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SAFETY SERIES
No.9
Basic Safety Standardsfor
Radiation Protection1967 Edition
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, 1967
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BASIC SAFETY STANDARDS FOR RADIATION PROTECTION
1967 E D IT IO N
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T h e follow ing S tates a re M em bers o f th e In te rn a tio na l A tom ic Energy Agency:
AFGHANISTAN GERMANY, FEDERAL NIGERIA
ALBANIA REPUBLIC OF NORWAY
ALGERIA GHANA PAKISTAN
ARGENTINA GREECE PANAMA
AUSTRALIA GUATEMALA PARAGUAY
AUSTRIA HAITI PERU
BELGIUM HOLY SEE PHILIPPINES
BOLIVIA HONDURAS POLAND
BRAZIL HUNGARY PORTUGAL
BULGARIA ICELAND ROMANIA
BURMA INDIA SAUDI ARABIA
BYELORUSSIAN SOVIET INDONESIA SENEGAL
SOCIALIST REPUBLIC IRAN SINGAPORE
CAMBODIA IRAO SOUTH AFRICA
CAMEROON ISRAEL SPAIN
CANADA ITALY SUDAN
CEYLON IVORY COAST SWEDEN
CHILE JAMAICA SWITZERLAND
CHINA JAPAN SYRIAN ARAB REPUBLIC
COLOMBIA JORDAN THAILAND
CONGO, DEMOCRATIC KENYA TUNISIA
REPUBLIC OF KOREA, REPUBLIC OF TURKEY
COSTA RICA KUWAIT UKRAINIAN SOVIET SOCIALIST
CUBA LEBANON REPUBLIC
CYPRUS LIBERIA UNION OF SOVIET SOCIALIST
CZECHOSLOVAK SOCIALIST LIBYA REPUBLICS
REPUBLIC LUXEMBOURG UNITED ARAB REPUBLIC
DENMARK MADAGASCAR UNITED KINGDOM OF GREAT
DOMINICAN REPUBLIC MALI BRITAIN AND NORTHERN
ECUADOR MEXICO IRELAND
EL SALVADOR M ONACO UNITED STATES OF AMERICA
ETHIOPIA MOROCCO URUGUAY
FINLAND NETHERLANDS VENEZUELA
FRANCE NEW ZEALAND VIET-NAM
GABON NICARAGUA YUGOSLAVIA
The Agency's Statute was approved on 26 October 1956 by the Conference on the Statute of the
IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The
Headquarters of the Agency are situated in Vienna, Its principal objective is "to accelerate and enlarge
the contribution of atomic energy to peace, health and prosperity throughout the world".
© IAEA, 1967
Permission to reproduce or translate the information contained in this publication may be obtained
by writing to the International Atomic Energy Agency, KSmtner Ring 11, A-1Q10 Vienna I, Austria.
Printed by the IAEA in Austria
July 1967
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SAFETY SERIES No. 9
BASIC SAFETY STANDARDS FOR RADIATION PROTECTION
1967 EDITION
IN T E R N A T IO N A L A T O M I C E N E R G Y A G E N C Y
V IE N N A , 1967
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BASIC SA FETY S T A N D A R D S FOR R A D IA T IO N P R O T E C T IO N - 1967 Edition
(Safety Series, N o .9)
A B S T R A C T . This first revision of the Basic Safety Standards was approved by the IAEA Board
of Governors in September 1965. It was prepared with the assistance of a panel of experts chaired
by Prof. L . Bugnard, Director of the French Institut National d’ Hygifene, and attended by represen
tatives of several international organizations. Com ments from M em ber States were considered
and changes were introduced on the basis of recommendations made by the International Commission
on Radiological Protection in 1966. The Director General of the IAEA has been authorized by the
Board to apply the revised Standards to.IAEA and IAEA-assisted operations. It has also been re
commended that the national regulations of Member States should conform, as far as is practicable,
to the revised Standards.
Contents: Acknowledgements; Introduction; Meaning of terms used; Scope; Limitations
of doses for exposure from controllable sources; Radiation doses and intakes of radioactive materials
through external and internal exposure; Fundamental operational principles; Annex A : Tables 1A,
IB, IIA and IIB; Annex B: Mixture of radionuclides - Tables IIIA and IIIB.
(79 p p ., 1 4 .8 x 21 c m , paper-bound, 1 figure)
(1967) Price: U S $ 2 .0 0 ; 1 4 /2 stg.
T H E S E R E G U L A T IO N S A R E A L S O
P U B L IS H E D IN F R E N C H , R U SSIA N A N D SPAN ISH
BASIC S A F E T Y S T A N D A R D S F O R R A D IA T IO N P R O T E C T IO N ,
1967 E D IT IO N
IA E A , V IE N N A , 1967
S T I /P U B /147
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FOREWORD
This first revision of the Basic Safety Standards was approved
by the Agency's Board of Governors in September 1965. It was pre
pared with the assistance of a panel of experts chaired by Professor
L . Bugnard, Director of the French Institut National d'Hygiene, and
attended by representatives of several international organizations,
The panel took into consideration comments received from Member
States as well as the important work done by the International Com
mission on Radiological Protection. A few changes were subse
quently introduced on the basis of recommendations made by that
Commission in 1966, as requested by the Board.
The Board has requested the Director General to apply the re
vised Standards to the Agency's operations, as well as to operations
assisted by it, as required. It has also recommended to all Member
States that their national regulations for radiation protection should
conform, as far as is practicable, to the revised Standards.
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CONTENTS
IN T R O D U C T IO N ............................... ..................................................... 4
1. M E A N IN G O F T E R M S U SED ........................................................ 5
2. SC O P E ...................................................................................... 9
3. L IM IT A TIO N O F DOSES F O R E X P O S U R E F R O M
C O N T R O L L A B L E SOURCES ......................................................... 9
3 .1 . Maximum permissible doses for w orkers.................... 9
3 .2 . Dose limits for individual members of the public . . . . 13
3 .3 . Dose limits for the whole population................................ 14
4. R A D IA T IO N DOSES A N D IN TA K ES O F RA D IO A C TIV E
M A T E R IA L S T H R O U G H E X T E R N A L A N D IN T E R N A L
E X P O S U R E ........................................................................................14
4. 1. Workers .................................................................................. 14
4 .2 . Individual members of the public ..................................... 18
5. F U N D A M E N T A L O P E R A T IO N A L PR IN C IP LE S .......................19
5 .1 . General requirements ......................................................... 19
5 .2 . Inspection and intervention................................................. 26
A N N E X A : T A B L E S I A , IB , IC , IIA and U B ................................. 27
A N N E X B : M IX T U R E S O F R A D IO N U C LID E S
T A B L E S III A A N D III B ................................. ......... . . 7 7
A C K N O W L E D G E M E N T S .................................................................... 1
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A C K N O W L E D G E M E N T S
The Agency's thanks are due to the following members of a panel
of experts convened by the Director General to discuss the original
draft of the revised Basic Safety Standards prepared by the
Secretariat:
Chairman:
Professor L . Bugnard*, Institut National d'Hygiene, France
M em bers :
M r . D .B . Beninson
Atomic Energy Com m ission
Argentina
M r . W . Binks
International Com m ission on
Radiological Protection
M r . G . C . Butler
Atomic Energy of Canada.Ltd.
Canada
M r . H . Donth
Federal Ministry of Scientific
Research
Federal Republic of Germ any
M r . H . J. Dunster
United Kingdom Atomic Energy
Authority
United Kingdom of Great Britain
and Northern Ireland
M r . P . Krishnamoorthy
Atomic Energy Establishment
India
M r . L .- E . Larsson
Institute of Radiophysics
Sweden
M r . Y . M urakam i
Atomic Energy Research
Institute
Japan
M r . T . Musialowicz
Central Laboratory of Radiation
Protection
Poland
M r . Y u . I. Moskalev
Academ y of Medical Sciences
Union of Soviet Socialist
Republics
M r . C . Polvani * *
Comitato Nazionale per l'Energia
Nucleare
* A c c o m p a n ie d by M r. H . Ja m m e t o f th e C o m m is s a r ia t i l 'e n e r g ie a to m iq u e .
A c c o m p a n ie d by M r. E. S tra m b i o f th e C o m ita to N a z io n a le p er l 'E n e rg ia N u c le a r e .
1
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M r . L . Taylor
National Bureau of Standards
United States of Am erica
M r . A . R . W . Wilson
Atomic Energy Com m ission
Australia
Representatives of organizations:
Food and Agriculture
Organization of the United
Nations
M r . G . Wortley
World Health Organization
M r . H . Parker
European Atomic Energy
Community
M r . P . Recht
European Nuclear Energy
Agency
Organization for European
Economic Co-operation
M r . S. Halter
M r . E . Wallauschek
M r . J. Zakovsky
International Labour Organisation
M r . J .V . Nehemias
Composition of the group of consultants and representatives
which met in 1966 to consider the comments of M em ber States on
the amendments proposed in the Agency's circular letter SC /611
of 26 M ay 1966.
M r . H .J . Dunster
Radiological Protection
Division
Authority Health and Safety
Branch
U .K . A .E . A .
Harwell, Didcot, Berks.
United Kingdom
M r . F .D . Sowby (ICRP)
Clifton Avenue
Sutton, Surrey
United Kingdom
M r . P . Pavanello
World Health Organization
Avenue Appia
Geneva, Switzerland
* M r . P . Pellerin (W H O )
Service Central de Protection
contre les Radiation Ionisants
L e Vesinet
France
M r. P e lle r in and M r. L eu p o ld a c c o m p a n ie d M r. P a v a n e llo as co n su lta n ts for th e W orld
H e a lth O rg a n iz a tio n .
2
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M r . H . Jam m et
Commissariat l'energie
atomique
Centre d'etudes nucleaires
* M r . R . L . Leupold
World Health Organization
Avenue Appia
Geneva, Switzerland
Fontenay-aux-Roses (Seine)
France
M r . E . Hellen
International Labour
Organisation
Geneva
Switzerland
# M r. P e lle r in and M r. Leupold a c c o m p a n ie d M r, P a v a n e llo as co n su ltan ts for th e W orld
H ea lth O rg a n iz a tio n .
3
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IN T R O D U C T IO N
1. Under Article III. A . 6 of its Statute "the Agency is authorized
to establish or adopt, in consultation and, where appropriate, in
collaboration with the competent organs of the United Nations and
with the specialized agencies concerned, standards of safety for pro
tection of health and minimization of danger to life and property (in
cluding such standards for labour conditions), and to provide for
the application of these standards to its own operations as well as
to the operations making use of materials, services, equipment,
facilities and information made available by the Agency or at its re
quest or under its control or supervision: and to provide for the
application of these standards, at the request of the parties, to
operations under any bilateral or multilateral arrangement, or, at
the request of a State, to any of that State's activities in the field
of atomic energy."
2. The Agency's Health and Safety Measures, approved by the
Board of Governors on 31 March I96 01, provide that Agency safety
standards shall include:
(a) The Agency's basic safety standards — standards pres
cribing maximum permissible levels of exposure to radi
ation and fundamental operational principles; and
(b) The Agency's detailed operational standards.
They further provide that the Agency's Basic Safety Standards should
be, as far as possible, based on the recommendations of the Inter
national Commission on Radiological Protection (ICRP) and in
accord with standards published by other international organizations.
3. In October 1958 the ICRP issued recommendations with respect
to the maximum permissible accumulated dose for occupational radi
ation exposures and for exposure of the population. In 1959 it re
leased recommendations regarding the maximum permissible con
centrations of radioactive materials in air and water.
4. In 1964 the IC R P published recommendations amending those
made in 1959 and revised in 1962. In 1966 the ICRP issued publica
tion No. 9 which contained a number of significant changes. These
amendments, together with the comments made by Member States,
justified a revision of the Agency's Basic Safety Standards.
5. The Agency believes that the limits established in the following
revised Basic Safety Standards for Radiation Protection, based as
1 INFCIRC/18.
4
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far as possible on the recommendations of the IC R P , provide an
appropriate regulatory basis for the protection of the health and safe
ty of employees and the public without imposing undue burdens upon
users of radioactive material. The recommended limits of ex
posure, derived from extensive scientific and technical investiga
tions and from years of experience with the practical problems of
radiation protection, represent a consensus of opinion as to
the measures generally considered desirable to provide appropriate
degrees of safety in the situations to which these Standards apply.
6. The Agency recognizes that the ICRP's recommendations cannot
be converted into regulations without loss of flexibility in their appli
cation to individual situations. It is, however, the policy of the Agency
to minimize this loss of flexibility, both in the formulation of
its regulations and in their administration, to the greatest extent
compatible with the nature of the problem and with good regulatory
practice.
7. Other publications in the Agency's Safety Series should be con
sulted for practical detailed guidance in implementing these stan
dards. W hen applied to the Agency's operations or to operations
assisted by the Agency, this document should be read in the light
of the Agency's Health and Safety M easures1.
1. M E A N IN G O F T E R M S U S E D
For the purposes of these standards the following terms have
the meanings hereby assigned to them.
1 . 1 . PH YSIC A L AND RAD IO LOGICA L TERM S
Ionizing radiation: 2
Electromagnetic radiation (X-ray or y -ray photons) or corpuscular
radiation capable of producing ionization in its passage through
matter.
1IN FC IRC /18.
2For a m o re d e ta ile d d e f in itio n , co n su lt P u b lica t io n Report 10 a 1 9 6 2 o f th e In te rn a tio n a l C o m m issio n o f R a d io lo g ic a l U n its and M e a su re m e n ts, p u b lish ed in H andbook 8 4 , U n ite d S ta te s N a tio n a l Bureau o f Standards.
5
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Source:
Apparatus capable of producing, or substance producing, ionizing
radiation.
Nuclide:
A species of atom having specified numbers of neutrons and protons
in its nucleus.
Radioactivity:
Spontaneous disintegration of a nuclide.
Radiotoxicity:
The toxicity attributable to the radiation emitted by a radioactive
substance within the body.
External radiation:
Radiation reaching the body from external sources.
Internal radiation:
Radiation arising from radioactive substances within the body.
Natural radiation■
The various natural radiation sources include:
(a) External sources of extra-terrestrial origin (cosmic-rays)
and external sources of terrestrial origin, i .e . the radio
active isotopes naturally present in the crust of the earth
and in air; and
(b) Internal sources, i.e . the radioisotopes 40 K and I4C which
make up a small percentage of these elements and are nor
mal constituents of the body, and other isotopes such as
226Ra and 232Th and their decay products, which are taken
up from the natural environment.
6
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Controlled area:
An area scheduled as such for the purpose of controlling individual
personnel exposure and under the supervision of a person who has
the knowledge and responsibility to apply appropriate radiation pro
tection regulations.
Qualified expert:
A person having the knowledge and training required to give advice
on protective measures and operating procedures which will ensure
effective radiation protection for persons exposed to ionizing
radiation.
Competent authority:
A national or international authority designated or otherwise re
cognized as such by a government for any purpose in connection with
these standards.
Emergency exposure:
A planned exceptional exposure in the case of compelling or over
whelming necessity.
Accidental exposure:
An unforeseen exposure resulting in a radiation dose or intake of
radioactive material exceeding the m axim um permissible values.
Absorbed dose:
The absorbed dose of any ionizing radiation is the energy imparted
to matter by ionizing particles per unit mass of irradiated material
at the place of interest.
rad: .
The unit of absorbed dose. 1 rad = 100 erg/g
7
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The dose equivalent:
(i) For protection purposes, it is useful to define a quantity
which is termed the "dose equivalent" (DE ).
(ii) (DE) is numerically equal to the product of absorbed dose D,
quality factor (QF), dose distribution factor (DF), and other necessary
modifying factors.
The unit of dose equivalent is the rem.
The quality factor (QF), as used in radiation protection, is the fac
tor dependent on energy transfer by which the absorbed dose is
multiplied to obtain, for the purposes of radiation protection, a
quantity that expresses on a scale common to all ionizing radiations
the dose received by exposed persons. Provision for other factors
is also made. Thus, a distribution factor (DF) may be used to ac
count for modifications of the biological effect due to a non-uniform
distribution of internally deposited isotopes.
The Q F values that should be used for radiation protection purposes
are listed in Tables IA , IB and IC of Annex A.
In this text the terms dose and dose equivalent are used interchangeably.
Dose commitment:
The total dose to an organ or tissue over a period of 50 years re
sulting from an intake of radioactive material.
oThe annual genetically significant dose :
The annual genetically significant dose to a population is the average
of the individual gonad doses, each weighted for the expected number
of children conceived subsequent to the exposure. The genetic dose
to a population is assessed as the annual genetically significant dose
multiplied by the mean age of child bearing which for the purpose
of this report is taken to be 30 years.
3 For c a lc u la t io n o f th e g e n e tic a l ly s ig n ific a n t dose to th e p op u lation see th e 1 9 5 9 Report o f
th e U nited N ations S c ie n t if ic C o m m itte e on th e E ffects o f A to m ic R ad iation , para. 8 3 ,and th e 1962
report, p. 3 8 9 .
8
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curie:
The special unit of activity is the curie (Ci). One curie equals
3 . 7 X 1010 disintegrations s'1 (exactly).
Neutron CLux density:
Neutron flux density expresses the number of neutrons falling on
a sphere of unit cross-sectional area per second.
2. S C O P E
2.1. These standards apply to the production, processing, handling,
use, storage, transport and disposal of natural and artificially pro
duced radioactive material, and to the use and operation of other
radiation sources. Fall-out from nuclear weapon tests is excluded
from these standards.
2.2. These standards apply to:
(a) Workers4
(b) Individual members of the public; and
(c) The whole population, as defined by the competent authority.
2.3. The doses referred to in these standards do not include:
(a) Doses to patients resulting from medical examination or
treatment; or
(b) Doses resulting from natural radiation.
3. L IM IT A T IO N O F D O S E S F O R E X P O S U R E S F R O M
C O N T R O L L A B L E S O U R C E S
3 .1 . M A X I M U M PERMISSIBLE D O S E S F O R W O R K E R S 5
M axim um permissible doses represent the m axim um values
to which workers may be exposed under certain appropriately de
4See also 4 .1 . 3.
5 Emergency doses and accidental exposures for workers are dealt with in section 4.
9
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fined conditions. To the extent permitted by reasonable economic
and social considerations actual exposures should be as far below
the maximum as is practicable.
The total dose to any organ or tissue shall comprise the doses
contributed by external sources during working hours and by the
intake of radioactive materials into the body during working hours.
3 . 1 . 1 . The maximum permissible dose to the whole body, go
nads or red bone marrow of an individual shall be 5 rem in any
one year.
3. 1. 1.1. It may sometimes be necessary to provide flexi
bility for the maximum permissible dose for exposure in
volving the whole body, gonad or the red bone marrow. In
such cases (these cases, however, are felt to be infrequent)
the total accumulated dose to the whole body, gonads or
red bone marrow of an individual shall not exceed the maxi
mum permissible dose derived from the formula D= 5(N-18)
where D is expressed in rem and N is the individual's age
in years. Age in years may, for administrative purposes,
be reckoned from any selected date of the year. Maximum
permissible doses for single organs other than the red bone
marrow, whole body and gonads are specified in paragraph
3. 1.6. Exceptions and modifications to the application of
the formula are indicated in paragraphs 3 . 1 . 2 through
3 . 1 . 5 .
3. 1.2. Provided the total dose in any one year does not exceed
the maximum permissible dose given in paragraph 3. 1. 1, and
subject to the provisions of (a), (b) and (c) below, a worker may
receive in. a quarter of a year a dose to the whole body, gonads
and the red bone marrow not exceeding 3 rem. A dose of 3 rem
m ay be received as a single dose within a quarter of a year,
but this shall be avoided as far as practicable.
(a) The dose accumulation at rates up to 3 rem per quarter
shall not apply in circumstances involving abdominal exposure
of women of reproductive capacity. W om en of reproductive
capacity shall be employed only under conditions where the ex
posure of the abdomen is limited to 1. 3 rem in a quarter, cor
responding to 5 rem per year delivered at an even rate.
1 0
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(b) The dose to the foetus of a pregnant woman accumulated
during the period after pregnancy has been diagnosed shall not
exceed 1 rem.
(c) In work with X-ray equipment of 150 kV and less or
with other forms of soft radiation or where the abdomen is pro
tected from or is not exposed to the radiation, the dose to the
foetus will be considerably less than that received by the woman
In these conditions a woman in whom pregnancy has been diag
nosed may continue to be engaged in radiation work involving
exposure at a rate not exceeding 1 .3 rem per quarter, esti
mated on the surface of the body (outside the protected area
of the abdomen if penetrating radiation is involved).
3 . 1 . 3 . If the dose previously accumulated in radiation work
by a worker over any given period is not known, it shall be as
sumed that the worker has received the currently recommended
maximum permissible dose in each year of that period.
3. 1. 4. Workers who have been exposed in accordance with the
former IC R P recommendations which laid down a maximum
permissible weekly dose of 0. 3 rem and who have accumulated
a dose higher than that determined by the formula shall not be
exposed at a rate higher than 5 rem in any one year, until the
accumulated dose at a subsequent time is lower than that de
termined by the formula.
3 . 1 . 5 . If a worker begins to be engaged in radiation work at
an age of less than 18 years, the dose to the whole body, gonads,
and red bone marrow shall not exceed 5 rem in any one year
while his age is less than 18 years, and the dose accumulated
at the age of 30 shall not exceed 60 rem. In addition the other
relevant requirements of paragraph 3. 1 shall apply.
3. 1.6. The dose to organs other than the gonads, the whole
body and the bone marrow received shall not exceed the values
listed below:
1 1
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Organ
Quarterly
limit
(rem)
Limit per
year
(rem)
Any single organ3, excluding the gonads,
the red bone marrow, bone, thyroid
and skin 8 15
Bone, thyroid, skin of the whole body
(excluding the skin of the hands,
forearms, feet and ankles) 15 30
Hands, forearms, feet and ankles 40 75
aIncluding the lens of the eye. However, in the case of irradia
tion of the lens of the eye with particulate radiation of high L E T a
special modifying factor is used as indicated in Annex A, Table I A,
Table IB and Table I C.
3.1. 7. Planned special exposure
Situations may occur infrequently during normal operations when
it may be necessary to allow a few workers to receive exposure
in excess of the recommended quarterly limits. In such cir
cumstances, exposure or intakes of radioactive material may
be allowed provided the dose commitments do not exceed twice
the annual dose limit in any single event and in a lifetime 5 times
this limit.
It is emphasized that doses or intakes of this magnitude are
only justified when alternative techniques which do not involve
such exposures of workers are either unavailable or im
practicable.
Planned special exposure should not be allowed under the fol
lowing conditions:
(a) If the addition of the intended dose to the worker's accu
mulated dose exceeds the amount determined by the procedure
in paragraph 3. 1. 1. 1.
1 2
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(b) If the worker has received in the previous 12 months
a single exposure or intake of radioactive material with a dose
commitment in excess of the quarterly quota.
(c) If the worker has previously received an emergency ex
posure or intake or an accidental exposure in excess of 5 times
the annual dose limit.
(d) In the case of women of reproductive capacity.
Doses resulting from planned special exposure shall be recorded
with those from usual exposures but any excess over the re
commended limits should not constitute a reason for excluding
a worker from his usual occupation.
3 .2 . D O SE LIM ITS FOR IN D IV ID U A L M EMBERS O F T H E PUBLIC
In any organ or tissue, the total dose shall comprise doses con
tributed by external sources and doses resulting from the intake of
radioactive material.
The annual dose limits for individual m em bers of the public
are listed below:
OrganLimit per year
(rem)
Whole body, gonads, red bone marrow 0. 5
Any single organ, excluding the red bone
marrow, gonads, bone, thyroid and skin 1.5
Bone, thyroid3, skin of the whole body
(excluding the skin of the hands, forearms,
feet and ankles) 3
Hands, forearms, feet and ankles 7.5
a The exposure of the thyroid of children below the age of 16 shall
be limited to 1. 5 rem in a year.
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3. 3. DOSE LIMITS FOR THE WHOLE POPULATION
3.3. 1. The genetic dose to the whole population over a period
of 30 years shall be kept to the minimum amount consistent with
necessity and shall not exceed 5 rem . Any allocation of the
genetic dose, from whatever source, among the various sec
tions of the population will depend on circumstances which may
vary from country to country and should, therefore, be decided
upon by the competent national authorities.
4. RADIATION DOSES A N D IN TAKES O F R ADIOACTIVE
M A T E R IA L S T H R O U G H E X T E R N A L A N D IN TE R N A L
E X P O S U R E
The exposure of individuals and the number of individuals ex
posed shall be kept as low as practicable. If a person is exposed
to both external and internal radiation, the combination of both ex
posures shall be considered and, if necessary, the corresponding
exposures shall be reduced appropriately in either or both cate
gories . Dose record keeping is dealt with in 5. 1. 2. 4.
4 . 1. WORKERS
4 . 1 . 1 . E x p o s u r e t o e x t e r n a l r a d i a t i o n o n l y
4. 1. 1. 1. Normal working conditions
Exposure to external radiation of workers shall be so
limited as to ensure that the doses received do not exceed
the maximum permissible doses listed in paragraph 3.1.
The exposure to external radiation which will lead to these
maximum permissible doses shall be determined from the
data listed in Tables I A , IB and IC of Annex A.
4. 1.1.2. Emergency exposure
Even in emergency work, all practicable steps shall be
taken to minimize radiation doses.
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Doses in excess of those specified in 3 . 1 . 7 are acceptable
in emergency operations during or immediately after an
accident and shall be planned with competent advice. The
justification for this will be the rescue of individuals, the
prevention of the exposure of a large number of people or
the saving of a valuable installation. It is not possible to
specify dose limits for such exposures since the acceptabi
lity of the dose will depend on the importance of the objec
tive. Whenever possible workers shall be informed about
the risks before they accept such exposures.
If the dose exceeds twice the appropriate annual limit in
3 . 1 . 1 and 3. 1.6, the situation shall be reviewed by appro
priate medical authorities. The worker may still be
allowed to continue routine work if there is no objection
from the medical viewpoint, the account having been taken of
his previous exposure, health, age and special skills, as
well as his social and economic responsibilities.
4 . 1 . 1 . 3 . Accidental exposure
Accidental exposures in excess of the limits for normal
working conditions differ from emergency exposures in
that they are unavoidable and unforeseen. The reference
of workers to appropriate medical authorities and decisions
concerning subsequent work shall be the same as for emer
gency exposures (4. 1.1. 2).
4.1 . 2. Exposure to internal radiation only
4. 1.2. 1. Normal working conditions
Internal contamination of workers shall be limited so that
the maximum permissible doses specified in section 3. 1
are not exceeded. From the yearly limits maximum per
missible organ burdens can be derived (see Tables IIA and
II B of Annex A) which, if maintained, lead to the average
maximum permissible organ doses. From these, in turn,
maximum permissible yearly intakes can be calculated
which, even if maintained throughout a worker's lifetime,
would not result in organ burdens in excess of the m axi
m um permissible values.
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Up to half the yearly intake can be taken in one quarter pro
vided the yearly limit is not exceeded. In practice, inha
lation is the most important route of contamination of
workers. For this reason, Tables II A and II B of Annex A
give, in respect of workers, values for m axim um per
missible yearly intakes by inhalation only. However, other
routes of intake are possible (e.g. ingestion and uptake
through the skin), and if they make a significant contribu
tion to the organ content or organ dose they must be taken
into consideration in assessing the organ doses.
(i) If only one radionuclide is present, the yearly in
take shall not exceed the limit given in Tables II A and IIB
of Annex A for workers.
(ii) Where there is a mixture of radionuclides of known
composition, the combined effect of the resulting exposures
shall be taken into account as indicated in Annex B.
(iii) Where there is a mixture of radionuclides of par
tially or completely unknown composition, intake shall be
limited in such a manner that, whatever its composition,
the yearly intake of none of the radionuclides that may be
present will exceed the limits stated in Table II of Annex A.
Methods of achieving this limitation are indicated in Annex
B and examples of the application of one method are shown
in Table III B of that Annex.
4. 1.2. 2. Emergency intakes
Even in emergency work, all practicable steps shall be
taken to minimize the intake of radioactive materials.
In emergency exposures, it is not possible to predict the
magnitude of the intake and it is therefore unrealistic to
specify a limit for the intake. The justification for such
exposures will be the rescue of individuals, the prevention
of the exposure of a large number of people or the saving
of a valuable installation.
Whenever practicable an estimate shall be made of the in
take, and, if it exceeds twice the annual limit, the situ
ation shall be reviewed by appropriate medical authorities.
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The worker may still be allowed to continue routine work
if there is no objection from the medical viewpoint, the
account having been taken of his previous exposure, health,
age and special skills, as well as his social and economic
responsibilities.
4. 1.2. 3. Accidental intakes
Accidental intakes differ from emergency intakes only in
that they are unavoidable and unforeseen. The reference
of workers to appropriate medical authorities and decisions
concerning subsequent work shall be the same as with emer
gency intakes 4. 1. 2. 2.
4.1.3. Administrative classification of workers
For administrative purposes it is convenient to consider two
conditions under which workers are exposed to radiation in the
course of their work. This distinction depends on the possi
bility of a certain level of dose being exceeded, rather than the
actual level observed, and will have an influence on arrange
ments for health surveillance and radiation protection as well
as on the design and operation of an installation.
The two conditions are :
(i) Conditions such that the resulting doses might exceed
three-tenths of the annual maximum permissible doses. This
working condition shall require that the workers be subject to
special health supervision and personnel monitoring. For these
workers the dose assessments will usually be achieved by indi
vidual monitoring for external radiation or internal contamina
tion as appropriate, although they may sometimes be made by
indirect methods.
(ii) Conditions such that the resulting doses are most un
likely to exceed three-tenths of the annual maximum permissible
dose. Workers working under this condition would not require
individual monitoring and special health supervision. For these
workers monitoring of the working environment will usually be
sufficient, even though in some cases individual monitoring may
be desirable, e.g. to obtain statistical information on the
exposures.
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4. 2. INDIVIDUAL MEMBERS OF THE PUBLIC
4 . 2 . 1 . The maximum permissible doses for workers given in
section 3 are regarded as upper limits and the doses may have
to be individually monitored and controlled to ensure that the
m axim um permissible doses are not exceeded. The dose li
mitation for members of the public is a more theoretical con
cept, intended to provide standards for the design and opera
tion of radiation sources so that it is unlikely that individuals
among the public will receive more than a specified dose. The
effectiveness of this is checked not by observing individuals but
by assessments through sampling procedures in the environment
and statistical calculations, and by a control of the sources from
which the exposure is expected to arise. For these reasons
it is seldom meaningful to speak of maximum permissible doses
for individual members of the public, instead the term dose li
mits should be used as indicated in 3.2.
4 . 2 . 2 . The basis for the limitation of exposures of members
of the public is the dose to the various body organs and not the
derived criteria by which the dose is controlled. The actual
doses received by individuals will vary depending on factors
such as differences in their age, size, metabolism, and customs,
as well as variations in their environment. The variation re
sulting from these sources makes it impossible to determine
the maximum doses that might be received individually. In prac
tice, it is feasible to take account of these sources of variability
by the selection of appropriate critical groups within the popu
lation, provided the critical group is small enough to be homo
geneous with respect to age, diet and those aspects of behaviour
that affect the doses received. Such a group should be repre
sentative of those individuals in the population expected to re
ceive the highest dose, and the Agency believes that it will be
reasonable to apply the appropriate dose limit for members of
the public to the mean dose of this group. Because of the innate
variability within an apparently homogeneous group, some m em
bers of the critical group will receive doses somewhat higher
than the dose limit; however, at the very low levels of risk
implied, it is likely to be of minor consequence to their health
if the dose limit is marginally or even substantially exceeded.
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4 . 2 . 3 . In some situations, especially in the planning of pro
posed operations or installations, it may not be practicable to
make the detailed studies necessary for the identification of
the critical group. To allow for individual variability it will
then be necessary to apply an operational " safety factor" to the
derived concentration limits applicable to a member of the
public. However, as the values to be recommended for such
factors would vary over a wide range, depending on the parti
cular circumstances, no generally applicable values are given
in this edition.
4 . 2 . 4 . The yearly intakes of radionuclides by inhalation or
ingestion shall remain within the limits listed in Tables II A
and II B of Annex A.
(a) If only one radionuclide is present in the air or in water,
the yearly intake shall not exceed the limit listed for individual
members of the public in Table II A of Annex A.
(b) W here there is a mixture of radionuclides of known
composition, the combined effect of the resulting exposures
shall be taken into account as indicated in Annex B .
(c) W here there is a mixture of radionuclides of partly
or completely unknown composition, annual intake shall be
limited in such a manner that, whatever its composition, the
yearly intake of none of the radionuclides that may be present
will exceed the limits stated in Tables II A and II B of Annex A.
Methods of achieving this are indicated in Annex B and examples
of the application of one method are shown in Tables HI A and
IIIB of that Annex.
5. F U N D A M E N T A L O P E R A T IO N A L P R IN C IP L E S
5 . 1 . GENERAL REQUIREM ENTS
5 . 1 . 1 . Notification, registration, licensing
Except as provided in paragraph 5. 1. 1.3, operations referred
to in paragraph 2. 1 shall be notified or registered as required
by the competent authority and, if necessary, licensed by that
authority in the light of the health hazard involved.
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5. 1. 1. 1. In making such notification or in applying for
such registration or licensing, all information which the
competent authority m ay deem necessary for evaluating
the health hazard shall be provided.
5. 1. 1.2. Insofar as the operation is not subject to special
regulations enforced by the competent authority, that
authority shall, using the services of qualified experts,
evaluate the health hazards involved, taking into account
the necessary elements such as the siting of the installation
and demographic, geological, hydrological, agricultural
and meteorological factors and shall prescribe any neces
sary measures to be taken in respect of the operation.
5. 1. 1. 3. If it is satisfied that the doses of radiation in
curred will be trivial, the competent authority should waive
the requirements of paragraph 5 . 1 . 1 for such operations
and items as the following:
(i) Operations which do not involve the use of radio
active substances having total activities in excess of those
listed in Tables II A and II B of Annex A (last column);
(ii) Operations which do not involve the use of radio
active substances at concentration exceeding 0.002 /uCi/g
or solid natural radioactive substances at concentration
exceeding 0. 0 1 /aCi/g;
(iii) The use of apparatus, provided that the dose-rate
at any external point situated at a distance of 0. 1 m from
the surface of the apparatus does not exceed 0.1 m rem /h;
leakage of any radioactive substances present must be ef
fectively guarded against, and the type of the apparatus must
be approved by the competent authority;
(iv) The use of equipment in which electrons are ac
celerated to an energy not exceeding 5 keV;
(v) The use of television sets for which the dose-rate
at any readily accessible point, 5 cm from the surface of
the set, does not exceed 0.5 m rem /h under normal working
conditions.
5. 1. 1.4. The exemption permitted by paragraph 5. 1.1. 3 (i)
shall not apply to:
(i) The use of radionuclides for medical purposes; and
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(ii) The intentional addition of radionuclides to food
stuffs, fertilizers, pharmaceutical goods, cosmetics, and
toys.
For these uses of radionuclides prior authorization by the
competent authority must be required; the competent
authority must be satisfied that no undue exposure will re
sult from the proposed application.
5.1 . 2. Radiation protection within establishments where
radiation sources are present
The responsibility for radiation protection in an establishment
lies with the management.
In addition to the provision of suitable facilities measures for
radiation protection within an establishment shall include ad
ministrative organization, physical surveillance, medical sur
veillance and the keeping of adequate records. The nature and
extent of the measures employed shall be related to the magni
tude of the risk of exposure.
5. 1. 2. 1. Administrative organization
(a) A technically competent person shall be designated
to supervise the application of appropriate radiation protec
tion regulations. This person shall seek the advice of quali
fied experts whenever necessary and shall have direct ac
cess to the management of the establishment, which in turn
shall consult him on all relevant safety matters.
(b) No workers shall be employed or shall continue
to be employed in work by reason of which the worker could
be subject to exposure to ionizing radiation contrary
to qualified medical advice.
(c) No worker under the age of 16 shall be engaged
in radiation work.
(d) Each worker employed in an establishment where
exposure to ionizing radiation can occur shall receive ap
propriate instructions (to the extent necessary, having re
gard to the circumstances of his employment) concerning
the hazards involved and the precautions to be observed.
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(e) Any necessary administrative, technical and medi
cal instructions concerning the radiation risk and safe work
ing practices relevant to the type of installation and the
work involved shall be made available. In addition, appro
priate protective equipment shall be made available and
provision made to ensure its use by all workers engaged
in radiation work.
(f) If an exposure in excess of the maximum permis
sible doses listed in section 3 occurs, or is suspected to
have occurred, a study shall be made of the circumstances
in which the exposure took place and the results shall be
reported to the authority in charge of the establishment.
Accidental conditions which may give rise to a risk of over
exposure should also be investigated.
5. 1.2.2. Physical surveillance
Physical surveillance shall be established to determine the
nature of the precautions which must be taken to ensure
compliance with these Basic Safety Standards and to assess
the effectiveness of precautions taken. Such physical sur
veillance shall include:
(a) Examination and control of protective measures, in
cluding:
(i) The assessment for approval purposes of new in
stallations and operations, or of modifications to exist
ing installations, from the point of view of radiation
protection;
(ii) The assessment of the continued adequacy of work
ing methods and of the effectiveness of protective de
vices; and
(iii) The checking of performance and correct use of
all relevant instruments.
(b) Surveying and monitoring, including:
(i) The assessment of exposure levels at all appropri
ate locations within the establishment, and of the
nature and quality of the radiation involved; and
(ii) The adequate assessment of radioactive conta
mination with a view to ensuring continued compliance
with these Basic Safety Standards.
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(c) Establishment of controlled areas
Controlled areas shall be established where individuals
could receive doses in excess of three-tenths of the annual
maximum permissible doses given in paragraph 3.1. Such
areas shall be marked out and warning signs posted as ap
propriate at the entrances to them and within them. These
warning signs shall display:
(i) The basic symbol shown below (Fig. 1) which indi
cates the presence of ionizing radiation; and
(ii) Such additional inscriptions or symbols as may
be required to indicate in a manner understandable to
all concerned the magnitude or particular nature of the
exposure risk.
60°
(d) Evaluation of doses received in controlled areas by
workers.
(i) The doses received from external radiation shall
be evaluated by the use, if necessary, of one or more
individual radiation detectors carried continuously on
the person while in the controlled area;
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(ii) The doses received from internal radiation shall,
if necessary, be evaluated by any physical or chemical
methods which enable the intake or body organ burden
of radioactive materials to be evaluated.
The frequency of assessments shall be such that
compliance with the Basic Safety Standards is ensured.
5 . 1 . 2 . 3 . Medical surveillance
Medical surveillance shall be established in order to pro
vide any necessary medical supervision of workers. A
suitable medical casualty service shall also be established.
(a) All workers engaged in radiation work shall under
go an appropriate medical examination before or shortly
after taking up employment to ensure their fitness for work.
Such an examination shall normally include an enquiry into
the worker's personal history, covering family, medical
and occupational background, and the usual clinical tests.
In addition, special investigations shall be carried out in
regard to those organs and functions which are considered
particularly vulnerable to the hazards involved, as well
as investigations which may be pertinent to the performance
of particular types of work.
(b) Routine medical examinations during employment
shall be carried out periodically as the competent authority
may require. They may include the types of examination
mentioned in (a) above as well as any special examinations
which are desirable in view of the radiation hazards in
volved in each particular case.
(c) In addition to routine medical examinations, ex
ceptional medical surveillance, comprising any further
examination, decontamination procedures or urgent medi
cal treatment deemed necessary by an appropriate medical
practitioner, shall be made available..
Any worker receiving an accidental or emergency dose
greater than twice the yearly maximum permissible doses
shall be subjected to exceptional medical surveillance as
requiredbysections4.1.1.2, 4 .1.1. 3, 4. 1. 2. 2 and4. 1. 2. 3.
(d) A medical casualty service shall be provided. The
extent of this service will depend on the radiation hazard
and other potential hazards that may be encountered in the
establishment.
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(i) First-aid facilities and advice shall be immediately
available; and
(ii) Arrangements for referring casualties and con
taminated personnel to medical services at an appro
priate stage should be clearly defined and made known.
5. 1.2.4. Records
(a) Records shall be kept of the results of the surveys
and monitoring of the controlled area and shall be made
available for inspection by the competent authority.
(b) Personal records shall be kept, in a form and in
a manner acceptable to the competent authority, for every
worker in radiation work. Such records shall contain rele
vant data and information on:6
(i) The general nature of the work involving exposure
to radiation and the type of radiation involved;
(ii) The extent to which the worker has been or is as
sumed to have been exposed to radiation, as indicated
by individual or area monitoring methods.
(iii) The results of medical examinations.
(c) Information on the assessment of individual doses
shall be preserved for at least 30 years after cessation of
the work involving exposure to ionizing radiation, or for
such other period as the competent authority may specify.
(d) All emergency and accidental doses and where
practicable emergency and accidental intakes shall be re
corded together and clearly distinguished from normal
exposure.
5. 1 .3 . Radiation protection surveillance outside establishments
in which radiation sources are present
The competent authority shall ensure that adequate surveillance
is undertaken outside establishments in which radiation sources
are present, and appropriate physical control shall be estab
lished to that effect. The management of the establishment
shall be responsible for compliance with any requirements of
6Personal dose records, however, will not be required for workers whose exposure is most un
likely to exceed three-tenths of the m axim um permissible dose.
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the competent authority aimed at providing radiation protection
outside the establishment. Physical control shall normally in
clude the controls of the release of radioactive waste and the
surveying and monitoring of appropriate areas outside the estab
lishment where external radiation or radioactive contamination
can occur as a result of operations within the establishment.
5. 1.3. 1. Surveying and monitoring shall include the esti
mation of external radiation levels and of contamination
of the environment, including foodstuffs, with a view to
assessing, as far as practicable, the resulting doses to
individual members of the public.
5. 2. 3. 2. The control of the release of radioactive waste
to the environment shall be such as to ensure conformity
with the Basic Safety Standards. The release of radioactive
waste to the environment at levels or in amounts above the
exemption limits fixed by the competent authority shall re
quire prior authorization and the approval of proposed pro
cedures by that authority.
5 .2 . INSPECTION AND INTERVENTION
An appropriate system of inspection shall be established by the
competent authority to supervise safety precautions both within and
outside establishments in which radiation sources are present, and
to enforce the relevant standards.
5.2. 1. The competent authority shall assume the necessary
power to intervene in cases of non-compliance with the appli
cable standards.
5 . 2 . 2 . Provision shall be made for action to be taken in the
event of accidents.
5 . 2 . 3 . Any situation which has resulted in, or is expected to
result in, doses in excess of those laid down in the Basic Safety
Standards shall be reported in a manner prescribed by the com
petent authority.
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ANNEX A
V A L U E S O F Q U A L I T Y F A C T O R (Q F )a U S E D IN D E F IN IN G
D O S E E Q U IV A L E N T S
Radiation QF
X -ra y s , y -ra y s , e lectro n s and ® "ray s ° f E m ax (i) greater than 30 keV 1 .0
(ii) less than 30 keV 1 .7
Fast neutrons and protons^ up to 10 M e V c 10
N aturally occurring a -p a r t ic le s from rad io activ e decay 10
Heavy re co il n u cle i ^ 20
a T hese values o f QF are those chosen sp e c if ic a lly for use in defining m axim um k perm issib le doses.
In th e case o f irrad iation o f the lens o f th e ey e w ith p articu la te radiation o f high LET, an ad d itional m odifying facto r m ay need to be used as w e ll as th e Q F. T h e value o f th e m odifying facto r should be 3 when th e QF is 10 or g re a ter , but should be 1 when the QF is 1. T h e values o f an appropriate m odifying facto r to be used with values o f QF betw een 1 and 10 m ay be obtained by in terpolation betw een 1 and 3.
c When th e neutron or proton energy is m ore c lo se ly d efin ed , th e values o f QF in T ab les IB and IC m ay be used.
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T A B L E IB
R E L A T IO N S H IP B E T W E E N D O S E A N D N E U T R O N
F L U X D E N S IT Y
N eutron en erg y Q F a
F lu x d en sity
e q u iv a le n t to
2 . 5 m rem / h
(n / c m 2s)
In te g ra te d flu x
e q u iv a le n t to 1 re m
(n / cm 2)
T h e r m a l 3 . 0 6 7 0 9 . 6 x 1 $
5 k e V 2 . 5 5 7 0 8 . 2 x 1 0 8
2 0 k e V 5 . 0 2 8 0 4 . 0 x 10 8
100 k e V 8 . 0' A
80 1 .2 X 1 0 s
500 k e V 1 0 . 0 30 4 . 3 X 1 0 7
1 M e V 1 0 .5 . 2 . 6 X 10 1
5 M e V 7 . 0 18 2 . 6 X 1 0 7
10 M e V 6 .5 17 2 . 4 X 1 0 7
2 0 M e V 6 . 0 10 1 . 5 X 1 0 7
50 k e V 5 . 2 7 1 . 0 X 10 1
100 M e V 4 . 7 ( 4 . 5) 6 . 3 9 . 0 X 1 0 6
2 0 0 M e V 4 . 0 4 . 5 6 . 5 X 1 0 6
5 0 0 M e V 3 . 5 2 . 2 3 . 2 X 1 0 6
1000 M e V 3 . 4 ( 3 . 5) 1 . 1 1 . 6 X 1 0 6
a T h e s e v a lu e s o f Q F a ce th o se c h o s e n s p e c i f ic a l ly fo r u se in d e fin in g m a x im u m
p e rm is s ib le d o ses. In th e c a s e o f th e le n s o f th e e y e an a d d it io n a l m o d ify in g
fa c to r m ay n e e d to b e used as w e l l as th e Q F , T h e m o d ify in g fa c to r should b e
3 w h en th e Q F is 10 or g r e a te r but should b e 1 w h en th e Q F is 1 . T h e v a lu e o f
an a p p ro p ria te m o d ify in g fa c to r to b e used w ith v a lu e s o f Q F b e tw e e n 1 and 10
m a y b e o b ta in e d by in te rp o la tio n b e tw e e n 1 and 3 .
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T A B L E IC
Q F a F O R P R O T O N E N E R G Y O F 50 M e V U P T O 1000 M e V
Energ y protons
(M eV )
Q F
' ,5 0 1 . 2
1 0 0 1 . 3
2 0 0 1 . 7
3 0 0 2 . 0
5 0 0 2 . 5
7 0 0 2 . 8
1 0 0 0 3 . 2
3 T h e s e v a lu e s o f Q F a re th o se c h o sen for use in d e fin in g m a x im u m
p e rm is s ib le d o ses. In th e c a s e o f th e le n s o f th e e y e an a d d it io n a l
m o d ify in g fa c to r should b e 3 w hen th e Q F is 10 or g r e a te r but should
b e 1 w hen th e Q F is 1 , T h e v a lu e o f an a p p ro p ria te m o d ify in g
fa c to r to b e used w ith v a lu e s o f Q F b e tw e e n 1 and 10 m a y be
o b ta in e d by in te rp o la tio n b e tw e e n 1 and 3 .
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T A B L E S IIA A N D II B
M A X IM U M P E R M IS S IB L E A N N U A L IN T A K E S IN A IR O R W A T E R
F O R S IN G L E R A D IO N U C L ID E S A P P L I C A B L E T O W O R K E R S
E N G A G E D IN R A D IA T ION W O R K A N D T O IN D IV ID U AL M E M B E R S
O F T H E P U B L IC , A N D T H E M A X IM U M P E R M IS S IB LE A C T IV IT Y
F O R E X E M P T I O N F R O M N O T IF IC A T IO N , R E G IS T R A T IO N O R
L IC E N S IN G .
Notes
1. The intakes in Tables IIA and Table IIB have been obtained by-
multiplying the relevant m axim um permissible concentration
given by the IC R P by the following standard intakes of air and
water. Air breathed by workers during work is taken as
2500 m 3/yr. Air breathed by adult individuals of the general
public is taken to be 7300 m 3/yr. Water in the form of food
or fluids taken in by adult m em bers of the general public
is taken to be 0. 8 m 3/yr. If maximum permissible concentra
tions (M PC ) are needed, they can be calculated by dividing the
m axim um permissible intakes by the standard intakes of air
and water.
2. In computing the dose to the critical organ from the given in
takes incase of the general public, it should be borne in mind
that the intakes would deliver the appropriate dose to the criti
cal organ of the standard adult. In computing the intakes for
children appropriate safety factors are to be applied to take
into account other factors such as the smaller sizes of the cri
tical organs.
3. In Table II A , third column, the organ content (qf2) giving the
maximum permissible dose has been computed in the following
way:
qf2 is the number of microcuries of a radionuclide which when
uniformly distributed throughout the appropriate critical organ
and maintained at that amount, delivers the appropriate maxi
m um permissible dose. It can be calculated from equation 3,
page 15 of the ICRP Report of Committee II (1959), substituting
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the weekly dose rate by the maximum permissible yearly dose
limit, viz.
qf2 = 5 . 6X 10'5 X ^ ^
where
m is the mass of the organ in grams
R is the maximum permissible organ dose in rems in
a year
e is the effective absorbed energy — EEF (Q F )n (in M eV )
per disintegration of a radionuclide in the organ in
question.
Values of m are given in Table 8 and of e in Tables 5 and 5a of
the ICRP Report of Committee II (1959).
4. It should be noted that these values of qf2 are calculated from
the maximum permissible yearly dose to the organ. If values
for q, the maximum permissible body burden, are to be calcuT
lated by using values of f2 given in the IC R P Report, it must
be remembered that these values of f2 apply to long-term chro
nic condition of exposure and may be misleading for calculating
body burdens used for short-term isolated intakes.
5. Noble gases apart from Rn are not included in Table IIA since
basically they can be regarded as sources of external radiation
and dealt with accordingly.
31
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T A B L E II A
(The values a re given to two significant figu res for convenience in ca s e fu rth er com putation should be req u ired , but the figu res
should be rounded off fo r d ire ct application. )
(1) (2) (3) (4) (5) (6) O )
Workers M em bers o f th e p ublic0 S ' c .3 o >
RadionuclideC rit ic a l organ a
Organcontentgiving them axim umperm issibledo se-rate
M axim um perm issible annual in tak e by inhalation during working hours b
Lim its o f annual in tak e by ingestion
Lim its of annual in tak e by in h alation
Max
imum
pe
rmis
sibl
e ac
ti
for
exem
ptio
n fro
m n
otif
aci
regi
stra
tion
or
lice
nsi
ng
(MCi) (MCi) (MCi) (MCi) (MCi)
'HSol. Body tissue 1 .2 x 103 1 . 2 x 104 2 .6 X 103 1 . 2 x 103 1000
iBe
Sol. GI (LLI) - 1 .4 0 X IO 3 -
T o ta l body 5 .6 x 102 1 .4 x 104 - 1 .4 X 103100
Insol. Lung 52 3 . 0 x 103 - 3 .0 x 102
GI (LLI) - - 1 .4 X 1 0 3 -
aT h e abbreviations G I, S , S I , ULI and LLI refer to g a stro -in testin a l t r a c t , stom ach , sm a ll in testin e , upper larg e in testin e , and low er large in testin e resp ectiv e ly ,
k T h e quarterly in tak e can be up to h a lf o f the yearly in tak e provided th at th e yearly in take is not exceed ed (see 3 . 1 . 2 . te x t) .
c For p ra c tic a l purposes th ese figures can be applied to th e population at larg e provided that th e m axim um perm issible g en e tic dose to th e w hole population is not ex cee d ed .
32
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (V)
14 r6
So l. Fat 1 .6 X 1 0 z 8 .7 X 1 0 3 6 . 6 X 1 0 2 8 .7 X 102 100
18,.9
So l.
Insol.
GI (SI)
GI (ULI)
- 1 . 3 X 1 0 4
6 .4 X 1 0 3
6 .6 X 1 0 2
4 .0 X 1 0 2
1 .3 X 103
6 .4 X 102100
n N a
Sol.
Insol.
T o ta l body
Lung
GI (LLI)
12
1
4 .3 X 1 0 2
2 .1 X 10
3 .2 x 10
2 . 4 X 10
4 . 3 X 10
2 .1 10
l i NaSo l.
Insol.
GI (SI)
GI (LLI)
- 3 .1 X 1 0 3
3 . 6 X 1 0 2
1 .5 X 1 0 2
2 .2 X 10
3 .1 X 102
3 .6 X 1010
31S i14
S o l.
Insol.
GI (S)
GI (ULI)
- 1 .4 X 104
2 .5 X 1 0 3
7 .0 X 1 0 2
1 .5 X 1 0 2
1 .4 X 1 0 3
2 . 5 X 1 0 2100
32 p
15S o l.
Insol.
Bone
Lung
GI (LLI)
3 .1
1 .2
1 .8 X 1 0 2
2 . Ox 102
1 .5 X 10
1 .8 X 10
1 .8 X 10
2 .0 X 10• 10
35 s 16
Sol.
Insol.
T estis
Lung
GI (LLI)
0 .2
15
6 .8 X 1 0 2
6 . 3 X 1 0 2
5 .0 X 10
2 .2 X 102
6 .8 X 10
6 .3 X 1010
33
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T A B L E II A (cont'd)
( 1 ) ( 2 ) (3) (4) (S) ( 6 ) (7)
17 C 1
Sol. T o ta l body 75 8. 7 X 102 6 . 6 X 10 8. 7 X 1010
Insol. Lung 3 .2 5 . 7 X 10 - 5 .7
GI (LLI) - - 4 . 6 X 10 -
n C 1
S o l. G I (S) ■ 6 .4 X 1 0 3 3 .2 X 1 0 2 6 .4 X 1 0 2100
Insol. GI (S) - 5 .1 X 1 0 3 3 .2 X 1 0 2 5 .1 X 1 0 2
42 t v -19
So l. GI (S) - 5 .0 X 1 0 3 2 .5 X 1 0 2 5 .0 X 1 0 210
Insol. GI (LLI) - 2 . 7 X 1 0 2 1 .6 X 10 2 .7 X 10
45C a20
S o l. Bone 26 8 .0 X 10 7 .3 8 .010
Insol. Lung 9 .7 3 .0 X 1 0 2 - 3 .0 X 10
G I (LLI) - - 1 . 0 x 1 0 2 -
41 Ca 20
So l. Bone 4 .2 4 . 3 X 102 4 .0 X 10 4 . 3 X 1010
Insol. G I (LLI) . - 4 .2 X 1 0 2 2 .6 X 10 4 .2 X 10
Lung 1 4 .7 X 1 0 2 - 4 .7 X 10
46 Sc 21
So l. GI (LLI) - 6 .1 X 1 0 2 3 .0 X 10 6 .1 X 10
Liver 2 .2 6 .0 X 1 0 2 - 6 .0 X 10
Insol. Lung 1 .3 6 .0 X 10 - 6 .010
GI (LLI) - - 3 .0 x 10 -
34
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T A B L E II A (cont'd)
( 1 ) ( 2 ) (3) (4) (5) ( 6 ) (7)
47 Sc21 So l.
Insol.
G I (LLI)
GI (LLI)
- 1 .5 X 103
1 .2 X 103
7 .1 X 10
7 .1 X 10
1 .5 X 102
1 .2 X 10210
48 Sc 21
So l.
In so l.
GI (LU )
GI (LLI)
- 4 .3 x 102
3 . 5 x 10*
2 .2 X 10
2 .2 X 10
4 .3 X 10
3 . 5 X 1010
« v23 vSo l.
Insol.
GI (LLI)
Lung
GI (LLI)
0 .9 3
4 .5 X 102
1 .4 X 102
2 . 3 X 10
2 . 3 X 10
4 .5 X 10
1 .4 X 1010
51Cr24
Sol.
Insol.
GI (LLI)
T o ta l body
Lung
G I (LLI)
780
60
2 . 6 x 1 0 4
2 .7 X 1 0 4
5 .6 X 1 0 3
1 .3 X 1 0 3
1 .2 X 1 0 3
2 . 6 X 1 0 3
2 .7 X 1 0 3
5 .6 X 1 0 z100
52 Mn25
Sol.
Insol.
GI (LLI)
Lung
GI (LLI)
0 .8 7
5 . 3 X 1 0 2
3 .5 X 1 0 2
3 . 8 X 1 0 2
2 . 6 X 10
2 . 4 X 10
5 .3 X 10
3 .5 X 10
3 . 8 X 10
10
So l.
Insol.
GI (LU )
Liver
Lung
GI (LLI)
6 .2
3 .6
9 .5 X 1 0 2
8. 7 X 10
1 .0 X 102
9 . 6 X 10
9 .5 x 10
8 .710
35
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T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5 ) (6) (7)
“ MnSo l.
Insol.
GI (LLI)
GI (LLI)
- 1 .9 X 103
1 .3 x 108
9 . 6 x 10
8 .0 X 10
1 .9 X 102
1 .3 X 10210
55 Fe 26 So l.
Insol.
Sp leen
Lung
19
130
2 .1 X 103
2 . 6 X 10s
6. 3 X 102 2 . 1 X 102
2 . 6 X 102100
GI (LLI) - - 1. 8 X 103 -
59 Fe 26
Sol. G I (LLI) _ . 4 . 7 X 10
Insol.
Spleen
Lung
0 .3 7
2
3. 7 X 102
1 .3 X 102
3 .7 X 10
1 .3 X 1010
GI (LLI) - - 4 .2 X 10 -
51 Co 21
Sol.
Insol.
GI (LLI)
Lung 16
8 .7 x 1 0 3
4 .0 x 102
4 .3 X 102 8 .7 X 102
4 .0 X 1010
GI (LLI) - - 3 .0 X 102 ' -
58mCo27 S o l. GI (LLI) - 4 . 5 X 104 2 . 2 X 103 4 . 5 X 1 0 3
Insol. Lung 4 .2 2 .2 X 104 - 2 .2 X 10310
GI (LLI) - - 1 .6 X 103
“ Co27 So l. GI (LLI) - 2 .1 X 103 1 . 0 x 102 2 .1 X 102
Insol.
T o ta l body
Lung
32
3
2 . 4 X 103
1 .4 X 102
2 . 4 X 102
1 .4 X 1010
GI (LLI) - - 7 .2 x 10 -
36
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) ( V
60Co21 So l. G I (LLI) - 8 . 0 X 102 3 .9 X 10 8 .0 X 10
T o ta l body 13 8. 7 X 102 - 8. 7 X 1010
Insol. Lung 1 .2 2 .2 X 10 - 2 .2
GI (LLI) - - 2 . 8 X 10 -
59 Ni 28So l. Bone 1400 1 .2 X 103 1 .6 X 1 0 2 1 .2 X 102
10Insol. Lung 110 1 .9 x 103 - 1 .9 X 102
GI (LLI) - - 1 .6 X 103 -
63NiSo l. Bone 100 1 . 6 x 102 2 .2 X 10 1 .6 X 10
10Insol. Lung 40 7 .0 x 1 0 2 - 7 .0 X 10
GI (LLI) - - 5 .7 X 1 0 2 -
28S o l. GI (LLI) - 2 .3 x 1 0 3 1 .1 X 1 0 2 2 .3 X 1 0 2
10Insol. G I (ULI) - 1 .3 X 1 0 3 8 .0 X 10 1 .3 x 1 0 2
64Cu29 S o l. GI (LLI) ~ 5 .3 X 1 0 3 2 .6 X 1 0 2 5 .3 X 1 0 2
100Insol. GI (LLI) - 2 . 6 X 103 1 .7 x 1 0 2 2 . 6 x 1 0 2
65 Zn30Sol. T o ta l body 61 2 . 6 X 1 0 2 7 .9 X 10 2 .6 x 10
Prostate 0 .1 3 .2 X 1 0 z 9. 6 x 10 3 .2 x 10
Liver 9 .5 - 1 . 0 x 10z - 10
Insol. Lung 5 .6 1 .5 X 1 0 2 - 1 .5 X 10
GI (LLI) - - 1 .4 X 1 0 2 -
37
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (7)
69m v „30 Z.n
So l. G I (LLI) 5 .4 X 1010
Prostate 0 .0 1 3 9 .5 x 102 - 9 .5 X 10
Insol. GI (LLI) - 8 .0 X 102 4 . 9 X 10 8 .0 X 10
® Z n30S o l. G I (S) _ _ 1 . 4 X 1 0 3
Insol.
Prostate
GI (S)
0 .0 1 5 1 . 8 X 104
2 .3 x 104 1 .4 X 1 0 3
1 . 8 x 103
2 .3 x 103100
S o l.
Insol.
GI (LLI)
GI (LLI)
- 5 .9 X 1 0 2
4 .7 X 1 0 2
3 .0 X 10
3 .0 X 10
5 .9 X 10
4 .7 x 1010
n Ge32
So l. GI (LLI) 2 .6 X 1 0 4 1 .3 X 103 2 . 6 X 1 0 3
Lung 84 1 .6 X 1 0 “ - 1 .6 x 1 0 3100
Insol. GI (LLI) - - 1 .3 X 1 0 3 -
73 As33 „ , So l. G I (LLI) . . 3 . 8 X 1 0 2
Insol.
T o ta l body
Lung
320
20
5 .1 X 103
9. 5 x 102
5 .1 x 102
9 .5 X 1010
GI (LLI) - - 3 . 7 X 102 -
14 As33
S o l.
Insol.
G I (LLI)
Lung 2 .2
8 .7 X 102
3 .1 X 102
4 . 2 X 10 8 .7 X 10
3 .1 X 1010
GI (LLI) - - 4 .2 X 10 -
38
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T A B L E II A (cont'd)
(1 ) (2 ) (3) (4) (5) (6 ) (V
76 As33
S o l .
In s o l.
G I (L LI)
G I (LL I)
- 3 . 2 X 102
2 . 5 X 102
L - 6 X 10
1. 5 X 10
3 . 2 X 10
2 . 5 X 1010
H as33S o l .
In so l.
G I (LL I)
G I (L U )
- 1 . 3 X 103
1 . 0 X 1 0 3
6. 6 X 10
6 . 4 X 10
1 . 3 X 102
1 . 0 X 10 210
75 S e
34 S o l . K id n e y 3 . 5 3 . 1 X 103 2 . 4 X 1 0 2 3 . 1 X 102
In s o l.
T o t a l body
Lung
98
8 . 9 3 . 1 X 1 0 2
2 . 7 X 1 0 2
3 . 1 X 1010
G I (LLI) - - 2 . 2 X 1 0 2 -
82 Br 35
S o l , T o t a l body 11 2 . 8 X 1 0 s 2 . 1 X 1 0 2 2 . 8 X 1 0 2
In s o l.
G I (S I)
G I (L L I) - 4 . 7 X 1 0 2
2 . 2 X 1 0 2
3 . 0 X 10 4 . 7 X 1010
86 Rb 37
S o l . T o t a l body 28 7 . 1 X 1 0 2 5 . 4 X 10 7 . 1 X 10
P a n c re a s 0 . 0 9 7 . 1 X 1 0 2 5 . 4 X 10 7 . 1 X 10
L iv er 2 . 2 1 . 0 X 1 0 3 - 1 . 0 X 1 0 210
In s o l. Lung 1 . 3 1 . 7 X 1 0 2 - 1 . 7 X 10
G I (LL I) “ 1 . 9 X 10 ”
39
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (7)
87 Rb31 So l. Pancreas 0. 65 1 . 2 X 10 3 8. 8 X 10 1 . 2 x 10 2
T o ta l body 220 1 . 6 X 103 - 1 . 6 x 1 0 2
Liver 16 1 . 1 X 1 0 s - 1 . 7 x 10*10
Insol. Lung 9 . 3 1 . 6 X 1 0 2 - 1. 6 X 10
GI (LLI) - - 1 . 4 X 1 0 2 -
85 mSrS o l. GI (SI) - 1 . 0 x 105 5 . 2 X 1 0 3 1.0 x 10 4
10Insol. G I (SI) - 8 . 7 x 104 5 . 4 X 1 0 3 8 . 7 X 103
85 SrSo l. T o ta l body 59 5 . 8 X 1 0 2 7 . 6 X 10 5 . 8 X 10
10Insol. Lung 5 . 2 2 . 6 X 1 0 2 - 2 . 6 X 10
GI (LLI) - - 1 . 4 X 102 -
SSlS o l. Bone 3 . 9 6 . 9 X 10 9 . 6 6 . 9
10Insol. Lung 1 . 5 8 . 7 X 10 - 8 . 7
G I (LLI) - - 2 . 2 X 10 -
30 Sr38 S o l. Bone 2 2 . 9 3 . 2 X 10 2.9 x 10"1
1Insol. Lung 0 . 7 6 1 . 4 X 10 - 1 . 4
GI (LLI) - - 2 . 8 X 10 -
>So l. GI (LLI) - 1 .1 x 1 0 3 5 .6 X 10 1 .1 x 102
10
Insol. G I (LLI) • 6 .3 X 1 0 2 3 .9 X 10 6 .3 X 10
40
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (V
92 Sr38
S o l. GI (ULI) - 1 .1 X 103 5 .4 X 10 1 .1 X 10210
Insol. GI (ULI) - 7 .3 X 1 0 2 4 .6 X 10 7 . 3 X 10
90 y 39
So l. GI (LLI) - 3 .2 X 1 0 2 1. 6 X 10 3 .2 X 1010
Insol. GI (LLI) - 2 .6 X 1 0 2 1 .6 X 10 2 .6 X 10
9im Y
39 So l. G I (SI) ■ 5 .5 X 104 2 .7 X 10 3 5 .5 x 1 0 3100
Insol. GI (S I) - 4 . 3 X 10“ 2 . 7 X 103 4 .3 x 103
91 Y39
S o l. GI (LLI) _ . 2 . 1 X 10
Bone 3. 8 8 .7 X 10 - 8 .710
Insol. Lung 1 .4 8 .0 X 10 - 8 .0
G I (LLI) - - 2 .1 X 10
92 Y 3 9 1
Sol. G I (ULI) - 9 .5 X 1 0 2 4 . 6 X 10 9 .5 X 1010
Insol. GI (ULI) - 7 . 3 X 1 0 2 4 .6 X 10 7 .3 X 10
93 Y
39 S o l. ^ GI (LLI) - 4 . 3 X 1 0 2 2 .2 X 10 4 .3 X 10
Insol. G I (LLI) - 3 .4 X 1 0 2 2 .2 X 10 3 .4 X 1010
93 Z r40
Sol. G I (LLI) - - 6 .4 X 102 -
Bone 100 3 .2 X 102 - 3 .2 X 10
Insol./
Lung 43 8. 0 X 102 - 8. 0 X 1010
G I (LLI) - - 6 .4 X 102 -
41
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T A B L E II A (cont'd)
(1) (2) (3) (4 ) (5) (6) (7)
9540 Zr
So l. G I (LLI) - - 5 .0 X 10 -
T o ta l body 18 3 .2 X 1 0 2 - 3 .2 X 1010
Insol. Lung 1 .6 8. 0 X 10 - 8 .0
GI (LLI) - - 5 .0 X 10 -
97 Zr40So l. G I (LLI) 2 . 9 x 1 0 2 1 .4 X 10 2 .9 X 10
100Insol. G I (LLI) - 2 . 3 X 1 0 2 1 .4 X 10 2 . 3 X 10
93™Nb41So l. G I (LLI) . . 3 .2 X 1 0 2 _
Bone 91 3 .1 X 1 0 2 - 3 .1 X 1010
Insol. Lung 22 4 .0 X 102 - 4 .0 X 10
G I (LU ) - - 3 .2 X 1 0 2 -
415 NbS o l. G I (LLI) - 1 .5 X 1 0 3 7 .7 X 10 1 .5 X 102
T o ta l body 38 1 .2 X 103 - 1 .2 X 1 0 210
Insol. Lung 3 .2 2 .5 X 1 0 2 - 2 .5 X 10
G I (LLI) - - 7 .7 X 10 -
11NbSo l. GI (ULI) “ 1 .5 X 104 7 .4 X 102 1 .5 X 1 0 3
100
Insol. GI (ULI) “ 1 .2 X 104 7 .4 X 102 1 .2 X 103
42
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (V
S o l. Kidney 0 . 5 6 1. 8 X 1 0 3 1 . 4 X 102 1 . 8 X 102
G I (LLI) - - 1 . 9 X 102 -10
Insol. GI (LLI) - 5 . 0 X 102 3 . 1 X 10 5 . 0 X 10
sem T c
Sol. G I (LLI) - 1. 9 X 105 9 . 6 X 10 3 1 . 9 X 104
Insol. GI (LLI) - - 8 . 0 X 103 -100
Lung 1 . 3 7 . 3 X 104 - 7 . 3 X 103
96 T c 43 iCSo l. G I (LLI) - 1 . 6 X 103 7 . 8 X 10 1 . 6 X 10 2
10
Insol. GI (LLI) - 6 . 0 X 102 3 . 8 X 10 6 . 0 X 10
9 ,m T c43 So l. G I(L L I) - 5 .8 X 10s 2 . 8 X 1C? 5 .8 X 102
Insol. Lung 9 .3 3 .8 X 102 - 3 .8 X 1010
G I (LLI) - - 1 .4 X 1 0 2 -
97 T cSo l. GI (LLI) - 2 .7 X 1 0 4 1 .4 X 1 0 3 2 .7 X 1 0 3
Kidney 13 3 .4 X 104 - 3 .2 X 1 0 310
Insol. Lung 42 7 .3 X 1 0 2 - 7 .3 X 10
G I (LLI) - - 6 .4 X 1 0 2 -
9 9 m
43S o l. GI (ULI) - 9 .5 x 1 0 4 4 . 6 X 1 0 3 9 .5 X 1 0 3
100Insol. GI (ULI) “ 3 .5 x 1 0 4 2 .2 X 1 0 3 3 .5 X 1 0 3
43
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T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5) (6) (7)
" T cS o l. GI (LLI) - 5 .3 X 103 2 . 6 x 1 0 z 5 .3 X 1 0 2
Insol. Lung 8 .9 1 .5 X 102 - 1 .5 X 1010
G I (LLI) - - 1 . 3 x 10z -
97 Ru44S o l. G I (LLI) - 5 . 8 X 103 2 . 9 X 102 5 . 8 X 102
10Insol. GI (LLI) - 4 . 4 X 103 2 . 8 X 102 4 . 4 X 102
103 Ru44So l. GI (LLI) - 1 . 3 X 102 6 .6 X 10 1 .3 X 102
10Insol. Lung 3 .1 2 .1 X 102 - 2 . 1 X 10
GI (LLI) - - 6 .4 X 10 -
105 RuS o l. G I (ULI) ■ 1 .8 X 1 0 3 8 . 8 X 10 1 . 8 X 1 0 2
10Insol. G I (ULI) - 1 .3 X 1 0 s 8 .0 X 10 1 .3 X 1 0 2
106 RuS o l. G I (LLI) - 1 .9 X 1 0 2 9 .6 1 .9 X 10
Insol. Lung 0 .6 1 .4 X 10 - 1 .41
GI (LLI) - - 9 .6 -
U3m Rh45S o l. G I (S) - 1 . 9 x 1 0 5 9 . 6 X 103 1 .9 X 104
100
Insol. GI (S) - 1 .5 X 105 9 .6 X 103 1 . 5 X 104
45 RhS o l. G I (LLI) - ' 2 . 1 X 103 1 .0 X 102 2 . 1 X 102
10Insol. GI (LLI) - 1 .3 X 103 8 .0 X 10 - 1 .3 x 102
44
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T A B L E II A (cont'd)
(1) (2) (3) (4 ) (5) (6) (V)
103 pd
46 S o l. G I (LLI) - - 2 . 7 X 102 -
Kidney 4 .1 0 3 .4 X 1 0 3 - 3 .4 X 1 0 2
10Insol. Lung 13 1 .9 X 1 0 3 - 1 .9 X i o 2
GI (LLI) - - 2 .2 X 102 -
-““’Pd46 So l. G I (LLI) ■ 1 .4 X 1 0 3 7 .0 X 10 1 . 4 x io 2
10Insol. GI (LLI) - 8. 7 X 10z 5 .6 X 10 8 .7 X 10
105.4 ,AS
S o l. GI (LLI) - 1 . 5 X 10 3 7 .8 X 10 1 .5 X i o 2
Insol. Lung 2 .9 2 .0 X 1 0 2 - 2 .0 X 1010
GI (LLI) - - 7 .7 X 10 -
i r mA gS o l. GI (LLI) ” 4 . 8 X 10z 2 . 4 X 10 4 . 8 X 10
10fnsol. Lung 1 2 . 6 X 10 - 2 . 6
GI (LLI) - - 2 . 4 X 10 -
111 Ag41 So l. GI (LLI) - 7 .1 X 102 3 .5 X 10 7 .1 X 10
10Insol. G I (LU ) - 5 .5 X 102 3 .4 X 10 5 .5 X 10
109 Cd48 So l. G I (LLI) - - 1 .4 X 102 -
Liver 14 1 .3 X 1 0 2 - 1 .3 X 10
Kidney 2 .6 1 .4 X 1 0 2 - 1 .4 X 1010
Insol. Lung 8 .4 1 .8 X 10 2 - 1 .8 X 10
G I(L L I) | - 1 .4 X 10s -
45
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T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5) (6) (V)
lism c d48
So l. GI (LU ) 2 .0 X 10
Insol.
Liver
Lung
2 .3
1 .4
8 .7 x 10
8 .7 x 10 ; 8 .7
8 .710
GI (LLI) - - 2 .0 X 10 -
115CdSol.
Insol.
GI (LLI)
GI (LLI)
- 5 .5 X 1 0 2
4 . 6 X 1 0 2
2 .7 X 10
2 .9 X 10
5 .5 X 10
4 .6 x 1010
m .49 In
So l.
Insol.
GI (ULI)
GI (ULI)
- 2 . 1 X 1 0 4
1 .7 X 1 0 “
1 .0 X 1 0 3
1 .0 X 1 0 3
2 . 1 X 1 0 3
1 .7 X 1 0 3100
114 itlIn
49So l. G I (LLI) . 2 .7 X 1 0 2 1 .4 X 10 2 .7 X 10
Kidney 0 .2 7 2 .6 X 1 0 2 - 2 .6 X 10
Spleen 0 .1 4 2 .8 X 1 0 2 - 2 . 8 X 1010
Insol. Lung 0 . 89 5 .4 X 10 - 5 .4
GI (LLI) - - 1 .4 X 10 -
n sm T49 *n
So l.
Insol.
G I (ULI)
GI (ULI)
- 5 .9 X 103
4 .7 X 1 0 3
3 .0 X 102
3 .0 X 102
5 .9 x 102
4 .7 x 1 0 2100
113 Sn50 S o l. GI (LLI) _ . 6 . 8 X 10 _
Bone 16 8 .7 X 102 - 8 .7 x 10
Insol. Lung 3 .6 1 .3 X 102 - 1 .3 X 1010
GI (LLI) - - 6 .5 x 10 -
46
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T A B L E II A (cont'd)
(1) (2) (3 ) (4) (5) (6)
125 Sn50 So l. G I (LLI) - 2 . 9 X 102 1 . 4 X 10 2 .9 X 10
Insol. Lung 0 .8 7 2 .1 X 102 - 2 .1 X 1010
G I (LU ) - 2 .2 X 102 1 .4 X 10 2 .2 X 10
122 Sb51 So l. GI (LLI) - 4 .7 X 102 2 .3 X 10 4 .7 X 10
10Insol. GI (LLI) - 3 .6 X 102 2 . 3 X 10 3 .6 X 10
124 Sb 51
S o l, G I (LLI) - 3 .7 X 102 1 .8 X 10 3 .7 X 101
Insol. Lung 0 .9 1 4 . 8 X 10 - 4 .8
GI (LLI) - - 1 .8 X 10 -
125 Sb51
So l. GI (LLI) 1 .6 X 103 8. 0 X 10 1 .6 X 102
Lung 3 .3 1 .3 X 103 - 1 .3 X 102
T o ta l body 56 1 .5 X 103 - 1 .5 X 102
10Bone 18 1 .8 X 103 - 1 .8 X 1 0 2
Insol. Lung 3 .3 6 .6 X 10 - 6 .6
GI (LLI) - - 7 .9 X 10 -
So l. Kidney 1 .8 8 .7 X 1 0 2 1 .3 X 1 0 2 8 .7 X 10
GI (LLI) - - 1 .4 X 1 0 2 -
T estis 0 .1 - 1 . 8 X 102 -10
Insol. Lung 6 3 .2 X 1 0 2 - 3 .2 X 10
GI (LLI) - - 9 .6 X 10
47
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (7)
I21mT e52
So l. Kidney 0 . 7 9 3. 3 X 102 5 . 0 X 10 3 . 3 X 10
T estis 0 . 0 3 6 3 . 5 X 102 - 3 . 5 X 10
G I (LLI) - - - - 10
Insol. Lung 2 . 6 1 . 0 x 102 - 1 . 0 x 10
G I (LLI) - - 4 . 2 X 10 -
So l. GI (LLI) - 4 . 2 X 103 2 . 1 X 102 4 . 2 X 10210
Insol. GI (LLI) - 2 . 1 X 103 1 . 4 X 102 2 . 1 X 102
129m 52 1®
So l. GI (LLI) - - 2 . 6 X 10 -
Kidney 0 . 3 2 2 . 0 X 1 0 2 - 2 . 0 X 10
T estis 0 . 0 1 6 2 . 3 X 10 2 - 2 . 3 X 10 10
Insol. Lung. 1 . 0 8 . 0 X 10 - 8 . 0
GI (LLI) - - 1. 6 X 10 -
129T e52
So l. GI (S) ■ 1. 3 X 104 6 . 6 X 102 1 . 3 X 103100
Insol. GI (ULI) - 1. 0 X 10“ 6. 6 X 102 1 . 0 X 103
i3im52 T e
S o l. GI (LLI) “ 9. 5 x 1 0 2 4 . 6 X 10 9 . 5 X 1010
Insol. G I (LLI) - 4 .7 x 1 0 2 3 .0 X 10 4 .7 X 10
132 X e
52 Sol. GI (LLI) ■ 5 .1 X 102 2 . 6 X 10 5 .1 X 1010
Insol. GI (LLI) - 2 . 6 X 102 1 .7 X 10 '2 .6 X 10
48
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4 ) (5 ) (6) (V
126 I53
S o l.
Insol.
Thyroid
Lung
G I (LLI)
0 .2 1
4 .7
1 .8 X 10
8 .0 X 102
1 .4
7 .4 X 10
1 .8
8 .0 X 101
1 2 9 t
53So l.
Insol.
Thyroid
Lung
GI (L U )
0 .4 9
10
4 .0
1 .8 X 1 0 2
3 .0 X 1 0 1
1 .7 X 1 0 2
4 .0 X 10-1
1 .8 X 101
131 .53 1
S o l.
Insol.
Thyroid
G I (LU )
Lung
0 .1 5
2 .8
2 . 1 X 10
8 .0 X 102
8 . 0 X 102
1 .6
5 .1 X 10
2 .1
8 . 0 X 10
8 .0 X 10
1
132 J
53S o l.
In so l,
Thyroid
G I (U LI)
0 .0 5 2 5 .9 X 102
2 . 3 X 2 0 3
4 . 5 X 10
1 . 4 X 1 0 2
5 .9 X 10
2 . 3 X 1 0 210
133 T53
So l.
Insol.
Thyroid
G I (LLI)
0 .0 6 2 8 .0 X 10
5 .2 X 1 0 2
6 .0
3 .3 X 10
8 .0
5 .2 X 1010
134 T 5 3 1
S o l.
Insol.
Thyroid
GI (S)
0 .0 4 1 1 .2 X 1 0 3
8 .0 X 1 0 3
9 .6 X 10
4 . 8 X 102
1 .2 X 1 0 2
8 .0 X 1 0 210
135 j
53 S o l.
Tnsol.
Thyroid
CT (LLr)
0 .0 6 5 2 . 6 X 102
S. 7 X lO 2
1 . 9 X 10
5 . 6 X 10
2 .6 X 10
8 .7 X 1010
49
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4) (5 ) (6 ) 0 )
131 Cs55
Sol. T o tal body 680 2 . 6 X 104 1 . 9 X 1 0 3 2 . 6 X 103
Insol.
Liver
GI (LLI)
60 3 . 2 X 10 4
1 . 4 X 1 0 2
3 . 2 X 1 0 3100
Lung 35 8 . 0 X 1 0 3 - 8 . 0 X 1 0 2
Sol,
Insol.
GI (S)
GI (ULI)
- 8 . 1 X 1 0 4
1 . 5 X 104
4 . 4 X 10 3
8. 8 X 102
8 . 1 X 1 0 3
1 . 5 X 1 0 3100
Sol.
Insol.
T o tal body
Lung
18
1 . 5
9 . 5 X 10
3 . 2 X 10
6 . 9 9 . 5
3 . 210
GI (LLI) - - 3 . 2 X 10 -
I s C sSol. Liver 22 1 . 2 X 103 8. 8 X 10 1 . 2 X 102
Spleen 1 . 9 1 . 3 X 103 9 . 6 X 10 1 . 3 X 102
T o ta l body 300 1 . 5 X 103 1 . 0 X 102 1 . 5 X 102 10
Insol. GI (LLI) - - 1 . 8 X 10 2 -
Lung 13 2 . 3 X 102 - 2 . 3 X 10
136 Cs 55Sol. T o ta l body 30 9 . 5 X 1 0 2 6. 8 X 10 9 . 5 X 10
100
Insol. Lung 2 . 4 4 . 2 X 1 0 2 - 4 . 2 X 10
GI (LLI) - - 5 . 2 X 10 -
50
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T A B L E II A (cont'd)
(1 ) (2 ) (3 ) (4) (5 ) (6 ) (7)
>S o l. T o ta l body 33 1 . 6 X 10z 1 .2 X 10 1 .6 X 10
Liver 3 .5 - 1 .4 X 10 -
Sp leen 0 .3 4 - 1 .8 X 10 -10
M uscle 14 - 1 . 9 X 10 -
Insol. Lung 2 3 .6 X 10 - 3 .6
G I (LLI) - - 3 .5 X 10 -
ls lBa56 _ ,
So l. G I (LLI) " 2 . 9 X 1 0 3 1 .4 X 1 0 2 2 . 9 X 1 0 210
Insol. Lung 4 . 4 8 .7 X 1 0 2 - 8 . 7 X 10
GI (LLI) - - 1 .4 x: i o 2 -
140 Ba56
S o l. G I (LLI) _ _ 2 . 1 X 10 _
Bone 2 .6 3 .2 X 102 - 3 .2 X 1010
Insol. Lung 0 .6 0 1 .1 X 102 - 1 .1 X 10
G I (LLI) - - 2 .0 X 10 -
140 La57 S o l. G I (LLI) ■ 3 .9 X 1 0 2 1 .9 X 10 3 .9 X 10
10Insol. G I (LLI) - 3 . 1 X 1 0 2 1. 9 X 10 3 . 1 X 10
141 C e58 ^
So l. G I (LLI) _ 1. 5 X 103 7 . 0 X 10 1 . 5 X 102
Liver 7 . 9 1 . 1 X 103 - 1 . 1 X 102
Bone 14 1 . 5 X 10s - 1. 5 X 102 10
Insol. Lung 4 . 7 3 . 9 X 102 : 3..9 X 10
G I (LLI) - - 7 . 2 X 10 -
51
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T A B L E II A (cont'd)
(1 ) (2 ) (3) (4) (5) (6) (7)
“ sC eSo l.
Insol.
GI (LU )
GI (LLI)
- 6 .4 X 1 0 2
5 .2 X 1 0 2
3 .2 X 10
3 .2 X 10
6 .4 X 10
5 .2 X 1010
l44C e58UeSo l. G I (LLI) _ . 9 . 6
Insol.
Bone
Lung
1 .7
0 .6 4
2 .7 X 10
1 . 6 X 10; 2 .4
1 .61
G I (L U ) - - 9. 6 -
I42 D f59 PrS o l.
Insol.
GI (LLI)
GI (LU )
- 4 . 8 X 102
3 .9 X 102
2 . 4 X 10
2 . 4 X 10
4 . 8 X 10
3 .9 X 1010
S o l. GI (L U ) - 8. 0 X 1b2 3 . 9 X 10 8. 0 X 10
Insol. Lung - 4 . 4 X 102 - 4 .4 X 1010
GI (LLI) - - 3 . 9 X 10 -
60S o l. G I (LLI) _ 9 .5 x 1 0 2 4 . 9 X 10 9 ,5 X 10
Insol.
Liver
GI (LLI)
4 .5 8 .7 x l o 2
4 .9 X 10
8 .7 X 1010
Lung 2 .8 5 .7 X 1 0 2 - 5 ,7 X 10
149 Nd 60So l.
Insol.
G I (LLI)
G I (ULI)
.
-
4 .5 x 1 0 3
3 .6 X 1 0 3
2 . 2 X 1 0 2
2 . 2 X 1 0 2
4 .5 X 1 0 z
3 . 6 X 1 0 2100
52
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4 ) (5) (6) (7)
*61 Pm ‘So l. G I (LLI) - - 1 .8 X 102 -
Bone 31 1 . 6 X 102 - 1 .6 X 1010
Insol. Lung 12 2 . 4 X 102 - 2 . 4 X 10
GI (LLI) - - 1 .8 X 102 -
149 Pm 61So l. G I (LLI) - 7 .1 X 102 3 . 5 X 10 7 .1 X 10
10Insol. G I (LLI) 5 .6 X 102 3 .5 X 10 5 .6 X 10
« SmS o l. Bone 9. 5 X 1 0 " Z 1 .7 X 1 0 " 1 4 . 6 X IO 1 .7 X 10"2
1Insol. Lung 0 .0 3 6 6 .4 X 1 0 ' 1 6 .4 X 1 0 "2
G I (LLI) - - 5 .5 X 10 -
151 Sm 62
Sol. GI (LLI) 3 .0 X 1 0 2
Bone 84 1 .6 X 1 0 2 - 1 .6 X 1010
Insol. Lung 20 3 .5 X 1 0 2 - 3 .5 X 10
GI (LLI) - - 3 .0 X 1 0 2 -
153 Sm 62
Sol. G I (LLI) - 1 .2 X 1 0 3 6 .2 X 10 1 .2 X 10210
Insol. GI (LLI) - 1 .0 X 1 0 2 6 .2 X 10 1. 0 X 102
So l. GI (LLI) - 1 . 0 X 103 5 .0 X 10 1 .0 X 10210
( 9 .2 hr) GI (LLI - . 8 .0 X 102 5 .0 X 10 ■ 8 .0 X 10In s o l.
53
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (V)
l52Eu63 So l. GI (LLI) - - 6 .1 X 10 -
(13 yr)Kidney 1 .0 3 .1 X 10 - 3 .1
1Insol. Lung 2 .5 4 .6 X 10 - 4 .6
G I (LLI) - - 6 .1 x 10 -
154 Eu63S o l. GI (LLI) - - 1 .8 X 10 -
Kidney 0 .3 3 9 .5 - 9 .5 X 10"1
Bone 4 .1 9 .5 - 9 . 5 X 10"11
Insol. Lung 0 .9 7 1. 8 X 10 - 1 .8
GI (LLI) - - 1 .8 X 10 -
155 „ 63 EU
S o l. GI (LLI) ' - - 1 . 6 X 102 -
Kidney ‘ 3 2 .3 X 102 - 2 .3 X 10
Bone 39 2 . 5 X 102 - 2 .5 X 1010
Insol. Lung 8. 8 1. 8 X 102 - 1 .8 x 10
GI (LLI) - - 1. 6 X 102 -
« jG dSo l. GI (LLI) _ 1 .7 X 102 -
Bone 47 5. 6 X 1 0 2 - 5 . 6 X 1010
Insol. Lung 8 .5 2 .3 X 1 0 2 - 2 .3 X 10
GI (LLI) - 1. 7 X 102 -
' « GdSo l. GI (LLI) _ 1 .2 X 1 0 3 6 .2 X 10 1 .2 X 1 0 2
10Insol, GI (LLI) - 1 .0 X 1 0 3 6. 2 X 10 1 .0 X 1 0 2
54
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1 ) (2 ) (3) M) (5) (6 ) (7 )
160 Tb
® So l. GI (LLI) - - 3 .5 X 10 -
Bone 10 2 . 5 x 102 - 2 .5 X 1010
Insol. Lung 1 .7 8 .0 X 10 - 8 .0
GI (LLI) - - 3 .6 X 10 -
S o l. GI (ULI) - 6 .4 x 103 3 .2 x 102 6 . 4 x 1 0 210
Insol. GI (ULI) - 5 .2 x 1 0 3 3 .2 x 1 0 2 5 .2 X 102
166 Dy 66 7S o l. G I (LLI) - 6 .1 x 1 0 Z 3 .0 X 10 6 . 1 x 10
10Insol. GI (LLI) - 4 .9 X 1 0 2 3 .0 X 10 4 .9 x 10
166H°
S o l. GI (LLI) - 5 .0 x 1 0 2 2 . 5 x 10 5 .0 X 1010
Insol. GI (LLI) ■ 4 .1 X 1 0 2 2 .5 X 10 4 .1 X 10
f 8’ ErS o l. GI (LLI) - 1 .5 x 1 0 3 7 .4 x 10 1 .5 X 1 0 2
10Insol. Lung 3 .8 9 .5 x 1 0 2 - 9 .5 X 10
GI (LLI) - - 7 .4 X 10 -
111 Er 68So l. GI (ULI) - 1 . 8 x 1 0 3 8. 8 X 10 1 . 8 x 1 0 2
10Insol. G I (ULI) 1 1 . 5 X 1 0 3 8 .8 x 10 1.5 x 1 0 2
55
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1 ) (2) (3 ) (4 ) (5 ) (6) (V)
™ T mS o l. GI (LLI) - - 3 .7 X 10 -
Bone 6 .5 8. 7 X 10 - 8 .71
Insol. Lung 2 .5 8 .7 X 10 - 8 .7
GI (LLI) - - 3 .7 X 10 -
17e9TmS o l. G I (LLI) - - 4 .1 X 102 -
Bone 73 2 . 8 X 102 - 2 .8 X 1010
Insol. Lung 28 5. 8 X 102 - 5 . 8 X 10
G I (LLI) - - 4 . 1 X 102 -
175 y b
S o l. GI (LLI) * 1 .8 X 103 8 .8 X 10 1 . 8 X 102
10Insol. G I (LLI) * 1 .5 X 103 8 . 8 X 10 1 .5 X 102
\ >S o l. G I (LLI) _ 1 . 6 X 103 8 .0 X 10 1 . 6 x 102
Insol. GI (LLI) 1 .3 X 103 8 .0 X 10 1 .3 x 102 10
Lung 5 .2 1 .8 X 103 - 1 .8 X 102
181 Hf
S o l. GI (LLI) - - 5 .6 X 10 -
Sp leen 0 .5 0 9 .5 X 10 - 9 .510
Insol. Lung 2 .9 1 . 8 X 102 - 1 . 8 x 10
G I (LLI) - - 5 .6 X 10 -
* T a •
S o t G I (LLI) - 3 .2 X 10 ..Liver 2 .6 9 .5 X 10 - 9 .5
10Insol. Lung 1 .5 5 .5 X 10 - 5 .5
GI (LLI) - - 3 .2 X 10 -
56
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5) (6) (7)
181 W 74
S o l. GI (LLI) 5 . 8 X 1 0 3 2 . 9 x 1 0 2 5 .8 X 1 0 210
Insol. Lung 9 .6 3 .1 X 1 0 2 - 3 .1 X 10
GI (LLI) - 2 . 6 X 1 0 2 -
So l. GI (LU ) “ 1 .9 X 1 0 3 9 .6 X 10 1. 9 X 10210
Lung 6 2 . 8 X 1 0 2 - 2 .8 X 10
G I (LLI) - - 8. 8 X 10 -
181 W 74
So l. GI (LLI) - 1 .1 X 103 5 .4 X 10 . 1 . 1 x 10210
Insol. GI (LLI) - 8 .0 X 102 5 .0 X 10 8 .0 x 10
‘ 75 R eSo l. GI (LLI) _ _ 4 . 5 X 1 0 z .
T o ta l body 82 6 .4 X 1 0 3 - 6 .4 X 1 0 210
Insol. Lung 8 .4 3 .9 X 1 0 2 - 3 .9 X 10
GI (LLI) - - 2 .2 X 1 0 z -
Sol. GI (LLI) - 1 .5 X 1 0 3 7 . 4 X 10 1 .5 X 1 0 210
Insol. GI (LLI) - 6 .0 X 1 0 z 3 .8 X 10 6 . 0 X 10
“ s Re 5 So l. GI (LLI) - - 2 . 0 X 103 -
Skin 280 2 . 3 x 10“ 2 .2 X 103 2 .3 X 103
Insol. Lung 70 1 . 2 x 103 - 1 .2 X 102103
GI (LLI) - - 2 .0 X 1 0 3 -
57
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T A B L E II A (cont'd)
(1) (2 ) (3) (4 ) (5) (6) (7)
*75 ReSol. GI (LLI) - 1 .0 X 103 5 .0 X 10 1 .0 X 102
10Insol. G I (LLI) ■ 4 . 0 X 102 2 .5 X 10 4 .0 X 10
185 _ 76 OS
So l. GI (LLI) - 1 .2 x 103 5. 9 X 10 1 .2 x 102
Insol. Lung 2 .9 1 .2 X 102 - 1 . 2 x 1010
GI (LLI) - - 5 . 3 X 10 -
m 0 s
76 So l. GI (LLI) - 4 .0 X 104 2 . 0 X 103 4 .0 X 103
Insol. Lung 6 .4 2 .3 X 10“ - 2 .3 X 103100
GI (LLI) - 1 . 9 x 103 -
191 Os16 Sol. GI (LLI) - 2 . 7 X 103 1 .4 X 102 2 .7 X 102
Insol. Lung 7 1 .0 X 1 0 3 - l . O x 10210
GI (LLI) - - 1 . 3 X 102 -
193 Os7 6
So l. GI (LLI) - 9 .5 X 1 0 2 4 .7 X 10 9 .5 X 1010
Insol. GI (LLI) - 6 .8 X 10z 4 .2 X 10 6 .8 X 10
190 if77
So l. GI (LLI) - 3 .2 X 1 0 3 1 .6 x 10z 3 .2 X 10z
10Insol. Lung 5 .2 1 . 0 x 10 3 - 1 . 0 X 1 0 2 •
GI (LLI) - ~ 1 . 4 X 10 2 "
58
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (7)
192 Ir77
S o l. G I (L LI) 3 .2 X 10
Kidney 0 .5 3 .1 X 1 0 2 - 3 .1 X 10 10
Insol. Lung 1 .4 6 .4 X 10 - 6 .4
G I (LLI) - - 3 . 0 X 10 -
194 Ir 77
S o l. G I (L U ) - 5 .5 X 1 0 2 2 .7 X 10 5 .5 x 10
10Insol. G I ( LLI) _ 5 .9 X 1 0 2 2 . 4 X 10 3 .9 X 10
191 pt
78 So l. G I (LL I) 1 .9 X 1 0 3 9 .6 x 10 1 .9 X 1 0 2
10Insol. G I (LLI) 1 .4 X 1 0 3 8. 8 X 10 1 .4 X 1 0 2
193m Pt78 rLS o l. G I (LLI) 1 .8 X 1 0 “ 8. 8 X 102 1 .8 X 1 0 3
Insol. GI (LLI) - 1 .3 X 1 0 4 8 .0 X 102 1 .3 X 1 0 3 100
■Luflg 2B 1 , 6 X 3 0 4 - 1 .6 X 1 0 3
193pt
18 So l. Kidney 18 2 .6 X 1 0 3 7 .5 X 1 0 2 2 .6 X l o 2
Insol. Lung 44 8 .0 X 1 0 2 - 8 .0 X 10 10
GI (LLI) - - 1 .2 X 1 0 3 -
i9 imPi
78So l. G I (ULI) - 1. 6 X 104 8 .0 X 1 0 2 1. 6 X 103
100
Insol. GI (ULI)
'
1 .2 X 104 7 .4 X 1 0 2 1 . 2 x lo 3
5 9
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
( 1 ) ( 2 ) (3) (4 ) (5) ( 6 ) (7 )
131 p t 78
Sol.
Insol.
GI (LLI)
GI (LLI)
1. 9 X 103
1 .4 x 103
9 . 6 x 10
8 .8 x 10
1 .9 x 1 0 2
1 .4 x 1 0 2100
196 A U 79
Sol. GI (LU ) - 2 . 6 X 1 0 3 1 .3 x 102 2 .6 x 1 0 2
Insol. Lung 4 1 .5 X 1 0 3 - 1 .5 x 1 0 2 10
GI (LLI) - - 1 . 2 x 102 -
198 Au79 Sol.
Insol.
GI (LLI)
GI (L U )
- 8 . 0 X 102
5 .9 X 102
4 .1 x 10
3 .7 X 1 0 ’
8 .0 x 10
5 .9 X 1010
*79 AUSol.
Insol.
GI (LLI)
GI (LLI)
- 2 . 7 X 103
2 .0 x 103
1 .4 x 102
1 .3 x 102
2 .7 X 102
2 .0 X 10210
191 m ,.80 H S
Sol.
Insol.
Kidney
GI (LLI)
1 .4 1 .8 X 1 0 3
2 .1 X 1 0 3
1 .5 X 1 0 2
1 . 4 x 1 0 2
1 . 8 x 102
2 .1 X 10210
I97 H o 80 “ 8
Sol.
Insol.
Kidney
GI (LLI)
5 .9 2 .9 X 1 0 3
6 .2 X 1 0 3
2 . 4 X 1 0 2
3 .9 X 1 0 2
2 .9 X 10 2
6 .2 X 102
100
DOX
Sol.
Insol.
Kidney
Lung
1 .7
4 .9
1 .8 X 1 0 2
3 .1 x 1 0 2
1 .4 X 10 1 .8 X 10
3 .1 x 1010
GI (LLI) - - 8 . 8 X 10 -
60
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (eont'd)
(1) (2 ) (3 ) (4) (5 ) (6)
200 ' j ’ j
81 Sol.
Insol.
GI (LLI)
GI (L U )
- 2.6 X 1 0 3
2 . 8 X 1 0 3
3 .5 X 1 0 2
1 .8 X 1 0 2
6.6 X 1 0 2
2 . 8 X 1 0 2100
201 j j 81 Sol.
Insol.
GI (LLI)
GI (LLI)
- 5 .0 X 1 0 3
2 .2 X 1 0 3
2 . 5 X 1 0 2
1 .4 X 1 0 2
5 .0 X 1 0 2
2 .2 X 1 0 2100
202 T I
81 Sol.
Insol.
GI (LU )
Lung
GI (LLI)
3 .1
1 .9 X 1 0 3
6 .0 X 1 0 2
9 .6 X 1 0 s
5 . 6 X 10
1 .9 X 1 0 2
6. 0 X 1010
204 -p j
81 Sol.
Insol.
GI (LLI)
Kidney
Lung
GI (L U )
1
3 .4
1 .8 X 1 0 3
1 .5 X 1 0 3
6.6 X 10
- 8 .8 X 10
4 . 9 X 10
1 .8 X 1 0 2
1 .5 X 1 0 2
6 .610
203pk82
Sol.
Insol.
GI (LLI)
GI (LLI)
- 6 .3 X 1 0 3
4 .5 X 1 0 3
3 .1 X 1 0 2
2 . 8 X 1 0 2
6 .3 X 1 0 2
4 .5 X 1 0 210
2“ pbSo l.
Insol.
Kidney
T o tal body
Lung
GI (LLI)
0 .0 2 5
0 .0 3 4
3 . 1 X 1 0 ' 1
6 .0 X 10-1
1 .1 X lO’1
9 . 6 X 1 0 '2
1 .4 X 102
3 . 1 X 10"2
6 .0 X 1 0 -20 .1
61
This publication is no longer valid Please see http://www-ns.iaea.org/standards/
T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) c n
M PbS o l. Kidney 0 .0 0 3 1 4 . 4 X 10 1 .6 X 10 4 .4
Insol.
GI (LLI)
Lung 0 .0 1 0 4 . 8 X 10
1 .5 X 10
4 .8i
G I (LLI) - - 1 .4 X 10 ' -
2>Sol. GI (LLI) - 3 .0 X 10
Insol.
Kidney
Lung
0 .4 3
1 .0
4 .7 X 1 0 2
3 .6 X 1 0 2
4 .7 X 10
3 .6 X 1010
GI (LLI) - - 3 . 0 X 10 -
CO
C/3 o GI (LLI) - - 5 .1 x 10 -
Insol.
Kidney
Lung
0 .7 6
1 .9
4 .2 X 102
3 .4 X 10
4 .2 X 10
3 .410
GI (LLI) - - 5 .0 x 10 -
210 B i
So l. GI (LLI) _ 3 .3 X 10
Insol.
Kidney
Lung
0 .0 1 3
0 .0 3 2
1 .6 X 10
1 .5 X 10
l . ■:
1 .51
GI (LLI) - - 3 .3 x 10 -
212B i
83 So l. GI (S) - - 2 . 8 X 102 -
Kidney 0 .0 0 3 0 2 .4 X 102 - 2 .4 X 1010
Insol. Lung 0 .0 1 0 5 .0 X 102 - 5 .0 X 10
GI (S) - - 2 . 8 X 102 -
62
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T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5) (6) (V
210 Po84
So l. Sp leen 0 .0 0 2 1 .2 5 . 8 X 1 0 ' 1 1 .2 X 1 0"1
Kidney 0 .0 0 4 5 1 .2 - 1 .2 X 100 .1
Insol. Lung 0 .0 1 5 5 .0 X 1 0 '1 - 5 .0 X 1 0 '2
GI (LLI) - - 2 .3 x 10 -
211 A f85 M
So l. Thyroid 0 .0 0 0 4 7 1 .8 X 10 1 .4 1 .8
Ovary 0 .0 0 0 0 3 1 - 1 .4 -0 .1
Insol. Lung 0 .0 1 1 8 .7 X 10 - 8 .7
G I (ULI) - - 5 .8 X 10 -
220 R n d 86Lung - 7 . 3 X 1 0 2 - 7 . 3 X 10 10
Lung - 7 . 3 X 1 0 2e - 7 . 3 X 1 0 e 0 . 1
2>88So l. Bone 0 . 0 3 9 4 . 3 5 . 8 X 1 0 " 1 4 . 3 X 1 0 " 1
1
Insol. Lung 3 X 1 0 ‘ 3 6 . 0 x 1 0 ' 1 6 . 0 X 1 0 -2
T h e daughter e lem en ts o f Z20Rn and 222Rn are assumed present to th e exten t they occur in unfiltered a ir . For a l l other isotopes the daughter e lem en ts are not considered as part o f th e in tak e and if present they must be considered on th e basis o f th e rules for m ixtures (see Annex B).
6 T hese figures have been provisionally adopted because in ce rta in industrial applications it has been found im p ra c tica b le to apply th e figures presented in th e report o f ICRP, C o m m ittee II (1 9 5 9 ) .
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6 ) (7)
224 Ra 88So l. G I (LLI) 3 .4
Bone 0 .0 3 9 1 .4 X 10 1 .8 1 .41
Insol. Lung 0 .0 0 2 9 1 .8 ■- 1 .8 X 1 0 ’ 1
GI (LLI) - - 4 .2 -
226 RaSoL Bone 0 .1 7 .1 X 1 0 '2 9 .6 X 1 0 " 3 7 .1 X 1 0 ‘ 3
Insol. Lung 0 .0 0 7 6 1 .3 X 1 0 " 1 - 1 . 3 x 1 0 - 2 0 .1
G I (LLI) - - 2 . 6 X 10 -
228 Ra“ So l. Bone 0 .0 5 8 1 .7 X 1 0 " 1 2 .2 X 1 0 " 2 1 .7 x 1 0 -2
Insol. Lung 0 .0 0 5 2 9 .5 x 1 0 "2 - 9 .5 x 1 0 '30 .1
G I (L U ) - - 2 .0 X 10 -
227 A c89
So l. Bone 0 .0 1 1 5 .8 X 1 0 '3 1 .5 X 1 0 "1 5 . 8 x 1 0 '4
Insol. Lung 0 .0 0 3 6 6 .5 X 1 0 '2 - 6 .5 x 1 0 -30 .1
GI (LLI) - - 2 . 4 X 102 -
228A c89
S o l. G I (ULI) _ 7 .0 X 10 _
Bone 0 .0 1 1 2 .1 X 102 - 2 . 1 x 10
Liver 0 .0 2 6 1 .9 X 102 - 1 .9 x 10 1
Insol. Lung 0 .0 0 5 2 4 .2 X 10 - 4 .2
G I (ULI) - - 7 .0 x 10 -
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T A B L E II A (cont'd)
(1 ) (2 ) (3 ) (4) (5) (6) (7)
™ T h90
Sol. GI (LLI) 0 .0 3 1 .4 X 10
Bone 0 .0 1 1 8 .7 X 1 0 " 1 - 8. 7 X 10"2
1Insol. Lung 0. 0036 4 .5 X 1 0 ' 1 - 4 .5 X 1 0 ‘ 2
GI (LLI) - - 1 .4 X 10 -
228 T h90
So l. Bone 0 .0 1 1 2 .3 X 10~2 5 .8 2 .3 X 1 0 -3
0 .1Insol. Lung 3. 5 X 10"3 1 .5 X 1 0 ‘ 2 - 1 .5 x 1 0 ‘ 3
GI (LLI) - - 1 . 0 x 10 -
So l. Bone 0 .0 4 6 5. 6 X 1 0 ‘ 3 1 .4 5 .6 X 1 0 "4
Insol. Lung 0 .0 1 7 2 .6 X 1 0 '2 ' 2 . 6 X 1 0 ‘ 3 0 .1
GI (LLI) - - 2 . 6 X 10 -
231 T h90
So l. G I (LLI) - 3 . 7 X 103 1 . 8 X 1 0 z 3 .7 X 102
10Insol. GI (LLI) - 3 .0 x 1 0 3 1 . 8 x 1 0 2 3 .0 X 102
232 T h f 90
So l. Bone 0 .0 4 1 4 .8 X 1 0 '3 1 .2 4 .8 X 1 0 - 4
Insol. Lung 0 ,0 1 8 2 .9 X 1 0 ' 2 - 2 .9 X 1 0 " 3 0 .1
GI (LLI) - - j 3 .0 X 10 -
f T h e a c t iv ity v alues for 232Th are p ro v is io n a l. A lthough c a lcu la tio n s and a n im a l ex p erim en ts suggest th at 232T h , i f in je c te d in trav en o u sly , is perhaps as hazardous as Pu and in d ic a te th e values listed ab o v e , e x p e r ie n ce to d ate has suggested th a t in in d u stria l c ircu m sta n ce s th e hazard o f 232Th is not m uch g re a ter than th a t o f U -n a t. T h e re fo re , pending further in v estig a tio n , a qu arterly in ta k e by in h a la tio n o f 2 x l 0 " 2 jiC i o f 232Th for workers d ire c tly engaged in ra d ia tio n work during working hours is re c o m m end ed as prov ision al le v e l .
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (V)
234 Th90
Sol. GI (LLI) _ 1 .4 X 10
Bone 2 .4 1 0 2 - 1 .5 X 101
Insol. Lung 0 .9 3 10 - 8 .0
GI (LLI) - - 1 .4 X 10 -
x h N a tg90
So l.
Insol.
230 Pa
91 Sol. GI (LLI) - - 1 . 9 X 102 -
Bone 0 .0 3 4 4 .2 - 4 .2 X 1 0 " 1
2 .0 X 1 0 '11
Insol. Lung 0 .0 1 4 2 .0 -
GI (LLI) - - 2 . 0 X 1 0 2 -
231 Pa9i raSo l. Bone 0 . 0 1 5 2 . 8 x 1 0 " 3 7 . 0 X 1 0 " 1 2 . 8 X 1 0 ' 4
0 . 1Insol. Lung 0 . 0 1 6 2 . 7 x 1 0 ' 1 - 2 . 7 X 1 0 - 2
GI (LLI) - - 2 . 2 X 10 -
233 PaSo l. GI (LLI) - - 9 . 6 X 10 -
Kidney 1 . 7 1 . 5 X 1 0 3 - 1 . 5 X 1 0 2
10
Insol. Lung 4 . 7 4 . 4 X 1 0 2 - 4 . 4 X 10
GI (LLI) - - 9 . 6 X 10 -
8 S e e T a b le II B.
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T A B L E II A (cont'd)
(1 ) (2) (3) (4) (5) (6) (V)
230 tt h 92 U
So l. Kidney 0 .0 0 0 7 2 7 . 3 X 1 0 ' 1 1 .9 7 .3 X 1 0 'z
Insol. Lung 0 .0 0 2 4 7 .1 X 1 0 " 1 - 2 .8 X 1 0 '2 1
GI (LLI) - - 3 .7 -
232 r j h
S o l. Bone 0 .0 0 9 1 2 .6 x 1 0 " 1 6 .7 X 1 0 '1 2 .6 X l O '2
Insol. Lung 0 .0 0 4 6 .9 X 10~2 - 6 .9 X 1 0 ‘ 3 0 .1
GI (LLI) - - 2 .3 X 10 -
2 33 u h
92 So l. Bone 0 .0 4 4 1 .3 3 .4 1 .3 X 1 0 " 1
Insol. Lung 0 .0 1 7 3 .0 X 1 0 "1 - 3 .0 X 1 0 ‘ 2 1
G I (LLI) - - 2 . 6 X 10 -
2 34 TT h 92 U
S o l. Bone 0 .0 4 6 1 .4 3 .4 1 .4 X 1 0 '1
In so l. Lung 0 .0 1 7 3 . 0 x 1 0 ' 1 - 3 . o y l o - 2 1
GI (LLI) - - 2 .6 X 10 -
235 u h 92
So l. Kidney 1 .9 X 1 0 "3 1 .2 3 .0 1 .2 X 1 0 '1
Bone 0 . 0 4 8 1 . 5 - 1 . 5 X 1 0 ' 1
1Insol. Lung 0. 0 1 8 3 . 2 X 1 0 ' 1 - 3 . 2 X 1 0 ' 2
G I (LLI) - - 2 . 2 X 10 -
Because o f th e c h e m ic a l to x ic ity o f natural uranium , 238 U , 236 U or 235 U in soluble form , the in h alation o f uranium o f any isotopic com position should not ex cee d 2 .5 mg o f soluble uranium in one day, nor th e ingestion o f soluble uranium in one d a y e x c e e d 150 m g.
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T A B L E II A (cont'd)
(1 ) (2) (3 ) (4) (5) (6) (7)
236 t t h 92 U
So l. Bone 0 .0 4 7 1 .5 3 .6 1. 5 X 10"1
, Insol. Lung 0 .0 1 8 3 .1 X 1 0 ' 1 - 3 .1 X 1 0 '2
G I (LU ) - - 2 .7 X 10 -
239ZU hSo l. K idney 3 .1 X 1 0 " 4 1 . 8 X 1 0 " 1 4 . 7 X 1 0 " 1 1 . 8 X 1 0 " 2
Insol. Lung 0 .0 2 3 .4 X 1 0 '1 - 3 .4 X 1 0 '2
GI (LLI) - - 2 . 8 X 10 -
n Nat92
Sol.
Insol.
240U92So l. GI (LLI) - 5 . 5 X 102 2 .7 X 10 5 .5 X 10
Insol. GI (LLI) - 4 . 4 X 102 2 .7 X 10 4 . 4 X 10
237 Np93 So l. Bone 0 .0 4 4 1 .0 X 1 0 '2 2 .5 1 .0 X 1 0 ‘ 3
0 .1Insol. Lung 0 .0 1 7 3 . 0 x 1 0 "1 - 3 .0 X 1 0 "2
G I (LLI) - - 2 . 8 X 10 -
239 Np93 So l. G I (LLI) 2 .1 X 1 0 3 1 . 0 X 102 2 . 1 X 1 0 2
10Insol. G I (LLI) ~ 1 .7 X 1 0 3 1 .0 X 10z 1 .7 X 1 0 2
S e e T a b le II B.
6 8
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T A B L E II A (cont'd)
( 1 ) (2) (3) (4) (5) (6 ) (V)
’ 5 P U
So l. Bone 0 .0 3 9 4 .8 X 10~ 3 4 .0 4 .8 X 10~4
Insol. Lung 0 .0 1 5 8 .7 X K T 2 - 8 .7 X 10“3 0 .1
G I (LLI) - - 2 .2 X 10 -
239 pu94 Sol. Bone 0 .0 4 1 4 .3 x 1 0 -3 3 .6 4 .3 X 1 0 ~4
Insol. GI (LLI) - - 2 .3 X 10 - 0 .1
Lung 0 .0 1 6 9. 5 x 1 0 "2 - 9 . 5 X 1 0 '3
240 Pu94
So l. Bone 0 . 041 4 . 3 X 1 0 " 3 3 .6 4 .3 X 1 0 “ 4
Insol. Lung 0 .0 1 6 9 .5 X 1 0 ‘ 2 - 9 .5 X 1 0 " 30 .1
GI (LLI) - - 2 .3 x 10 -
241 Pu
94 So l. Bone 0 .7 8 2 . 3 X 1 0 " 1 1. 8 x 1 0 z 2 .3 X 1 0 "2
Insol. Lung 16 9. 5 X 10 - 9 .5 1
GI (LLI) - - 1 .1 X 1 0 3 -
242 Pu94
Sol. Bone 0 .0 4 4 4 .5 X 1 0 ' 3 3 .8 4 .5 X 1 0 ‘ 40 .1
Insol. Lung 0 . 0 1 6 9 .5 X l O '2 - 9 .5 X l O '3
GI (LLI) - - 2 . 5 X 10 -
243 p u
94 So l. G I (ULI) - 4 . 4 X 10 3 2 . 7 X 1 0 2 4 . 4 X 1 0 2
Insol. GI (ULI) - 5 . 5 X 1 0 3 2 . 7 X 1 0 2 5 .5 x 1 0 2
6 9
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T A B L E II A (cont'd)
(1 ) ( 2 ) (3) (4) (5) (6 ) (7)
244pu
94 So l. Bone 0 . 0 4 5 4 . 1 x 1 0 ~ 3 3 . 4 4 . 1 X 1 0 ' 4
Insol. Lung 0 . 0 1 7 8 . 0 X 1 0 " 2 - 8 . 0 X 1 0 " 3
GI (LLI) - -
CO00 -
“ Am95 So l. Kidney 0. 0 0 4 4 1 . 5 X 1 0 ' 2 3 . 0 1 . 5 X 1 0 " 3
Bone 0 . 0 3 9 1 , 5 x 1 0 " 2 - 1 . 5 x 1 0 ‘ 3
0 . 1
Insol. Lung 0 . 0 1 5 2 . 6 X 1 0 ' 1 - 2 . 6 x 1 0 ' 2
GI (LLI) - - 2 . 2 x 10 -
242 m ,95 Am
Sol. Bone 0 . 0 3 6 1 . 4 x 1 0 “2 3 . 5 1 . 4 x 1 0 ‘ 3
Insol. Lung 0 . 0 3 7 6 . 5 X 1 0 _I - 6 . 5 X 1 0 ' 2
G I (LLI) - - 7 . 4 X 10 -
242 A 95
So l. G I (LLI) 0 . 0 9 8 _ 1. 0 X 1 0 2
Liver 0 . 0 2 3 9 . 5 x 10 - 9 . 5
Insol. Lung 0 . 0 3 7 1 . 2 x 1 0 2 - 1 . 2 X 10
GI (LLI) - - 1 . 0 X 1 0 2 -
243 AmSo l. Bone 0 . 0 4 1 1 . 4 X 1 0 ' 2 3 . 5 1 . 4 X 1 0 ' 3
Kidney 0 . 0 0 4 6 1 . 5 X 1 0 ’ 2 - 1 . 5 X 1 0 - 3
0 . 1
Insol. Lung 0 . 0 1 6 2 . 7 X 1 0 " 1 - 2 . 7 x 1 0 ‘ 2
G I (LLI) - - 2 . 2 X 10 “
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T A B L E II A (cont'd)
(1) (2 ) (3) (4) (5) (6) (V)
“ Am95 „ ,So l. G I (S I) 3 . f rx 103
Bone 0 .0 4 4 1 .6 X 104 - 1 . 0 x 103
Kidney 0 .0 4 4 1 . 1 x 104 - 1 . 1 x 103
Insol. Lung 0 .5 2 6 .0 x 104 - 6 .0 x 103
GI (SI) - - 3 .8 X 1 0 3 -
2g C mS o l. G I (LLI) - _ 1 .9 X 10 _
Liver 0 .0 1 8 3 . 0 x 1 0 " 1 - 3 .0 x 10~2
Insol. Lung 0 .0 1 3 4 .1 X 1CT1 - 4 .1 X 1 0 '20 .1
G I (LLI) - - 2 .0 X 10 -
243
S o l. Bone 0 .0 3 7 1 .6 X 1 0 " 2 4 .1 1 .6 x l ( T 3
Insol. Lung 0 .0 1 4 2 .5 X 1 0 '1 - 2 .5 X 1CT20 .1
GI (LLI) - - 2 .0 X 10 -
244 Cm96
Sol. Bone 0 .0 3 7 2 .3 X 1 0 " 2 5 .7 2 .3 X 1 0 " 3
Insol. Lung 0 .0 1 4 2 .5 X 1 0 '1 - 2 .5 X 1 0 '20 .1
GI (LLI) - - 2 .1 X 10 -
* CmS o l. Bone 0 .0 3 9 1 .2 x 1 0 " 2 2 .8 1 .2 x 10-3
Insol. Lung 0 .0 1 5 2 . 7 X 1 0 " 1 - 2 . 7 x 1 0 " 2 0 .1
GI (LLI) ■ 2 .2 X 10
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T A B L E II A (cont'd)
(1) ( 2) (3) (4) (5) (6) (7)
246 Cm96
S o l. Bone 0 . 0 3 9 1 . 2 X 1 0 ' 2 2 . 9 1 . 2 X 1 0 ' 3
Insol. Lung 0 . 0 1 5 2 . 6 X 1 0 ' 1 - 2 . 6 X 1 0 ' 20 . 1
GI (LLI) - - 2 . 2 X 10 -
* CmSol. Bone 0 . 0 4 1 1 . 2 X 1 0 -2 2 . 9 1 . 2 X 1 0 ' 3
Insol. Lung 0 . 0 1 5 2 . 7 X 1 0 " 1 - 2 . 7 X 1 0 ' 2
GI (LLI) - - 1. 8 X 10 -
9 6 CmSo l. Bone 0 . 0 0 4 8 1 . 5 x 1 0 ' 3 3 . 5 X 1 0 " 1 1 . 5 x 1 0 ' 4
Insol. Lung 0 . 0 0 1 8 3 . 3 X 1 0 ~ 2 - 3 . 3 X 1 0 ' 3
G I (LLI) - - 1 . 0 -
24996 C m
So l. G I (S) 1 . 8 X 1 0 3
Bone 0 . 4 1 3 . 1 x 1 0 4 - 3 . 1 X 1 0 3
Insol. G I (S) - 2 . 8 X 1 0 4 1 . 8 X 1 0 3 2 . 8 X 1 0 3
249 Bk97
So l. GI (LLI) . . 4 . 7 X 1 0 2 _
Bone 0 . 5 5 2 . 3 - 2 . 3 X 1 0 ' 1
1
Insol. Lung 12 3 . 0 X 1 0 2 - 3 . 0 X 10
GI (LLI) . - - 4 . 7 X 1 0 2 -
2 5 0 B k97 S o l. G I (ULI) - - 1 . 8 X 1 0 2 -
Bone 0 , 0 3 8 3 . 6 X 1 0 2 - 3 . 6 X 10
Insol. G I (ULI) 2 . 8 X 1 0 3 1 . 8 X 1 0 2 2 . 8 X 1 0 2 |
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5 ) (6) (7)
249 c f
98 So l. Bone 0 .0 3 7 3 .9 X 1 0 '3 3 .3 3 .9 X 10-4
Insol, Lung 0 .0 1 4 2 .5 X 1 0 " 1 - 2 .5 x 1 0 - 2 0.1GI (LLI) - - 1.9 x 10 -
250C f98 So l. Bone 0 .0 3 5 1.2 x 1 0 ‘ 2 1 . 0 x 10 1.2 x 1 0 ‘ 3
2 .5 X 1 0 "10. 1
Insol. Lung 0 .0 1 4 - 2.5 x 1 0 '2
G I (LLI) - - 2 .0 X 10 -
251 C f98 ^So l. Bone 0 .0 3 8 4 .2 X 1 0 ‘ 3 3 .4 4 .2 X 1 0 ‘4
Insol. Lung 0 .0 1 4 2 .5 X 1 0 '1 - 2 .5 X IQ "2
GI (LLI) - - 2 .1 X 10 -
252 C f98 So l. G I (LLI) - - 5 .8 -
Bone 0.01 1 .6 X 1 0 '2 - 1.6 X l o -3
0 .1Insol. Lung 0 .0 0 4 8 .0 X 1 0 " z - 8 .0 X l o -3
GI (LLI) - - 5 .8 -
zs3c f98
So l. GI (LLI) _ . 1 . 1 x 1 0 2 .
Bone 0 .0 2 9 2.1 - 2 . 1 X l o ' 1
Insol. Lung 0 .0 1 4 1 .9 - 1 .9 x l o _1
G I (LLI) - - 1 . 1 x 1 0 2 -
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T A B L E II A (cont'd)
(1) (2) (3) (4) (5) (6) (7)
264 C f98
So l. GI (LU ) . 9 .6 X 1 0 " 2
Bone 0 . 00058 1 .3 X 1 0 " 2 - 1 .3 X 1CT3
Insol. Lung 0 .0 0 0 2 2 1 .2 X 1 0 '2 - 1 .2 X 1 0 '3
GI (LLI) - - 9 .6 X 1 0 " 2 -
253Es99 So l. GI (LLI) - - 1. 8 x 10 -
Bone 0 .0 3 1 .9 - 1 .9 x 1 0 " 1
Insol. Lung 0 .0 1 2 1 .5 - 1 .5 » 10_l
GI (LLI) - - 1. 8 x 10 -
254 m Es99
S o l. GI (LLI) 1 .5 X 10 _
Bone 0 .0 1 7 1 .3 X 10 - 1 .3
Insol. Lung 0 .0 1 1 1 .5 X 10 - 1 .5
GI (LLI) - - 1 .5 x 10 -
254 Es 99
So l. GI (LLI) - - 1 .1 X 10 -
Bone 0 .0 1 8 4 . 7 X 1 0 "2 - 4 .7 X 1 0 ‘ 3
Insol. Lung 0 .0 1 2 2 . 7 X 1 0 " 1 - 2 .7 X 1 0 ‘ 2
GI (LLI) - - 1 .1 X 10 -
255 Es99
So l. G I (LLI) - - 2 . 2 X 10 -
Bone 0 . 0 2 9 1 . 2 - 1 . 2 X 1 0 " 1
In s o l. Lung 0 . 0 1 1 1 . 0 - 1 . 0 X 1 0 " 1
GI (LLI) - - 2 . 2 X 10 -
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T A B L E II A (cont'd)
(1) (2 ) (3 ) (4) (5) (6) (7)
254 F m
S o l. GI (ULI) ' - - 9 . 6 X 10 -
Bone 0 .0 1 6 1. 6 X 102 - 1 .6 X 10
Insol. Lung 0 .0 1 1 1. 8 X 102 - 1 .8 .X 10
GI (ULI) - - 9 .6 x 10 -
« F m100S o l. G I (LLI) 2 .6 X 10
Bone - 0 .0 2 9 4 .1 X 10 - 4 .1
Insol. Lung 0 .0 0 1 2 .7 X 10 - 2 .7
GI (LLI) - - 2 . 6 X 10 -
256 Fm 100
S o l. GI (ULI) 7 ,1 X 1 0 '1
Bone 0 .0 0 0 6 6 .9 - 6 .9 X 1 0 "i
Insol. Lung 0. 00023 4 .4 - 4 . 4 X 1 0 "1
G I (ULI) “ 7 .1 X 1 0 _1 “
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T A B L E II B
M A X IM U M P E R M I S S I B L E I N T A K E S O F N A T U R A L T H O R IU M AND N A T U R A L O R D E P L E T E D URANIUM
Workers Members of the public“ 1CCO O
M axim um u S 1?Organ perm issible 1 § !
'H CJ Ccontent annual Lim its of Lim its of
£ C w •S3 o o
RadionuclideC ritica lorgan
giving the m axim um
intake by inhalation
annual intake by
annual intake by i s s
V cpermissible during ingestion inhalation E g* -2
3 Cd ose-rate ^ working
hours
C 0) 2.£ x J3 S .23 m m ooS i s
(Mg)a (Mg)* (Mg)a (Mg) 3 (kg)
x h Nat
Sol. Bone 8 . 0 X 1 0 4 3 . 7 X 1 0 4 9 . 5 X 10 s 3 . 7 X 1 0 s
Insol. Lung 9. 3 X 1 0 4 - 9 . 3 X 1 0 3 1
GI (LLI) - - 7 . 1 X 1 0 7 -
u N a t bc
Sol. Kidney 9 . 2 X 1 0 2 5 . 5 X 1 0 5 1 . 4 X 1 0 6 5. 5 X 1 0 4
Insol. Lung - 4 . 8 X 1 0 5 - 4 . 8 X 1 0 41
GI (LLI) - - 3 . 9 X 1 0 7 -
a 1 gram o f T h ^ at contains 0 .1 1 pC i 232Th, 0 .1 1 ^Ci 22sxh and various amounts of 227Th, 23iTh and 2i*Th, depending on the relative abundance o f 232Th and natural uranium in the ore and the age after separation.T he values for the T h ^ at are provisional. Although calculations and anim al experim ents suggest that ThN at, i f in jected intravenously, is perhaps as hazardous as Pu and ind icate the values listed above, experience to date has suggested that in industrial circum stances the hazard of T h ^ at is not much greater than that o f uN at. Therefore, pending further investigations, a yearly intake by inhalation o f 6 .6 x 105^g o f ThNat .for workers d irectly engaged in radiation work during working houts is recom mended as provisional le v e l,
k 1 gram o f U ^at and depleted uranium contains 0 .3 3 pCi 238U, up to 0 .3 3 jjC i 234U and up to 0 .0 1 5 3 pCi 235U. c Because o f the ch em ical tox icity o f natural uranium, 238U, 23<>U and 23SU in soluble form , the inhalation o f uranium
o f any isotopic composition should not exceed 2 .5 mg o f soluble uranium in one day nor the ingestion o f soluble uranium in one day exceed 150 mg.
^ Except for uranium where the kidney burden is based on ch em ical tox icity which is m ore lim itin g .
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ANNEX B
M IX T U R E S OF RADIONUCLIDES
In the c a s e of m i x t u r e s o f ra d io n u c l id e s in a i r o r w a t e r , the m a x im u m p e r m i s s i b le in tak e s of th e s e m ix t u r e s m ay be com puted in s e v e r a l w ays, e x a m p le s of which a r e given below:
(a) If the detailed com posit ion of the m ix tu re s i s not known but the rad ion u clid es c o m p ris in g it have been identified , the M P I 's to be used can be those of T a b le s III A and I I I B of Annex B or that of the m o st r e s t r i c t iv e nuclide known to be p re sen t . T h is m ethod m a y s o m e t i m e s pro ve to be u n re a s o n a b ly r e s t r i c t i v e and it m a y be n e c e s s a r y to s e e k o th e r m e th o d s ;
(b) If the con cen tra t io n and to x ic i ty of one radionuclide in the m ix tu re a r e such that they a r e pred om inant and the c o n cen tra t io n of that nu clide i s known, the M P I to be u se d i s th at g iven fo r th is ra d io n u clid e in T a b le I IA of Annex A:
(c) If s e v e r a l radionuclides a re p re sen t in known concentration such that they c o n s t i tu te h a z a r d s of the s a m e o r d e r o f m ag nitu d e , th e i r com bined b io lo g ic a l h az ard m a y be com puted by dividing the concentra tio n of each nuclide by i ts M P I and adding the quot ien ts . The sum m ust be l e s s than one; o r
(d) In o th e r c a s e s w h ere the p ro b le m m a y be m o r e c o m p le x and w h ere s p e c ia l a s s e s s m e n t s m a y be r e q u i r e d , o th e r m e th o d s of evaluation should be applied by c om p eten t a u th o r i t ie s .
T A B L E S III A AND I I I B
The intakes in T a b le s III A and III B have been obtained by m ultiplying the re levant maximum p e rm iss ib le concentrations given bythe ICR P by the following standard intakes of a i r and water:
A ir breathed by w o rk ers at.work is 2500 m 3 /yr A ir breathed by adult individuals of the general public,
7300 m 3 /yrW ater taken in by adult m e m b ers of the general public,
800 l i t re s / y r .
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In the ca se of the general public, it should be borne in mind that the intakes are those appropriate to the critica l organ(s) of the standard adult. In computing the intakes for children appropriate safety facto rs are to be applied to take into account amongst other things the sm aller sizes of the critical organs of infants and children and various other biological p aram eters such as differences in breathing ra te .
T A B L E IIIA
MAXIMUM PER M ISSIB LE ANNUAL INTAKES BY INGESTION OF P A R T IA LL Y UNKNOWN M IXTURES OF RADIONUCLIDES
(Values appropriate to adult individuals in the population)
L im itationsA m em ber o f th e public a
(fiCi/yr)
I f no one o f th e radionuclides 90Sr , 1291,
210P b ,210 Po, 223 Ra, 226 Ra, 228 Ra, 231 Pa,
232U , Un a t , T h n at, 248C m , 254 C f. 256 Fm
is present 1 .6
129 210I f no one o f th e rad ionuclid es I , Pb,
226 Ra, 228 Ra, and 254 C f is present 3 .2 x 1 0 " 1
I f n eith er 226 Ra nor 228 Ra is present 8 .0 x 1 0 '2
I f no in form ation is a v a ila b le about the
com position 8 .0 x 1 0 " 3
2 T hese figures have been derived from th e roun d ed -off figures th e ICRPco m m itte e II report (1 9 5 9 ) , where th e values in T a b les II A and IIB h ave been tak en from th e o rig in al ICRP ca lcu la tio n s .
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T A B L E I I IB
M A X IM U M P E R M I S S I B L E IN T A K E S B Y IN H A LA TIO N O F W O R K E R S AND M E M B E R S O F T H E P U B L I C O F
P A R T I A L L Y UNKNOWN M I X T U R E S O F R A D IO N U C L ID E S
Lim itationsW o rk era (uCi/yr)
An individual a m em ber o f the
public (fiCi/yr)
If th ere are no ex-em ittin g radionuclides and
i f no one o f th e 8 -e m itt in g radionuclides
M gr, i M i . ^ p b , 22T Ac> 228 R a, 230Pa„ 241Pu,
and 249 Bk is present 7 . 8 7 .3 X 1 0 " 1
I f th ere are no ra-em ittin g radionuclides and
i f no one o f th e 8 -em ittin g radionuclides
210Pb, 227 A c , 228Ra, and 241 Pu is present 6 .0 X 1 0 ' 1 7 .3 X 1CT2
I f there are no a -e m itt in g rad ionuclides and
i f th e 0 -em ittin g rad ionuclid e 227 A c is not
present 6 .0 X 1 0 ‘ 2 7 .3 X 1 0 ‘ 3
If no one o f th e radionuclides 221 A c , 230 T h ,
231 P a , 238 Pu, 239 Pu, 240 Pu, 242 Pu, 244 Pu,
248 C m , 249 C f, 251 C f is present 7 . 8 X 1 0 " 3 7 .3 X 1 0 " 4
I f no one of the radionuclides 231P a , 239Pu, 240Pu,
242 Pu, 244Pu, 248 C m , 249 C f , 251 C f is present 3 .9 X 1 0 ‘ 3 5 .1 X 1 0 - 4
If 248C m is not present 1 7 .5 x lO "4 2 .9 X 1 0 "4
If no inform ation is av a ila b le about the
com position o f th e m ix tu re , th e valu e would be 1 1 . 7 X 1 0 ' 4 1 . 5 x 1 0 " 4
a T hese figures have been derived from th e rounded-off figures of th e ICRP co m m itte e II report (1 9 5 9 ) , where th e values in T ab les IT A and ITS have been taken from the orig in al ICRP ca lcu la tio n s .
79
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INTERNATIO NAL ATOM IC ENERGY AGENCY VIENNA. 1967
PRICE: US $2 00Austrian Schillings 52.114 2 stg: F Fr.9.80: DM 8. 1
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