1.3.2.  has taken receipt of information on test r esults from the person performing this test.  
2. Requirements for the use of intra -oral dental x -ray equipment  
2.1. During imaging and routine operation, the registrant must:  
2.1.1.  when setting exposure parameters, developing film, or editing a digital image, 
follow the instructions of the manufacturer and the person that performed  
2.1.1.1.  the acceptance test, if a long -term stability test has not yet been performed on 
the equipment; or  
2.1.1.2.  in cases not provided for under point  2.1.1.1, the most recent long -term 
stability test;  
2.1.2.  make a record of every action that makes it possible to retroactively assess patient 
exposure; and  
2.1.3.  keep the record pursuant to point  2.1.2 for ten years.  
2.2. A registrant must ensure optimisation of radiation protection of radiation workers and 
the population as fo llows:  
2.2.1.  the distance of an individual performing the irradiation from the imaged patient 
must be greater than 2  m, or during imaging this individual must be behind a barrier 
equivalent to at least 15  cm of solid brick; and  
2.2.2.  other individuals present in the r oom during imaging must be at least 5  m from the 
imaged patient, or must be behind a barrier equivalent to at least 15  cm of solid 
brick and simultaneously at least 2  m from the imaged patient.  285 
 
 2.3. A registrant may use portable intra -oral X -ray equipment  
2.3.1.  only if it is a secondary device for use outside a permanent office; or  
2.3.2.  if for serious reasons a different device cannot be used as the primary device.  
2.4. A registrant must ensure that a portable intra -oral X -ray device is equipped with an 
image receptor holder co rresponding to the type of device and image receptor used, 
which must be used during routine imaging.  
2.5. If a discrepancy is found during the operating constancy test performed pursuant to 
Annex  13 
2.5.1.  points  1.1, 1.2.1, or 1.3.1, the registrant must reconfigure standard exposure 
parameters so that the change in imaging is compensated for all exposures, and 
must continue to use these reconfigured exposure parameters during routine 
operation and during operating constancy tests, or, in the event that such 
reconfigu ration is not possible, must arrange servicing to correct it;  
2.5.2.  points  1.2.2 or 1.3.2, the registrant must clean the monitor used for clinical 
diagnosis;  
2.5.3.  point  1.3.3, the registrant must stop using unsatisfactory indirect digitisation film; 
and 
2.5.4.  point  3.1, th e registrant must clean the negatoscope.  
3. Requirements for the use of panoramic dental X -ray equipment and a dental computed 
tomography scanner  
3.1. During imaging and routine operation, the registrant must:  
3.1.1.  follow the instructions of the manufacturer, exposure table, or pre -sets, or follow 
the instructions of the person who performed the long -term stability test or the 
acceptance test;  
3.1.2.  make a record of every action that makes it possible to retroactively assess patient 
exposure; and  
3.1.3.  keep the record defined under  point  3.1.2 for 10 years.  
3.2. A registrant must ensure optimisation of radiation protection of radiation workers and 
the population as follows:  
3.2.1.  during routine imaging, he or she must follow instructions regarding protection 
from scattered radiation specified in the acceptance test record, including proposed 
structural modifications or the use of protective aids;  
3.2.2.  during imaging, he or she shall ensure that no one other than the imaged patient is 
in the room.  
3.3. If a discrepancy is found during the operating consta ncy test performed pursuant to 
Annex  13 
3.3.1.  points  2.1.1, 2.2, 2.3.1, or 4.1, the registrant must arrange servicing;  
3.3.2.  points  2.1.2, 2.3.2, or 4.2, the registrant must clean the monitor used for clinical 
diagnosis;  
3.3.3.  point  2.3.3, the registrant must stop using uns atisfactory indirect digitisation film; 
and 
3.3.4.  point  3, the registrant must clean the negatoscope.  
4. Requirements for the use of veterinary X -ray equipment  
4.1. A registrant must ensure optimisation of radiation protection of radiation workers and 
the population as follows:  286 
 
 4.1.1.  during routine imaging, he or she must follow instructions regarding protection 
from ionising radiation specified in the acceptance test record or the long -term 
stability test record, including proposed structural modifications or the use of 
prote ctive aids;  
4.1.2.  in the case of an individual assisting during imaging of an animal in a location close 
to the X -ray beam, with an individual performing imaging with a portable 
veterinary X -ray device, he or she shall ensure:  
4.1.2.1.  the use of a protective shielding a pron and collar providing shielding 
equivalent to at least 0.25  mm of lead; and  
4.1.2.2.  if during exposure the hands of this individual are near the primary beam, 
also the use of protective shielding gloves equivalent to at least 0.25  mm Pb.  
4.2. During imaging and rou tine operation, the registrant must:  
4.2.1.  use the source of ionising radiation according to the manufacturer's instructions;  
4.2.2.  if the animal must be held during the examination,  
4.2.2.1.  ensure that the individual holding the animal is over the age of 18 and is not a 
pregnant woman;  
4.2.2.2.  instruct the individual holding the animal regarding  
4.2.2.2.1.  possible risks of ionising radiation related to holding the animal; and  
4.2.2.2.2.  instruct them regarding the appropriate way to hold the animal with 
respect to the edge of the X -ray field and the resu lts of scattered 
radiation measurements;  
4.2.2.3.  ensure the correct use of protective aids;  
4.2.2.4.  ask for written consent from the person holding the animal; and  
4.2.2.5.  ensure that the size and position of the X -ray field is configured using a light 
field so that the hands of the individual holding the animal are not located 
within the primary beam;  
4.2.3.  keep records of individuals holding the animal during examination;  
4.2.4.  keep information pursuant to point  4.2.3 for five years;  
4.2.5.  ensure that only individuals whose presence is necessary during the examination 
are present in the examination room; and  
4.2.6.  ensure the X -ray beam is collimated so that the size of the X -ray field is as small as 
possible with regards to the required examination; the X -ray field must not be 
larger than the image rece ptor. 
4.3. During a radiographic examination at a temporary workplace, a registrant must  
4.3.1.  preferentially use an area that is surrounded by natural barriers, especially a wall or 
fence;  
4.3.2.  if use of an area pursuant to point  4.3.1 is not possible and the examination  is taking 
place outside, ensure that no individual is located in the area in the path of the 
primary beam during irradiation;  
4.3.3.  mark off the area where animals are imaged with a warning tape at the distance 
stipulated in the acceptance test record or the lo ng-term stability test record;  
4.3.4.  ensure that only the individual assisting during imaging is present in the area where 
the examination is being performed, and that their presence is necessary during the 
examination;  
4.3.5.  ensure that an individual pursuant to poin t 4.3.4  
4.3.5.1.  is equipped with personal protective aids;  287 
 
 4.3.5.2.  is over the age of 18;  
4.3.5.3.  is not a pregnant woman;  
4.3.5.4.  has been instructed of the possible risks of ionising radiation related to 
assistance during imaging of an animal; and  
4.3.5.5.  has provided written agreement to assi st while imaging the animal;  
4.3.6.  place the image receptor in a holder so that it does not need to be held during 
exposure;  
4.3.7.  if it is not possible to proceed pursuant to point  4.3.6, use means to ensure that the 
hands of the individual holding the image receptor  are not in the immediate vicinity 
of the primary beam; in this case, the registrant must ensure that the individual 
holding the image receptor uses protective gloves;  
4.3.8.  choose the direction of the primary beam so that it is absorbed by the terrain as 
soon a s possible;  
4.3.9.  mark the size of the X -ray field with a light field, and if light conditions do not 
permit good visibility of the light field, employ means to ensure that the edges of 
the light field are precisely aimed;  
4.3.10.  set beam collimation and image receptor  size so that the primary beam does not 
reach past its edge;  
4.3.11.  if possible, give the animal a sedative prior to examination; and  
4.3.12.  ensure that the individual performing imaging gives a clear, loud warning prior to 
irradiation to all potentially present individ uals near the irradiation location that 
ionising radiation will be used.  
4.4. If a discrepancy is found during the operating constancy test performed pursuant to 
Annex  13 
4.4.1.  point  5.1, the registrant must stop using an unsatisfactory protective aid; and  
4.4.2.  points  5.2, 5.3, or 5.4, the registrant must arrange servicing.  
5. Requirements for the use of an X -ray bone densitometer  
5.1. A registrant must  
5.1.1.  during imaging, follow the instructions of the manufacturer of the source of 
ionising radiation;  
5.1.2.  make a record of every action th at makes it possible to retroactively assess patient 
exposure; and  
5.1.3.  keep the record pursuant to point  5.1.2 for 10 years.  
5.2. If a discrepancy is found during the operating constancy test performed pursuant to 
Annex  13 point  6, the registrant must not use the s ource of ionising radiation for medical 
irradiation until the discrepancy is eliminated through servicing and its elimination is 
confirmed with a successful operating constancy test.  288 
 
 Annex  21 to Decree No …/….Sb.  
 
REGISTRATION FORM - A1 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
REQ UEST FOR REGISTRATION OF USE OF A SOURCE OF IONISING RADIATION  
B. Identification of the applicant  
Name of the legal entity or name(s) and surname of the natural person:2) ID number 3): 
Residential address of the natural person or registered address of the  legal entity:2) 
Mailing address:  
Name(s) and surname of persons that are the statutory body or a member of the statutory body of the legal 
entity:2) 
 
C. Specification of the source of ionising radiation in use 4) 
 
 Dental X -ray equipment  
 Veterinary X-ray equipment  
 X-ray bone densitometer  A. For SONS use1) 
  
 
 
 
 
If administrative fees  
are paid via fee stamps,  
paste here.  289 
 
 D. Information necessary for obtaining an extract from the Criminal Records Register for a natural person 
or a person who is the statutory body or a member of the statutory body of a legal entity (if there are sev eral 
persons who are a statutory body or members of a statutory body, provide their details on a separate 
attachment to the registration form)  
Name(s) and surname:  Date of birth:  
Maiden name:  Place of birth:  
Birth number:  District:  
Citizenship  Town:  
 
E. Information on payment of fees - if paid by bank transfer  
 
debited from account number  credited to account number  Amount (CZK)  
   
 
Payment codes  
Variable  special processing  constant  specific  
*    
 
* provide an ID number; if a natural person hasn't b een assigned an ID number, provide the first 6 digits of their 
birth number  
 
 
______________________________________  
Date and applicant's signature  
 
 
1) Do not fill in, for use of the State Office for Nuclear Safety  
2) Cross out where inapplicable  
3) If a natural p erson has not been assigned an ID number, fill in their birth number  
4) Select the source of ionising radiation you are registering  
 
Annexes to registration form A1  
 
 Information on the source of ionising radiation  
 Record from the acceptance test or most recen t long -term stability test  
 Confirmation that the person ensuring radiation protection for the registrant has undergone preparations  
 Document on the appointment of a natural person ensuring radiation protection for the registrant and their 
written consent t o the appointment  
 Proof of professional competence of the natural person for the registered activity or proof of professional 
competence for the registered activity for at least one member of the statutory body, if the applicant is a 
legal entity  
 290 
 
 REGISTRA TION FORM - A2 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
REQUEST FOR REGISTRATION OF IMPORT, EXPORT, OR DISTRIBUTION  
 OF A RADIATION GENERATOR  
B. Identification of the applicant  
Name of the legal entity or name(s) and surname of the natural person:2) ID number 3): 
Residential addr ess of the natural person or registered address of the corporate entity:2) 
Mailing address:  
The name(s) and surname of persons that are the statutory body or a member of the statutory body of the legal 
entity:2) 
 
C. Specification OF THE registered activ ity 4) 
 
 Import of a radiation generator  
 
 Export of a radiation generator  
 
 Distribution of a radiation generator  
 A. For SONS use1) 
  
 
 
 
 
If the administrative fee  
is paid with a stamp,  
paste here.  291 
 
  
D. Information necessary for obtaining an extract from the Criminal Records Register for a natural person 
or a person who is the statut ory body or a member of the statutory body of a legal entity (if there are several 
persons who are a statutory body or members of a statutory body, provide their details on a separate 
attachment to the registration form)  
Name(s) and surname:  Date of birth:  
Maiden name:  Place of birth:  
Birth number:  District:  
Citizenship  Town:  
 
 
E. Information on payment of fees - if paid by bank transfer  
 
debited from account number  credited to account number  Amount (CZK)  
   
 
 
Payment codes  
Variable  special processin g constant  specific  
*    
 
* provide an ID number; if a natural person hasn't been assigned an ID number, provide the first 6 digits of their 
birth number  
 
 
 
 
 
______________________________________  
Date and applicant's signature  
 
 
1) Do not fill in, for use  of the State Office for Nuclear Safety  
2) Cross out where inapplicable  
3) If a natural person has not been assigned an ID number, fill in their birth number  
4) Select the activity you are registering for  
 
Annex to registration form A2  
 
 Proof of professional compet ence of a natural person or one member of the statutory body  
 292 
 
  
 
 
S T A T E  O F F I C E  F O R  N U C L E A R  S A F E T Y  
 
REGISTRATION FORM - B 
 
Date:  
Ref. No:  
Processing department:  
Authorised official:  
 
CONFIRMATION OF REGI STRATION  
 
The State Office for Nuclear Safety, as the administrative body competent pursuant to §  10 of 
Act No 263/2016, the Atomic, Act, confirms the registration of:  
1. the use of a source of ionising radiation, a radiation generator in the area of dental 
radiodiagnostics, in the field of veterinary medicine, and bone densitometers;  
2. import of a radiation generator, export of a radiation generator, distribution of a 
radiation generator.  
for: 
Name of the legal entity or name(s) and surname of the natural person:  
Residential address of the natural person or regist ered address of the legal entity:  
ID number/birth number:  
 
 
 
 
for the State Office for Nuclear Safety:  293 
 
 Annex  22 to Decree No …/….Sb.  
 
National diagnostic reference levels  
 
National diagnostic reference levels for radiographic examinations of adults  
for gro ups of standard patients, regardless of gender, with an average weight of 70  kg ± 5  kg, with the weight of 
individual patients within the range of 50 - 90 kg  
Examination type  PKA (mGy ×cm2) Ke (mGy)  
Skull, overview images PA  700 2.8 
Skull, overview images  LAT  550 2.2 
Chest PA  220 0.3 
Chest LAT  550 1.1 
Cervical spine AP  290 1.7 
Cervical spine LAT  280 1.3 
Thoracic spine AP  1100  4.4 
Thoracic spine LAT  1200  5.7 
Lumbar spine AP  1700  6.2 
Lumbar spine LAT  3100  12.0 
Abdomen AP  2900  5.2 
Pelvis AP  2000  4.5 
 
Legend:  
 
PKA– product of kerma and surface area  
Ke– initial surface kerma  
PA– rear-front projection  
LAT – side projection  
AP– front -rear projection  
 
 
 
National diagnostic reference levels for radiographic -skiascopic and skiascopic examinations of adults  
for groups of standard patients, regardless of gender, with an average weight of 70  kg ± 5  kg, with the weight of 
individual patients within the range of 50 - 90 kg  
Examination type  PKA for the entire examination 
(Gy×cm2) 
Oesophagus  15 
Stomach and duoden um 16 
Large intestine  32 
Passage through the digestive 
tract 12 
Excretion urography  13 
 
Legend:  
 
PKA – product of kerma and surface area  
 
 
 
National diagnostic reference levels for adult examination in interventional radiology  
for groups of standard pa tients, regardless of gender, with am average weight of 80  kg ± 5  kg, with the weight of 
individual patients within the range of 60 - 100 kg  294 
 
 Examination type  PKA for the entire examination 
(Gy×cm2) 
Coronography  49 
PCI/PTCA  91 
 
Legend:  
 
PKA– product of k erma and surface area  
PCI - percutaneous coronary intervention  
PTC - percutaneous transluminal coronary angioplasty  
 
 
 
National diagnostic reference levels for examination of adults using computed tomography  
for groups of standard patients, regardless of g ender, with an average weight of 70  kg ± 5  kg, with the weight of 
individual patients within the range of 50 - 90 kg  
Examination type  CVOL (mGy)  PKL for the entire examination 
(mGy ×cm) 
Head  65 1100  
Neck  21 500 
Chest  15 500 
Spine  32 550 
Abdomen  19 750 
Pelvis  25 860 
 
Legend:  
 
PKL– product of kerma and length  
CVOL– volumetric kerma index for computed tomography  
 
 
National diagnostic reference levels for mammography examinations  
for groups of standard patients defined by thickness of the breast after com pression in cranial -caudal projection 
listed in the first column of the table  
Breast thickness after compression 
(mm)  DG for cranial –caudal 
projection (mGy)  
19 – 23 1.1 
30 – 34 1.3 
43 – 47 1.6 
51 – 55 1.8 
58 – 62 2.1 
73 – 77 2.5 
85 – 95 3.0 
 
Legend : 
 
DG – average dose in the milk gland  
 
 
 295 
 
 National diagnostic reference levels for dental examinations of adults  
for all adult patients  
Examination type  Ki (mGy)  PKA (mGy ×cm2) 
Intraoral image of the maxillary molar  1.2 - 
Simple panoramic image of the jaw  - 110 
 
Legend:  
 
Ki– incident kerma  
PKA– product of kerma and surface area  
 
 
 
National diagnostic reference levels for diagnostic examination of adults in nuclear medicine  
for adult patients, regardless of gender, with a weight of 70  kg ± 5  kg 
Examination  
Radio -
nuclide  Substance, chemical form  Activity applied 
during one 
examination  
(MBq)  organ, system, illness  examination type, group  
bones  scintigraphy (whole -body, three -phase, 
SPECT1)) Tc-99m phosphates  800 
bone marrow  scintigraphy (whole body, SPE CT) Tc-99m nano -colloids  550 
brain  scintigraphy  dynamic  Tc-99m TcO 4, DTPA  600 
static, planar  Tc-99m TcO 4, DTPA  600 
SPECT  Tc-99m TcO 4, DTPA, HMPAO, ECD  800 
receptors  I-123 Iomazenil, IBZM  200 
glucose accumulation  F-18 FDG  400 
cisternography  In-111 DTPA  40 
Yb-169 EDTA  40 
thyroid gland  accumulation test  I-131 iodide  0.5 
scintigraphy  planar  Tc-99m TcO 4 200 
Tc-99m MIBI, DMSA (V)  400 
I-123 iodide  20 
I-131 iodide  7*) 
Tl-201 chloride  80 
whole -body  Tc-99m MIBI, DMSA (V)  800 
SPECT  I-131 iodide  300 
for thyroid cancer  Tl-201 chloride  100 
parathyroid gland  scintigraphy  planar  Tc-99m TcO4  200 
Tc-99m MIBI  750 
Tl-201 chloride  80 
adrenal glands  scintigraphy  planar  I-123 MIBG  200 
I-131 norcholesterol, MIBG  20 
lungs  scintigraphy  ventilation  Tc-99m aerosol, technegas  1000**)  
Kr-81m gas 6000  
SPECT  Tc-99m MAA, microspheres  300 
static perfusion  Tc-99m MAA, microspheres  200 
heart  myocardial perfusion  Tc-99m MIBI, tetrofosmin  1000***)  
scintigraphy  SPECT  Tl-201 chloride  110 
re-injection  Tl-201 chloride  40 
viability  F-18 FDG  500 
Tc-99m erythrocytes  800 
first flow scintigraphy  Tc-99m TcO 4, HSA  900 
lymphatic system  radionuclide lymphography  Tc-99m nano -colloid  150 
detection of sentinel nodes  Tc-99m nano-colloid  100 
veins  fibrinogen uptake  I-125  3 
radionuclide venography  Tc-99m MAA  200 296 
 
 Examination  
Radio -
nuclide  Substance, chemical form  Activity applied 
during one 
examination  
(MBq)  organ, system, illness  examination type, group  
(one limb)  Tc-99m DTPA  300 
radionuclide angiography  Tc-99m erythrocytes, TcO 4, DTPA, 
HSA  800 
scintigraphic thrombosis detection  Tc-99m platelets  500 
blood  blood volume and components  Tc-99m HSA  80 
I-131 HSA  6 
Cr-51 erythrocytes  6 
survival and local destruction of blood 
elements  Cr-51 erythrocytes, platelets  6 
In-111 platelets  10 
ferrokinetics  Fe-59 Fe (III) citrate  3 
spleen  scintigraphy  planar  Tc-99m altered erythrocytes  100 
SPECT  Tc-99m altered erythrocytes  200 
hepatobiliary system  scintigraphy  planar  Tc-99m colloids  150 
SPECT  Tc-99m colloids  300 
dynamic  Tc-99m IDA derivatives  250 
gastrointestinal tract  salivary gland scintigraphy  Tc-99m TcO 4 100 
scintigraphic motility of the oesophagus  Tc-99m colloids  70 
gastroesophageal reflux  Tc-99m colloids  50 
gastric evacuation  Tc-99m colloids  60 
scintigraphy of Meckel's diverticulum  Tc-99m TcO 4 500 
gastrointestinal bleeding scintigraphy 2) Tc-99m erythrocytes  700 
determining blood and protein losses in the 
GIT Cr-51 erythrocytes  4 
I-125 HSA  6 
I-131 HSA  6 
Schilling test  Co-57 monocyanocobalamin  1 
Co-58 monocyanocobalamin  1 
kidneys  simple renography  I-131 hippuran  1 
scintigrap hy planar  Tc-99m DMSA (III), gluconate  150 
SPECT  Tc-99m DMSA (III), gluconate  250 
dynamic  Tc-99m DTPA, MAG3, EC  250 
with evaluation of 
perfusion  Tc-99m DTPA, MAG3, EC  500 
stipulation of EPPL3), GFR4) Tc-99m MAG3, DTPA  20 
I-131 hippuran  0.5 
Cr-51 EDTA  3 
urinary  
bladder  radionuclide 
cystography  direct  Tc-99m TcO 4 50 
indirect  Tc-99m MAG3  200 
testes, scrotum  scintigraphy  Tc-99m TcO 4 600 
tumours  scintigraphy  
(planar, SPECT)  Tc-99m MIBI, depreotide, antibodies  800 
In-111 antibodies, pent etreotide  120 
Ga-67 citrate  300 
Tl-201 chloride  100 
I-123 MIBG  400 
I-131 MIBG  20 
F-18 FDG  750 
scintimammography (planar, SPECT)  Tc-99m MIBI, tetrofosmin, 
phosphonates  800 
inflammation  scintigraphy  
(planar, SPECT)  Tc-99m leukocytes, HIG  600 
Tc-99m antibodies  800 
In-111 leukocytes  30 
Ga-67 citrate  150 
 
Legend:  
 
*) only before therapy I -131 
**) activity in nebuliser; it is assumed that less than one tenth is deposited in the lungs  297 
 
 ***) summary value for a one -day protocol  
1) SPECT s ingle -photon emission computed tomography;  
2) GIT gastrointestinal tract, digestive tract;  
3) EPPL effective renal plasma flow;  
4) GFR glomerular filtration.  
 
CELEX:32013L0059  298 
 
 Annex  23 to Decree No .../….Sb.  
 
Criteria for categorising a radiological incide nt, procedures in case of occurrence, record 
archiving time, and reporting scope and deadlines  
 
1.The criteria for categorisation of a non -repeated radiological incident relating to one 
patient  
 Category  The criteria for the classification of a radiologica l incident into the appropriate category  
In radiotherapy  In nuclear medicine  In interventional 
radiology and 
radiodiagnostic 
medicine  
</A
> An event in which the patient experiences or can be 
expected to have a serious clinical manifestation that can 
lead to permanent injury or premature death.  
An event for which one can assume increased late effects 
of ionising radiation associated with excessive exposure 
of healthy tissue.  
In the case of teletherapy and brachytherapy, this 
primarily involves cases where  the total applied dose 
differs by more than 20  % of the prescribed total dose.  
In the case of stereotactic irradiation in radiation therapy, 
this mainly involves cases where the total applied dose 
differs by more than 10  % of the prescribed dose.   CT: 
 CVOL > 10 Gy  
 
Interventional 
radiology:  
 Kerma at the 
patient's input reference 
point > 15  Gy 
 PKA > 1 500 Gy×cm2 
B An event in which the patient experiences or can be 
expected to have a serious clinical manifestation that is 
not life -threatening but increases  the likelihood of an 
undesirable result, especially treatment complications or 
insufficient tumour control.  
In the case of teletherapy and brachytherapy, this 
primarily involves cases where the total applied dose 
differs by 10 - 20 % of the prescribed tot al dose.  
In the case of stereotactic irradiation in radiation therapy, 
this mainly involves cases where the total applied dose 
differs by 5 - 10 % of the prescribed dose.  Treatment 
application of nuclear 
medicine:  
Total applied activity 
differs by more tha n 
100 % from the 
prescribed activity.  
Diagnostic 
application of nuclear 
medicine:  
The applied activity is 
more than 20 times the 
prescribed activity.  
 CT: 
 CVOL > 3 Gy – if an 
eye is not in the primary 
beam  
 CVOL > 0.5  Gy – if an 
eye is in the primary 
beam  
 
Interventional 
radiology:  
 Kerma at the 
patient's input reference 
point > 5  Gy 
 PKA > 500  Gy×cm2 
C All other radiological incidents except for the above , 
for which there is little likelihood of clinical expression.  
These are especially  
 erroneous treatment c onditions, particularly a wedge 
or shielding, for one fraction;  
 the wrong side or localisation for one fraction; or  
 treatment without a written prescription or day record 
for one fraction.  All other radiological 
incidents except for 
the above.  All other ra diological 
incidents except for 
the above.  
These are especially  
 wrong patient;  
 wrong examined 
area; or  
 repeat exposure.  
 
Legend:  
 
PKA– product of kerma and surface area  299 
 
 CVOL– volumetric kerma index for computed tomography  
 
 300 
 
 2.The criteria for categorisati on of repeated radiological incidents relating to one patient  
 
Reclassification  Medical irradiation modality  The number of repeated 
radiological incidents for one 
patient  
From category C to category B  Radiation therapy  
Once or more  Nuclear medicine  
Interventional radiology  
Computed tomography  
Skiascopy  
Dental computed tomography  
Other radiodiagnostics  Three times and more  
From category B to category A  Radiation therapy  
Once or more  Nuclear medicine  
Interventional radiology  
Compute d tomography  
Skiascopy  
Dental computed tomography  
Other radiodiagnostics  Three times or more  
From category C to category A  Radiation therapy  
Twice or more  Nuclear medicine  
Interventional radiology  
Computed tomography  
Skiascopy  Three ti mes or more  Dental computed tomography  
Other radiodiagnostics  Nine times or more  
 
Legend:  
 
In the event that radiological incidents repeatedly affect one patient, they are classified into a higher category 
according to the rules in the table.  
 
 301 
 
 3.The  criteria for categorisation of repeated radiological incidents involving several 
patients  
 
 
Legend:  
 
If radiological incidents repeatedly affect multiple patients, they are classified into a higher category according to 
the rules in the table.  
* The number of affected patients is the number of patient s that the cause of the radiological incident has affected, 
i.e. the number of patients who have been erroneously irradiated due to one error or a set of errors.  
 
 Reclassification  Medical irradiation modality  Number of patients affected*  
From category C to 
category B  Brachytherapy  
Stereotactic irradiation in radiotherapy  3 or more patients in one month  
Teletheraphy  10 or more patients in one month  Treatment applications of nuclear medicine:  
Diagnostic applications of nuclear medicine:  20 or more patients in one month  
Interventional radiology  10 or more patients in on e month  Computed tomography  
Skiascopy  
Dental computed tomography  20 or more patients in one month  
Mammography  100 or more patients in one month  
Other radiodiagnostics  200 or more patients in one month  
From category B to 
category A  Brachytherapy  
Stereotactic irradiation in radiotherapy  3 or more patients in one month  
Teletheraphy  10 or more patients in one month  Treatment applications of nuclear medicine:  
Diagnostic applications of nuclear medicine:  20 or more patients in one month  
Interve ntional radiology  10 or more patients in one month  Computed tomography  
Skiascopy  
Dental computed tomography  20 or more patients in one month  
Mammography  100 or more patients in one month  
Other radiodiagnostics  200 or more patients in one month  
From category C to 
category A  Brachytherapy  
Stereotactic irradiation in radiotherapy  6 or more patients in one month  
Teletheraphy  20 or more patients in one month  Treatment applications of nuclear medicine:  
Diagnostic applications of nuclear medicine:  100 or more patients in one month  
Interventional radiology  20 or more patients in one month  Computed tomography  
Skiascopy  
Dental computed tomography  100 or more patients in one month  
Mammography  500 or more patients in one month  
Other radiodiag nostics  1 000 or more patients in one 
month  302 
 
 4.Deadlines for reporting serious radiological incidents  
 
1. The Office must be informed in the  event of  
1.1. a category A radiological incident  
1.1.1.  immediately upon discovering that a radiological incident has occurred, of all the 
facts known about it;  
1.1.2.  immediately upon determining all other facts within the scope of the radiological 
incident's investigation , especially after determining the facts listed in Part  5, of the 
determined facts;  
1.1.3.  immediately upon implementing all measures to mitigate the consequences of the 
radiological incident as much as possible, of the implemented measures;  
1.1.4.  immediately upon impl ementing all measures to prevent the occurrence of a similar 
radiological incident in the future, of the implemented measures; and  
1.1.5.  in full, pursuant to Part  5, within one month from discovering that a category A 
radiological incident has occurred in radiot herapy;  
1.2. a category B radiological incident  
1.2.1.  in radiotherapy, in full, pursuant to Part  5 within one month from discovering that a 
category A radiological incident has occurred;  
1.2.2.  in interventional radiology, in radio diagnostics, or in nuclear medicine, in fu ll, 
pursuant to Part  5, within three months from discovering that a radiological incident 
has occurred.  
2. If tissue reactions caused by erroneous irradiation may adversely affect the health of the 
patient, or if due to radiological incidents it is necessary to make a change in treatment 
procedure, the patient or his or her legal representative, the indicating doctor, and the 
application technician, must be informed in the event of  
2.1. a category A radiological incident  
2.1.1.  immediately upon discovering that a radiolog ical incident has occurred, of all the 
facts known about it;  
2.1.2.  immediately upon determining all other facts listed in Part  5 within the scope of the 
radiological incident's investigation, of the determined facts;  
2.1.3.  immediately upon implementing all measures to  mitigate the consequences of the 
radiological incident as much as possible, of the implemented measures;  
2.1.4.  immediately upon implementing all measures to prevent the occurrence of a similar 
radiological incident in the future, of the implemented measures; an d 
2.1.5.  in full, pursuant to Part  5, within one month from discovering that a category A 
radiological incident has occurred in radiotherapy;  
2.2. a category B radiological incident, in full, pursuant to Part  5 within three months of 
discovering that a radiological in cident has occurred;  
 
 303 
 
 5.The scope of reporting serious radiological incidents  
 
1. The Office must be informed to the following extent by the deadlines pursuant to Part  4: 
1.1. in the event of a category A radiological incident  
1.1.1.  the date and time the radiological i ncident was discovered, and of its occurrence, if 
known;  
1.1.2.  the nature, scope and severity of the radiological incident;  
1.1.3.  the possible impact of the radiological incident;  
1.1.4.  all measures implemented to mitigate the consequences of the radiological incident 
as mu ch as possible;  
1.1.5.  all other facts determined during the investigation of the radiological incident that 
affect its nature, scope, impact and severity;  
1.1.6.  further steps planned in the investigation; and  
1.1.7.  all measures implemented to prevent the occurrence of a sim ilar radiological 
incident in the future;  
1.2. in the event of a category B radiological incident  
1.2.1.  the date the radiological incident was discovered, and of its occurrence, if known;  
1.2.2.  the nature, scope and severity of the radiological incident;  
1.2.3.  the possible impac t of the radiological incident;  
1.2.4.  all measures implemented to mitigate the consequences of the radiological incident 
as much as possible;  
1.2.5.  all other facts determined during the investigation of the radiological incident that 
affect its nature, scope, impact a nd severity; and  
1.2.6.  all measures implemented to prevent the occurrence of a similar radiological 
incident in the future.  
2. The patient or his or her legal representative, the indicating doctor, and application technician 
must be informed by the deadlines pursua nt to Part  4 to the following extent:  
2.1. in the event of a category A radiological incident  
2.1.1.  the date and time the radiological incident was discovered, and of its occurrence, if 
known;  
2.1.2.  the nature, scope and severity of the radiological incident;  
2.1.3.  the possible impact of the radiological incident;  
2.1.4.  all measures implemented to mitigate the consequences of the radiological incident 
as much as possible;  
2.1.5.  all other facts determined during the investigation of the radiological incident that 
affect the patient's state of  health and treatment; and  
2.1.6.  further steps planned in the investigation of the radiological incident;  
2.2. in the event of a category B radiological incident  
2.2.1.  the date the radiological incident was discovered, and of its occurrence, if known;  
2.2.2.  the nature, scope and  severity of the radiological incident;  
2.2.3.  the possible impact of the radiological incident;  
2.2.4.  all measures implemented to mitigate the consequences of the radiological incident 
as much as possible; and  
2.2.5.  all other facts determined during the investigation of the  radiological incident that 
affect the patient's state of health and treatment.  304 
 
 3. Summary information about a radiological incident in radiation therapy, regarding which, 
pursuant to Part  4 points  1.1.5, 1.2.1, 2.1.5, and 2.2.1, the Office is informed, and t hat the 
permit holder draws up and maintains pursuant to Part  7 point  1.4, must contain:  
3.1. the date and time the radiological incident occurred, its duration, and the date and time it 
was discovered;  
3.2. a description of the radiological incident, its scope, sev erity, and category;  
3.3. the causes of the radiological event and all other facts determined during the 
investigation of the radiological incident that affect its nature, scope, impact and 
severity;  
3.4. clinical manifestations due to the radiological incident;  
3.5. an estimate of the potential long -term consequences of the radiological incident;  
3.6. measures implemented to prevent clinical consequences of the radiological incident;  
3.7. immediate measures to prevent the radiological incident from reoccurring; and  
3.8. preventive syst emic measures to prevent the radiological incident from reoccurring.  
 
 
6.The archiving period for records of radiological incidents and cases where a radiological 
incident could have occurred if its causes had not been discovered in time and eliminated  
 
Records of radiological incidents and cases where a radiological incident could have occurred if 
its causes had not been discovered in time and eliminated must be archived  
1. for category A radiological incidents, for 30 years from the discovery of the radiolog ical 
incident;  
2. for category B radiological incidents, for 10 years from the discovery of the radiological 
incident;  
3. for category C radiological incidents, for 10 years from the discovery of the radiological 
incident; and  
4. for cases where a radiological inci dent could have occurred if its causes had not been 
discovered in time and eliminated, for 5 years from their discovery.  
 
 
7.Procedures in the event of a radiological incident or if a radiological incident could have 
occurred if its causes had not been dis covered in time and eliminated  
 
1. In radiotherapy it is necessary,  
1.1. during a category A or B radiological incident,  
1.1.1.  to immediately commence dosimetric and clinical assessment of the incident;  
1.1.2.  to implement measures to limit clinical consequences of the inciden t for the 
afflicted patient, especially interruption of treatment according to the original 
treatment plan and recalculation of the treatment plan and related activities, 
including drawing up a new treatment plan, and simulation and verification of the 
plan if the original plan needs to be modified or planned entirely anew;  
1.1.3.  to implement immediate measures that should ensure radiation protection for other 
patients, including verification of whether the same radiological incident cause is 
not present in other  cases;  305 
 
 1.1.4.  within the scope of investigating the radiological incident, to appoint investigation 
groups, define and analyse the problem, and analyse the root causes, progress and 
consequences of the radiological incident;  
1.1.5.  to identify and implement systemic pr eventive measures;  
1.1.6.  to draw up a summary of information on the radiological incident pursuant to Part  5 
point  3 and send it to the Office within one month of discovering this incident; and  
1.1.7.  to archive the summary of information on the radiological incident p ursuant to 
Part 5 point  3 for the duration specified in Part6 and in the patient's health records;  
1.2. in the event of a category A radiological incident, if tissue reactions caused by erroneous 
irradiation may adversely affect the health of the patient, or if  due to the radiological 
incidents it is necessary to make a change in treatment procedure, the patient or his or 
her legal representative, the application technician, and the indicating doctor must be 
informed within one month of discovery of the radiolog ical incident to the extent 
specified in Part  5 point  2.1; 
1.3. in the event of a category B radiological incident, if tissue reactions caused by erroneous 
irradiation can adversely affect the health of the patient, or if due to the radiological 
incidents it is  necessary to make a change in treatment procedure, the patient or his or 
her legal representative, the application technician, and the indicating doctor must be 
informed within three months of discovery of the radiological incident to the extent 
specified  in Part  5 point  2.2; 
1.4. in the event of a category C radiological incident  
1.4.1.  within the scope of investigating the radiological incident, to appoint investigation 
groups, define and analyse the problem, and analyse the root causes, progress, and 
consequences o f the radiological incident, and dosimetric and clinical assessment of 
the radiological incident;  
1.4.2.  to implement measures to limit the clinical consequences of the incident for the 
afflicted patient;  
1.4.3.  if needed, to modify the treatment plan;  
1.4.4.  to identify and i mplement systemic preventive measures;  
1.4.5.  to draw up a summary of information on the radiological incident pursuant to Part  5 
point  3 and send it to the Office within one month of discovering this incident; and  
1.4.6.  to archive summary information on the radiologic al incident to the extent specified 
in Part  5 point  3; 
1.5. in the event that a radiological incident could have occurred if its causes had not been 
discovered in time and eliminated,  
1.5.1.  immediately after discovering that a radiological incident could occur, to ta ke all 
measures to prevent it;  
1.5.2.  to investigate and find the root causes and contributing factors;  
1.5.3.  to create and file a record of this case; and  
1.5.4.  to implement preventive measures to prevent the occurrence of similar cases in the 
future.  
2. In nuclear medicine, i nterventional radiology and radiodiagnostic medicine, it is necessary  
2.1. in the event of a radiological incident, in a manner and with timing corresponding to the 
severity of the radiological incident and its possible consequences,  
2.1.1.  immediately after discoveri ng that a radiological incident occurred, to implement 
measures to prevent an increase in the undesirable dose received by the patient, as 306 
 
 well as measures to prevent this radiological incident repeating in the case of a 
different patient;  
2.1.2.  to subsequently collect all available data on the radiological incident;  
2.1.3.  to take timely action to mitigate the impact of the radiological incident, where 
possible;  
2.1.4.  to determine the causes of the radiological incident and to change procedures so 
that the incident cannot be  repeated;  
2.1.5.  to inform the Office, the patient or his or her legal representative, the application 
technician, and the indicating doctor of the radiological incident pursuant to Parts  4 
and 5; and  
2.1.6.  to archive records of the radiological incident, records of i ts investigation, and of 
implemented measures, pursuant to Part  6; 
2.2. in the event that a radiological incident could have occurred if its causes had not been 
discovered in time and eliminated,  
2.2.1.  immediately after discovering that a radiological incident could occur, to take all 
measures to prevent it;  
2.2.2.  to subsequently determine the reasons why the radiological incident almost 
occurred, to verify whether standard procedures ensure the prevention of such a 
radiological incident, and if not, to change these procedu res so that the radiological 
incident cannot occur in the future;  
2.2.3.  to archive all records of these cases, records of their investigation, and of 
implemented measures.  
CELEX:32013L0059  307 
 
 Annex  24 to Decree No …/….Sb.  
 
Information on health services during whic h ionising radiation was used and that were 
reported by a health services provider, and paid for by a health insurance company, 
provided to the Office by the health insurance company  
 
1. Information must be provided to the Office in the following format:  
1.1. delimited ASCII text;  
1.2. the field separator is a semicolon;  
1.3. text is surrounded by the " " symbol; and  
1.4. the decimal symbol is the comma.  
2. Information must be provided to the Office in the following extent:  
2.1. designation of the activity pursuant to the decree on stipu lation of the values of a point, 
fees paid for services, and regulatory restrictions;  
2.2. designation of specialisation pursuant to the decree on stipulation of the values of a 
point, fees paid for services, and regulatory restrictions;  
2.3. the ID number of the he alth services provider;  
2.4. the ID number of the healthcare facility;  
2.5. the district in which the healthcare facility is located;  
2.6. the patient's gender and date of birth;  
2.7. a unique patient identifier for all provided data, created by the health insurance 
company;  
2.8. the date of examination; and  
2.9. the applied amount of activity in the case of administration of radiopharmaceuticals.  308 
 
 Annex  25 to Decree No …/….Sb.  
 
Conditions for classifying workplaces located on an underground or ground floor of a 
building as workplaces wi th potentially increased exposure to radon  
 
A. Conditions for classifying workplaces located on an underground or ground floor of a 
building as workplaces with potentially increased exposure to radon are as follows:  
1. the workplace is located on an undergrou nd or ground floor of the building, except for  
1.1. a building that was built after 28February1991;  
1.2. a building situated in the landscape so that all its perimeter structures are separated from 
the subsoil by an air gap where air can circulate freely;  
1.3. workplaces  or buildings in which anti -radon measures have been implemented, and their 
sufficient efficacy confirmed by measurement;  
1.4. a workplace that is a parking lot or garage; or  
1.5. a workplace with a sub -cellar under its entire floor plan and without direct contact w ith a 
basement floor;  
2. for a person who performs an activity during which a workplace is operated with possible 
increased exposure to radon, a natural person performs the work; and  
3. a workplace on a basement or ground floor of a building is located in a muni cipality where 
the likelihood of exceeding the reference level pursuant to §  96(1) is greater than 30  %.The 
following municipalities comply with this condition:  
 
REGION  DISTRICT  MUNICIPALITY  
THE CITYOF PRAGUE  PRAGUE:  KOLOVRATY, LYSOLAJE, ŠEBEROV  
THE CENT RAL 
BOHEMIAN REGION  BENEŠOV  BENEŠOV, BÍLKOVICE, BUKOVANY, 
BYSTŘICE, ČAKOV, DIVIŠOV, 
HEŘMANIČKY, CHOTÝŠANY, 
KŘEČOVICE, LITICHOVICE, MARŠOVICE, 
MRAČ, NEVEKLOV, OLBRAMOVICE, 
OSTŘEDEK, POPOVICE, POSTUPICE, 
SMILKOV, STRANNÝ, STRUHAŘOV, 
STŘEZIMÍŘ, TEPLÝŠOVICE, T ISEM, 
TOMICE, TŘEBEŠICE, VÁCLAVICE, 
VELIŠ, VOJKOV, VOTICE, VRCHOTOVY 
JANOVICE  
BEROUN  BYKOŠ, KONĚPRUSY, KORNO, 
LIBOMYŠL, MÁLKOV, MĚŇANY, 
SUCHOMASTY, TMAŇ  
KLADNO  JEMNÍKY, MALÉ PŘÍTOČNO, 
TŘEBICHOVICE  
KOLÍN  HRADEŠÍN, MASOJEDY, PŘIŠIMASY  
PRAGUE - EAST  BABICE, BŘEZÍ, KLECANY, LOUŇOVICE, 
ŠTÍHLICE, TEHOVEC, VYŽLOVKA  
PRAGUE - WEST  BOJANOVICE, BRATŘÍNOV, ČÍČOVICE, 
PETROV, SVRKYNĚ, ŠTĚCHOVICE, 
TRNOVÁ  309 
 
 PŘÍBRAM  BEZDĚKOV POD TŘEMŠÍNEM, 
BOROTICE, ČÍM, DALEKÉ DUŠNÍKY, 
DOLNÍ HBITY, DRAHENICE, DRÁSOV, 
DUBENEC, DUB LOVICE, HÁJE, 
HLUBYNĚ, HORČÁPSKO, HŘIMĚŽDICE, 
HUDČICE, HVOŽĎANY, CHOTILSKO, 
CHRÁST, CHRAŠTICE, JABLONNÁ, 
JESENICE, KAMÝK NAD VLTAVOU, 
KLUČENICE, KŇOVICE, KORKYNĚ, 
KOSOVA HORA, KOUPĚ, KOZÁROVICE, 
KRÁSNÁ HORA NAD VLTAVOU, 
KŘEPENICE, LÁZ, LEŠETICE, LHOTA U 
PŘÍBRAMĚ, MALÁ HRAŠTICE, MILEŠOV, 
MODŘOVICE, NALŽOVICE, NARYSOV, 
NEČÍN, NEDRAHOVICE, NECHVALICE, 
NOVÁ VES POD PLEŠÍ, NOVÉ DVORY, 
OBORY, OBOŘIŠTĚ, OSEČANY, OSTROV, 
OUBĚNICE, PEČICE, PETROVICE, 
POČEPICE, PROSENICKÁ LHOTA, 
PŘÍBRAM, PŘÍČOVY, RADĚTICE, RADÍČ, 
ROŽ MITÁL POD TŘEMŠÍNEM, RYBNÍKY, 
SEDLČANY, SEDLEC -PRČICE, 
SMOLOTELY, STARÁ HUŤ, 
STAROSEDLSKÝ HRÁDEK, SVATÝ JAN, 
ŠTĚTKOVICE, TĚCHAŘOVICE, TŘEBSKO, 
VELKÁ LEČICE, VĚŠÍN, VIŠŇOVÁ, 
VOLENICE, VRANČICE, VRANOVICE, 
VŠEVILY, VYSOKÝ CHLUMEC, 
ZALUŽANY, ZDUCHOVICE, ŽUPAN OVICE  
RAKOVNÍK  VELKÁ CHMELIŠTNÁ  
THE SOUTH BOHEMIAN 
REGION  ČESKÉ BUDĚJOVICE  HRADCE, SLAVČE, VITÍN, ŽÁR  
ČESKÝ KRUMLOV  BESEDNICE, POHORSKÁ VES, SOBĚNOV  
JINDŘICHŮV HRADEC  BEDNÁREC, ČESKÝ RUDOLEC, ČÍMĚŘ, 
HEŘMANEČ, HORNÍ NĚMČICE, KUNŽAK, 
LODHÉŘOV, STARÉ M ĚSTO POD 
LANDŠTEJNEM, STRMILOV, STUDENÁ  
PÍSEK  ALBRECHTICE NAD VLTAVOU, BOUDY, 
BOŽETICE, BRANICE, CERHONICE, 
ČIMELICE, ČÍŽOVÁ, DOBEV, DRHOVLE, 
HOROSEDLY, HRAZANY, HREJKOVICE, 
CHYŠKY, JICKOVICE, KLUKY, KOSTELEC 
NAD VLTAVOU, KOVÁŘOV, KOŽLÍ, 
KRÁLOVA LHOTA, K UČEŘ, KVĚTOV, 
LETY, MILEVSKO, MIROTICE, MIROVICE, 
MINICE, MIŠOVICE, MYSLÍN, NERESTCE, 
NEVĚZICE, OKROUHLÁ, ORLÍK NAD 
VLTAVOU, OSEK, OSLOV, OSTROVEC, 
PASEKY, PROBULOV, PŘEBOROV, 
PŘEDOTICE, PŘEŠTĚNICE, RAKOVICE, 
SMETANOVA LHOTA, STEHLOVICE, 
TÁLÍN, VARVAŽOV, V LKSICE, 
VOJNÍKOV, VRÁŽ, VRCOVICE, 
ZBELÍTOV, ZHOŘ, ZVÍKOVSKÉ 310 
 
 PODHRADÍ  
PRACHATICE  BOHUNICE, BOŠICE, BUŠANOVICE, 
LČOVICE, RADHOSTICE, STACHY, 
STOŽEC, STRÁŽNÝ, SVATÁ MAŘÍ, 
ŠUMAVSKÉ HOŠTICE, TVRZICE, 
ÚJEZDEC, VACOV, VRBICE, VIMPERK, 
VLACHOVO BŘEZÍ, ZÁLEZLY, Ž ELNAVA  
STRAKONICE  BĚLČICE, BEZDĚDOVICE, BLATNÁ, 
BRATRONICE, BŘEZÍ, BUZICE, 
ČEČELOVICE, ČEPŘOVICE, ČESTICE, 
DOUBRAVICE, DRÁŽOV, DŘEŠÍN, 
HAJANY, HÁJEK, HLUPÍN, HORNOSÍN, 
HOSLOVICE, CHOBOT, CHLUM, 
CHRÁŠŤOVICE, JINÍN, KADOV, 
KOCELOVICE, KRAJNÍČKO, KRTY -
HRADE C, KUŘIMANY, LAŽÁNKY, 
LAŽANY, LIBĚTICE, LNÁŘE, LOM, 
MAČKOV, MEČICHOV, MĚKYNEC, 
MILOŇOVICE, MNICHOV, MYŠTICE, 
NEBŘEHOVICE, NĚMČICE, NĚMĚTICE, 
NIHOŠOVICE, NIŠOVICE, NOVÁ VES, 
PŘEDMÍŘ, PŘEDNÍ ZBOROVICE, 
PŘEDSLAVICE, PŘECHOVICE, 
PŘEŠŤOVICE, SEDLICE, SOUSEDOVIC E, 
STOŽICE, STRAŠICE, STRUNKOVICE NAD 
VOLYŇKOU, STŘELSKÉ HOŠTICE, 
ŠKVOŘETICE, TCHOŘOVICE, 
TŘEBOHOSTICE, TŘEŠOVICE, ÚLEHLE, 
UZENICE, UZENIČKY, VACOVICE, VELKÁ 
TURNÁ, VOLYNĚ, ZÁBOŘÍ  
TÁBOR  BOROTÍN, DRAŽIČKY, JISTEBNICE, 
NADĚJKOV, OPAŘANY, RADKOV, 
SVRABOV  
THE PLZEŇ REGION  DOMAŽLICE  BABYLON, ČESKÁ KUBICE, CHODOV, 
KANIČKY, MEZHOLEZY, NOVÁ VES, 
TRHANOV, ÚSILOV  
KLATOVY  BĚHAŘOV, BEZDĚKOV, BOLEŠINY, 
BŘEŽANY, BUKOVNÍK, ČERNÍKOV, 
ČÍHAŇ, ČÍMICE, DEŠENICE, DLAŽOV, 
DOBRŠÍN, DOLANY, DOMORAZ, 
FRYMBURK, HNAČOV, HRADEŠIC E, 
HRÁDEK, CHANOVICE, CHLISTOV, 
CHUDENICE, JANOVICE NAD ÚHLAVOU, 
KAŠPERSKÉ HORY, KLATOVY, KOLINEC, 
KOVČÍN, KVÁŠŇOVICE, LOMEC, MALÝ 
BOR, MAŇOVICE, MĚČÍN, MOKROSUKY, 
MYSLÍV, MYSLOVICE, NALŽOVSKÉ 
HORY, NEZAMYSLICE, OLŠANY, 
OSTŘETICE, PAČEJOV, POLEŇ, 
PŘEDSLAV,  SLATINA, SOBĚŠICE, 
STRÁŽOV, SVÉRADICE, TÝNEC, TUŽICE, 
VELKÝ BOR, ZAVLEKOV, ZBOROVY, 
ŽICHOVICE  311 
 
 PLZEŇ - CITY  LHŮTA  
PLZEŇ - SOUTH  ČMELÍNY, DOLNÍ LUKAVICE, DRAHKOV, 
HORNÍ LUKAVICE, HORŠICE, HRADEC, 
HRADIŠTĚ, CHOCENICE, JAROV, 
KASEJOVICE, KBEL, KLÁŠTER, MÍ ŠOV, 
MOHELNICE, NEKVASOVY, NEPOMUK, 
NETUNICE, NEURAZY, NEZDŘEV, NOVÉ 
MITROVICE, OSELCE, PTENÍN, PRÁDLO, 
SRBY, TŘEBČICE, TÝNIŠTĚ, ÚNĚTICE, 
VLČTEJN, VRČEŇ, ŽDÍREC, ŽINKOVY  
PLZEŇ - NORTH  BOHY, DOLANY, LOCHOUSICE  
ROKYCANY  BŘEZINA, KAMENEC, KAKEJCOV  
TACHO V BROD NAD TICHOU, HOŠŤKA, LESNÁ, 
STARÉ SEDLO, TISOVÁ, ZADNÍ CHODOV  
THE KARLOVY VARY 
REGION  CHEB  DOLNÍ ŽANDOV, KRÁSNÁ, 
KŘIŽOVATKA, MILÍKOV, PLESNÁ, 
POUSTKA, PRAMENY, SKALNÁ, STARÁ 
VODA, VALY, VOJTANOV  
KARLOVY VARY  ABERTAMY, ANDĚLSKÁ HORA, BOŽÍ 
DAR, BŘEZ OVÁ, ČERNAVA, 
DĚPOLTOVICE, HORNÍ BLATNÁ, 
HROZNĚTÍN, JÁCHYMOV, KOLOVÁ, 
MERKLÍN, NEJDEK, NOVÉ HAMRY, 
PERNINK, PILA, POTŮČKY, SMOLNÉ 
PECE, STANOVICE, STRUŽNÁ, VYSOKÁ 
PEC, TEPLIČKA  
SOKOLOV  HORNÍ SLAVKOV, JINDŘICHOVICE, 
KRASLICE, KRÁSNO, KYNŠPERK NAD 
OHŘÍ, LO KET, PŘEBUZ, ROTAVA, 
ŠINDELOVÁ  
THE ÚSTÍ REGION  CHOMUTOV  KALEK, LOUČNÁ  
MOST  KLÍNY  
TEPLICE  DUBÍ, HROB, JENÍKOV, PROBOŠTOV  
THE LIBEREC REGION  JABLONEC NAD NISOU  ALBRECHTICE V JIZERSKÝCH HORÁCH, 
DALEŠICE, DESNÁ, JANOV NAD NISOU, 
JOSEFŮV DŮL, KOŘENOV, LUČ ANY NAD 
NISOU, MARŠOVICE, NOVÁ VES NAD 
NISOU, RÁDLO, SMRŽOVKA  
LIBEREC  BÍLÝ POTOK, HEJNICE, LIBEREC, 
OLDŘICHOV V HÁJÍCH, STRÁŽ NAD 
NISOU  
SEMILY  HARRACHOV, PASEKY NAD JIZEROU  
THE HRADEC KRÁLOVÉ 
REGION  RYCHNOV NAD 
KNĚŽNOU  ZDOBNICE  
TRUTNOV  KLÁŠTERSKÁ LH OTA, KUNČICE NAD 
LABEM, MLADÉ BUKY, PEC POD 
SNĚŽKOU, VRCHLABÍ  
THE PARDUBICE REGION  CHRUDIM  BÍTOVANY, BOŘICE, CTĚTÍN, 
ČANKOVICE, DOLNÍ BEZDĚKOV, 312 
 
 HLINSKO, HONBICE, HROCHŮV TÝNEC, 
JENÍKOV, JENIŠOVICE, LEŠTINKA, 
NABOČANY, POKŘIKOV, PROSETÍN, 
PŘESTAVLKY, RANÁ,  STUDNICE, 
TRHOVÁ KAMENICE, TROJOVICE, 
ÚHŘETICE, VÍTANOV, VOJTĚCHOV, 
VORTOVÁ, VYŽICE, ZÁJEZDEC  
PARDUBICE  HOLOTÍN  
SVITAVY  BŘEZINY, HARTINKOV  
ÚSTÍ NAD ORLICÍ  PASTVINY  
THE VYSOČINA REGION  HAVLÍČKŮV BROD  BOJIŠTĚ, DOLNÍ MĚSTO, DOLNÍ 
SOKOLOVEC, HORNÍ PASE KA, 
KAMENNÁ LHOTA, KOUTY, LIPNICE 
NAD SÁZAVOU, POHLED, RUŠINOV, 
TRPIŠOVICE, ÚSOBÍ  
JIHLAVA  BÍLÝ KÁMEN, BRTNICE, CEJLE, DUDÍN, 
HUBENOV, JERSÍN, JEŽENÁ, KALIŠTĚ, 
KAMENICE, KLATOVEC, KNÍNICE, 
MILÍČOV, MIROŠOV, MRÁKOTÍN, OLŠÍ, 
OPATOV, PUKLICE, ŘÍDELOV, SMRČNÁ , 
ŠIMANOV, VĚTRNÝ JENÍKOV, ZBILIDY  
PELHŘIMOV  HOJANOVICE, JANKOV, KALIŠTĚ, 
KOBEROVICE, NOVÝ RYCHNOV, 
PROSEČ, ÚSTRAŠÍN, VESELÁ  
TŘEBÍČ  BENETICE, BOCHOVICE, BRANSOUZE, 
BUDIŠOV, ČIKOV, ČÍMĚŘ, DOLNÍ 
VILÉMOVICE, HLUBOKÉ, HODOV, HORNÍ 
HEŘMANICE, HORNÍ ÚJEZD, HORNÍ 
VILÉMOVICE, HROZNATÍN, JASENICE, 
KAMENNÁ, KLUČOV, KOJATÍN, 
KOŽICHOVICE, KRALICE NAD OSLAVOU, 
LIPNÍK, MIKULOVICE, NALOUČANY, 
NÁRAMEČ , NOVÝ TELEČKOV, 
OCMANICE, OKŘEŠICE, OSTAŠOV, 
PETRŮVKY, POZĎATÍN, PŘECKOV, 
PYŠEL, RAPOTICE, ROHY, RUDÍKOV, 
SLAVIČKY, SMRK, STAŘEČ, STŘÍTEŽ, 
STUDNICE, SVATOSLAV, TRNAVA, 
TŘEBÍČ, VALDÍKOV, VLADISLAV, 
VLČATÍN, ZAHRÁDKA  
ŽĎÁR NAD SÁZAVOU  BALINY, BŘEZÍ, BŘEZSK É, DAŇKOVICE, 
DOLNÍ HEŘMANICE, HAMRY NAD 
SÁZAVOU, HORNÍ RADSLAVICE, 
CHLUMEK, JABLOŇOV, JIMRAMOV, 
KADOV, KARLOV, KRÁSNÉ, KŘÍDLA, 
KŘIŽÁNKY, MĚŘÍN, MEZIŘÍČKO, NOVÉ 
SADY, NOVÝ JIMRAMOV, OSLAVIČKA, 
OŘECHOV, OSLAVICE, OSOVÉ, OTÍN, 
PAVLÍNOV, PETRÁVEČ, PÍSEČNÉ, RU DA, 
SÁZAVA, SKŘINÁŘOV, SNĚŽNÉ, 
STRÁNECKÁ ZHOŘ, TASOV, UHŘÍNOV, 
VĚCHNOV, VELKÁ BÍTEŠ, VELKÉ 313 
 
 MEZIŘÍČÍ, VÍR, VLKOV, ZÁBLATÍ  
THE SOUTH MORAVIAN 
REGION  BLANSKO  BUKOVINA, HOLŠTEJN, KRASOVÁ, 
NĚMČICE, SLOUP, SUDICE, VELENOV, 
ŽĎÁRNÁ  
BRNO - VENKOV  BRANÍŠKOV, HORN Í LOUČKY, KATOV, 
KETKOVICE, KUŘIMSKÁ NOVÁ VES, 
LESNÍ HLUBOKÉ, LOMNIČKA, LUBNÉ, 
ŘIKONÍN, STANOVIŠTĚ, TIŠNOVSKÁ 
NOVÁ VES, ÚJEZD U TIŠNOVA, 
VŠECHOVICE, ŽĎÁREC  
VYŠKOV  OLŠANY, PODOMÍ  
ZNOJMO  BOSKOVŠTEJN, CHVALATICE, 
PETROVICE, SKALICE, SLATINA  
THE OLOMOUC R EGION  JESENÍK  KOBYLÁ NAD VIDNAVKOU, VELKÁ 
KRAŠ  
OLOMOUC  BOUZOV, DASKABÁT, LUKÁ, TĚŠETICE, 
VELKÝ ÚJEZD, STRUKOV  
PROSTĚJOV  BOHUSLAVICE, BRODEK U KONICE, 
BŘEZSKO, BUDĚTSKO, DZBEL, HAČKY, 
JESENEC, KONICE, LIPOVÁ, LUDMÍROV, 
OCHOZ, OTINOVES, POLOMÍ, RAKŮVKA, 
ROZSTÁNÍ, SKŘÍPOV, STRAŽISKO, 
SUCHDOL, ŠUBÍŘOV, VINCENCOV  
PŘEROV  LAZNÍČKY, POLKOVICE, STŘÍTEŽ NAD 
LUDINOU  
ŠUMPERK  BLUDOV, BOHDÍKOV, BRNÍČKO, 
KOPŘIVNÁ, PALONÍN, POSTŘELMŮVEK  
THE MORAVIAN -
SILESIAN REGION  BRUNTÁL  LESKOVEC NAD MORAVICÍ, ŠIROKÁ 
NIVA, ZÁTOR  
OPAVA  NOVÉ LUBLICE  
 
B. A condition indicating a possible increased exposure to radon in the workplace located in the 
basement or first floor of a building are also the following circumstances:  
1. for a person who performs an activity during which a workpl ace is operated with possible 
increased exposure to radon, a natural person performs the work and  
2. the value of 300  Bq/m3 radon activity concentration has been found to have been exceeded in 
the indoor air of the workplace.  
CELEX:32013L0059  314 
 
 Annex  26 to Decr ee No …/….Sb.  
 
Method of evaluating results to determine the radon index of a property  
 
1. Determination based on the radon potential of a property  
 
 
 
NÍZKÝ RADONOVÝ INDEX POZEMKU  LOW PROPERTY RADON INDEX  
STŘEDNÍ RADONOVÝ INDEX 
POZEMKU  MEDIUM PROPERTY RADON INDEX  
VYSOKÝ RADONOVÝ INDEX 
POZEMKU  HIGH PROPERTY RADON INDEX  
 
Legend:  
 
RP– the radon potential of a property  
k (m2)– a statistical parameter, usually third quartile, of the set of measured values of gas permeability,  
cA (kBq/ m3)– a statistical parameter, usually third quartile, of the set of measured values of radon activity 
concentration in soil air  
 
CELEX:32013L0059  
 315 
 
 2. Determination when assessing gas permeability based on professional experience and 
knowledge  
 
Property 
radon index  Radon concentration in soil air  
(kBq/m3) 
Low cA < 30 cA < 20 cA < 10 
Medium  30  cA 100 20  cA 70 10  cA 30 
High  cA 100 cA 70 cA 30 
 Low Medium  High  
 Gas permeability of soils  
 
Legend:  
 
cA (kBq/m3) – a statistical parameter, usually thi rd quartile, of the set of measured values of radon activity 
concentration in soil air  316 
 
 Annex  27 to Decree No …/….Sb.  
 
Activity concentration of radon and natural radionuclide content in drinking water  
 
 
Maximum permissible value of radon activity concentra tion in drinking water for public 
use and for making bottled water available on the market;  
 
 Maximum permissible value  
Rn-222 300 Bq/l 
 
 
The reference level for natural radionuclide content in drinking water for public use and 
for making bottled water a vailable on the market;  
 
 Reference level  
Rn-222 100 Bq/l 
Indicative dose  0.1 mSv/year  
 
 
Investigation levels of total alpha activity concentration and the total beta activity 
concentration  
 
 Investigation levels  
Total alpha activity 
concentration   0.2 Bq/l  
Total beta activity 
concentration   0.5 Bq/l  
 
 
The method and scope of systematic measurement and evaluation of natural radionuclides 
in water  
 
Basic analysis  activity concentration of Rn -222, in the case of water from an underground source  
total alpha activity concentration  
total beta activity concentration  
Supplementary analysis  analysis of the presence of individual natural  
radionuclides in water that has been found  
to exceed investigation levels, according to the following  
procedure  
 
uranium c ontent, if the total alpha activity concentration  
exceeds the investigation level  
 
activity concentration of Ra -226, if the total  
alpha activity concentration after subtraction of the contribution  
of uranium exceeds the investigation level  
 
activity concen tration of Ra -226, if the total activity  
concentration of Ra -226 exceeds the investigation level  
of total alpha activity  
 317 
 
 determination of other  
radionuclides emitting alpha radiation, if  
the total activity concentration after subtraction  
of the Ra -226 and  uranium contribution exceeds the investigation level  
 
potassium content, if the total beta  
activity concentration exceeds the investigation level  
 
determination of other  
radionuclides emitting beta radiation, if  
the total activity concentration after subt raction  
of the contribution of K -40 exceeds the investigation level  
 
 
 
The frequency of systematic measurement and evaluation of natural radionuclides in water  
 
Volume of water distributed or produced daily [m³] *)  The number of samples per calendar year  
volume ≤ 1  000 1 
1 000 < volume ≤ 10  000 1 
+ 1 for every 3  300 m³/day, including portions 
thereof from the total volume  
10.000 < volume ≤ 100 000  3 
+ 1 for every 10  000 m³/day, including portions 
thereof from the total volume  
volume > 100  000 10 
+ 1 fo r every 25  000 m³/day, including portions 
thereof from the total volume  
 
Legend:  
 
*) Volumes are calculated as averages taken over the course of a calendar year.Frequency can also be determined 
from the number of supplied inhabitants, assuming water consu mption of 200  l/day per natural person.  
CELEX:32013L0051  318 
 
 Annex  28 to Decree No …/….Sb.  
 
Construction material pursuant to §  9(2)(j) of the Atomic Act  
 
Construction material pursuant to §  9(2)(j) of the Atomic Act is  
1. natural stone and aggregates to be used for construction purposes, including construction 
products made of the same, these being  
1. all types of granitoids, phonolite, porphyry, andesite, rhyolite, lava, tuff, pozzolan,  
2. ortorula, pararula, migmatite,  
3. black and alum slate, sands, gravels and clays, kaolin, argilites of permo -
carboniferous and neogene age, gypsum, phosphor -gypsum,  
4. artificial stone manufactured using natural stone pursuant to points  1.1 to 1.3,  
2. artificial aggregates, in particular agloporite, perlite, expanded clay, geopolymers, and 
products thereof,  
3. aerated concrete, clinker concrete, aerated concrete construction products, clinker 
concrete construction products,  
4. fly ash, bottom ash, slag, gypsum arising from industrial processes, tailings and sludge 
intended to be used for constructio n purposes, materials from workplaces pursuant to 
§ 92(1)(b) and (c) of the Atomic Act intended to be used for construction purposes, 
construction products made from them not specified in other points, and  
5. material from waste heaps: ore, coal, and waste he aps that remain after mining heavy 
magmatic rocks and tailings ponds intended to be used for construction purposes.  
CELEX:32013L0059  319 
 
 Annex  29 to Decree No  .../…Sb.  
 
The amount of absorbed dose above which emergency protective measures must be 
implemented i mmediately  
 
Organ, tissue  The absorbed dose that is assumed or expected to be 
received over the course of less than 2 days [Gy]  
Whole body  1a) 
Lungs  6 
Skin 3 
Thyroid gland  5 
Lens of the eye  1.5 
Gonads  1 
 
Legend:  
 
a) The possibility of immediate dama ge to a foetus at anticipated doses greater than 0.1  Gy must be taken into 
consideration when justifying and optimising the current intervention level for immediate protective measures.