Basic Safety Standards for Radiation Protection Safety Standards/Safety...BASIC SAFETY STANDARDS FOR RADIATION PROTECTION - 1967 Edition (Safety Series, No.9) ABSTRACT. This first

SAFETY SERIES

No.9

Basic Safety Standardsfor

Radiation Protection1967 Edition

INTERNATIONAL ATOMIC ENERGY AGENCY

VIENNA, 1967

This publication is no longer valid Please see http://www-ns.iaea.org/standards/


BASIC SAFETY STANDARDS FOR RADIATION PROTECTION

1967 E D IT IO N


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


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


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


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.



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



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


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


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


M r . H . Jam m et

Commissariat l'energie

atomique

Centre d'etudes nucleaires

* M r . R . L . Leupold


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


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


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


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


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


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


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


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


(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


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


(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.

13


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.

14


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.

15


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.


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.

17


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.

18


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.

19


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


(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.

2 1


(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.


(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;

23


(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.


(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.

25


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.

26


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.

27


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 .

28


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 .

29


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

30


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


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


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



( 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



( 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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



(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



( 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


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



(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



(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 ) .

63



(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 -

64



(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 .

65



(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.

66



(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.

67



(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



( 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



(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 “

70



(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

71



(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 |

72



(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 -

73



(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 -

74



(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 “

75


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 .

76


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 .

77


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 .

78


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



IAEA SALES AGENTS

Orders for Agency publicat ions can be p laced with your b o o ksell e r or any of our s a l e s

agen ts l is ted below :

A R G E N T I N A F I N L A N DComision Nac io nal de Akateeminen KirjakauppaEnerg ia Atomica K eskuskatu 2Avenida del Liberfcador H els in k iGenera l San Martin 825 0 F R A N C EBu en os A ires - Sue. 29 Off ice in ternation al de

A U S T R A L I A documentation e t l ibrairie

Hunter P u b l ic a t io n s , 48 , rue G ay»Lussac23 McKillop S tre et F - 7 5 , P a r i s 5 eMelbourne, C . l G E R M A N Y , F e d e ra l Republi c of

A U S T R I A R. Oldenbourg

Georg Fromme & Co. Ro senheim er S t ra sse 145S p e n gerg a sse 39 8 Munich 8A -1 0 5 0 , Vienna V H U N G A R Y

B E L G I U M Kultura

Off ice internat iona l de librairieHungarian Trading Co. for Book s

30, avenue Marnix B r u s s e l s 5

B R A Z I L

and Newspapers P . O . B . 149 Budap est 62

I S R A E LLivr aria Kosmos EditoraRua do R o sa r io , 135-1 3 7 H eil iger and Co.

R io de Ja n eiro

A genc ia Expoente O s c a r M. S ilv a

3 Nathan S tra uss Street J e rusa lem

Rua X av ie r de T o ledo , 14 0 -1 ® Andar I T A L Y

(C aixa P o s t a l No. 5. 614) A genz ia Ed it or ia le In tem azio nale

Sao Pau lo Or ganizza zi oni U niv ersa li ( A .E .I .O .U . ) Via Meravigli 16

B Y E L O R U S S IA N S O V I E T S O C IA L IS T MilanR E P U B L I C J A P A N

See under USSR Maruzen Company Ltd .CANADA 6, Tor i Nichome

The Q u ee n ’s Printer NihonbashiOttawa; Ontario (P .O . Box 605)

C H I N A (Taiw an)Tokyo Centra l

B o o k s and S c ie n t i f i c Suppl ies M E X I C OS e r v i c e , L td . , L ibrer ia InternacionalP . O . B o x 83 Av. Sonora 206T a ip e i Mexico 1 1 , D . F .

C Z E C H O SL O V A K S O C IA L IS T R E P U B L I C N E T H E R L A N D SS .N . T . L . N.V. Martinus NijhoffSpolena 51 Lange Voorhout 9Nove Mesto Prague 1

The Hague

D E N M A R KE jn a r Munksgaard Ltd.

N E W Z E A L A N DWhitcombe & T o m bs , Ltd.

6 Norregade G .P .O . Box 18 94

Copenhagen K Wellington, C . l


N O R W A Y S W I T Z E R L A N DJohan Grundt Tanum Libra irie PayotKarl J o h a n s gate 43 Rue Grenus 6Oslo 1211 Geneva 11

P A K I S T A N T U R K E YKarachi Ed ucation Soc ie ty L ib ra ir ie Hachet teHaroon Chambers 4 6 9 , I s t ik la l CaddesiSouth Napier Road B e y o e lu . Istanbul(P .O . Box' No. 4866)K arac hi 2 UKRAINIAN S O V I E T S O C I A 1 I S T

R E P U B L I CP O L A N D

See under USSROsrodek Ro zpowszechnianaWydawnictw Naukowych UNION O F S O V I E T S O C IA L IS T

P o l s k a Akademia Nauk R E P U B L I C S

P a f a c Kultury i Nauki Mezhdunarodnaya Kniga

Warsaw Sm olensk ay a-Sennay a 32-34 Moscow G-200

R O M A N I ACartimex U N IT E D KINGDOM O F G R E A TRue A. Briand 1 4-18 BR IT A IN AND NO RTHERN IR E L A N DB u ca r e s t Her M a je s ty ’ s Stationery Off ice

P .O . Box 569SOUTH A F R IC A London, S . E . l

Van Schaik*s Boo ks tore (P ty) Ltd.L ib r i Bui lding UNIT ED S T A T E S O F AMERICA

Church S tre et National Agency for

(P .O . Box 724) In ternation al P u b l i c a t i o n s , In c .

Preto ria 3 1 7 E a s t 34th Street New Yor k. N .Y . 1001 6

S P A I NLib rer ia B o s c h V E N E Z U E L ARonda de la Univers idad 11 Sr, Brau lio Gabrie l C h acaresB a rce lo n a Gobernador a Candili to 37

S W E D E N Santa R o sa l ia

C .E . F r i t z e s Kungl. Hovbokhandel (Apartado P o s t a l 80 92 )

Fr ed sg a ta n 2 C a ra c a s D . F .

Stockholm 16 Y U G O S L A V I AJu g o s lo v e n sk a Knj iga T e r a z i je 27 Belgrade

IAEA p ubl ica t io ns can a ls o be purchase d re ta i l a t the United Nation s Boo kshop a tUnited Nations Headquarters. New York , a t the news-stand at the A g e n c y ’s Head-quarters , V ienna , and at most co n f e r e n c e s , symp os ia and seminars organized by theAgency.

In order to fa c i l i t a t e the distribution of it s p u b li ca t io n s , th'e Agency is prepared toa c c e p t payment in UNES CO coupons or in l o c a l cu rre n c ies .

Orders and inq uiries from countr ies where s a l e s age nts have not y e t been appointedmay be s e n t to :

Distribut ion and S a l e s Group, Internat ion al Atomic Energy Agenc y,K am tn er Ring 11 , A -1 0 1 0 , Vienna I , Austria



INTERNATIO NAL ATOM IC ENERGY AGENCY VIENNA. 1967

PRICE: US $2 00Austrian Schillings 52.114 2 stg: F Fr.9.80: DM 8. 1


Documents

Basic Safety Standards for Radiation Protection Safety Standards/Safety...BASIC SAFETY STANDARDS FOR RADIATION PROTECTION - 1967 Edition (Safety Series, No.9) ABSTRACT. This first