Basic Toxicity Classification )f Radionuclides

TECHNICAL REPORTS SERIES No. 15

•

I \ Basic •

Toxicity Classification

•

( )f Radionuclides •

REPORT OF JOINT STUDY OF A GROUP OF CONSULTANTS

TO THE INTERNATIONAL ATOMIC ENERGY AGENCY

INTERNATIONAL ATOMIC ENERGY AGENCY - VIENNA 1963

A BASIC TOXICITY CLASSIFICATION OF RADIONUCLIDES

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Printed by the IAEA in Austria April 1963

TECHNICAL REPORTS SERIES No. 15

A BASIC TOXICITY CLASSIFICATION

OF RADIONUCLIDES

REPORT OF JOINT STUDY OF A GROUP OF CONSULTANTS TO THE

INTERNATIONAL ATOMIC ENERGY AGENCY

INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA 1963

A BASIC TOXICITY CLASSIFICATION OF RADIONUCLIDES IAEA, VIENNA, 1963

STI/DOC/10/15

FOREWORD

To facilitate the application of radiation protection regulations and recommendations, it may be necessary in some cases to classify radionuclides into groups according to their radiotoxicity.

The Agency convened a group of consultants to consider this problem and make a study of the radiotoxicity grading and grouping based on the data provided by the International Commission on Radio-logical Protection (ICRP), in particular the Report of Committee II on Permissible Dose for Internal Radiation.

The result of such work is the present report which presents a basic toxicity classification of radionuclides. This classification, however, may need some adjustments when applied to operations which depart from the conditions upon which the classification was based.

CONTENTS

1. Introduction 9

2. Definition of Toxicity 10

3. Why is a Toxicity Grading and Classification Possible for Radionuclides! 11

4. Basis of the Toxicity Grading 11

5. Basic Toxicity Grading of Radionuclides 13

6. Basic Toxicity Classification taking into Account Specific Activity 14

Annexe I

Mathematical Basis of Toxicity Grading for Continuous or Single Intake of Radionuclides 16

1. I N T R O D U C T I O N

In the course of its work in the field of health and safety the International Atomic Energy Agency has often met the practical re-quirement for grading radionuclides in order of their relative radio-toxicities. This need was particularly evident when the Agency's Basic Safety Standards for the protection of health against ionizing radiation [3] were in preparation, when it was necessary to exempt quantities of radionuclides from inclusion in the norms. A basic toxicity grading might be of help to laboratories in meeting some of their requirements in problems related to waste management as well as for the design of experimental facilities. It should also serve as a basis for the development of safety criteria for laboratory equip-ment and procedures for handling and transporting various quantities and kinds of radionuclides.

The purpose of the present Report is to make a toxicity grading of the radionuclides according to the risk of biological injury which they may cause when they have become incorporated in the human body. No account has been taken of the biological effects of radiation penetrating the body when the radionuclide is external to it. Inform-ation on the metabolism and subsequent biological risk from radio-nuclides taken into the body has been freely taken from the Report of Committee II of the International Commission on Radiological Pro-tection (ICRP) [1] . This information has been used in the present Report to show that a factor of about 108 in relative toxicity exists between radionuclides with the highest and lowest toxicities. Such a wide range of toxicities makes it necessary, especially in regu-latory procedures, to group the radionuclides within the toxicity grading so that recommendations or regulations may be made ap-plicable to each of a small number of groups rather than to a large number of different toxicities of the individual radionuclides. In the present classification only three main groups have been distinguished. Radionuclides of high toxicity and those of low toxicity have been separated from a larger group of medium-toxicity nuclides. However, it is recognized that, for some purposes, the group of medium-toxicity nuclides may cover too wide a range of toxicity and there-fore a further division is suggested which splits the group into two sub-groups.

The exact arrangement of the toxicity grading and the division into groups may depend on the particular application for which it is required. The IAEA has already developed a toxicity classification of radionuclides for transport purposes [4]. While that classification may require some reconsideration with a view to modification in the

9

light of the present Report, it is recognized that the basic classi-fication as derived here would not be directly applicable to transport without adjustment to take due account of factors and circumstances which are peculiar to such application.

One special factor which is important in all applications of toxi-city grading and classification is specific activity. Hence in this Re-port a method is given for taking specific activity into account in the classification.

2. DEFINITION OF TOXICITY

No agreed definition is available regarding what is meant by the toxicity of a radionuclide. However it may be useful to examine an accepted definition of chemical toxicity to see how it can guide the development of a similar definition for radionuclides. GOLDWATER [2] defines toxicity and the closely related concept of toxicity hazard as follows:

"Toxicity is the ability of a chemical molecule or compound to produce injury once it reaches a susceptible site in or on the body. Toxicity hazard is the probability that injury may be caused by the manner in which the substance is used. "

Similarly, we may adopt the following definition for the toxicity of a radionuclide:

"The toxicity of a radionuclide is the ability of the nuclide to produce injury, by virtue of its emitted radiations, when in-corporated in a body. "

There are two important points of difference in the effects of a chemical toxin and a radionuclide which require some comment. Firstly, most attention is focused on the acute effects of chemical toxins, whereas the effects of all but the largest intake of radio-nuclides do not usually become apparent for several years, There-fore the degree of injury and the time of its manifestation are in general very different. Secondly, the susceptible site in the chemical definition has no exact counterpart in radionuclide definition but, in general, the site of greatest biological injury is in the body organ which accumulates the greatest concentration of the radionuclide. The body organ in which a radionuclide is most concentrated and the associated relative biological efficiency (RBE) dose is highest is, in general, called 'the critical organ' by the ICRP [1] . Factors other than the RBE dose were considered by the ICRP [1] in choosing the critical organ for a particular radionuclide, such as the essentiality of the organ and its radiosensitivity, but usually the RBE dose was the overriding consideration.

A definition of toxicity hazard for a radionuclide may be obtained directly from that given by Goldwater for a chemical substance as follows:

10

"A toxicity hazard is the probability that injury may be caused by the manner in which the radionuclide is used. "

If these proposed definitions of toxicity and toxicity hazard are accepted, then it becomes clear that the basic grading and classi-fication of the radionuclides may be made purely on their toxicity, and any modification required due to the particular use of the radio-nuclide which might affect the probability of intake and subsequent injury as, for example, in the case of transport, changes the classi-fication to one of toxicity hazard. Hence the present Report, in the terms of the above definitions, is concerned with a toxicity grading and classification and, in general, is not concerned with toxicity hazard.

3. WHY IS A TOXICITY GRADING AND CLASSIFICATION POSSIBLE FOR RADIONUCLIDES?

It is almost impossible to grade non-radioactive nuclides in order of their toxicity because there is no way of quantitatively com-paring the various injuries produced or measuring the potentiality of a nuclide to produce injury when it is outside thé body. In the case of radionuclides the injury to the body comes from the radiations emitted, which are few in type and which have well-defined and measured physical properties. All types of radiation produce the same primary basic physicochemical effects of excitation and ioniza-tion within the biological material and they differ only in the spatial distribution and intensity of these effects. The types of irradiation emitted, and their energies, have been well-established for most radionuclides and the disintegration rate of any radioactive sample can be measured. Therefore if the concentration of a radionuclide by a body organ of known mass can be determined from experimental measurement, then the dose in rads delivered to the organ by the radionuclide can be calculated. If the ICRP [1] concepts are used, then this dose is multiplied by the RBE factor appropriate to the radiation delivering the dose in order to take into account the different amounts of biological damage caused by each type of ionizing radi-ation to the various body organs. In principle, the product RBE X dose (rad) is proportional to the risk of biological damage for all types of radiation.

4. BASIS OF ТЦЕ TOXICITY GRADING

The toxicity grading given below has been limited to those radio-nuclides listed by the ICRP [1] and no radioactive chemical compounds have been considered because of lack of a consistent set of data on the metabolic behaviour of compounds in the human body.,. For example, there are many compounds containing tritium, carbon,

1 1

sulphur, phosphorus and iodine which are readily available from isotope production centres which, if accidentally taken into the body, would be metabolized in a very different way from the elemental radionuclide. Hence this shortcoming in the toxicity grading should be kept in mind when using it.

There are three important ways in which radionuclides normally enter the body — by absorption through the skin, by ingestion and by inhalation. Of these three modes of entry it was considered that in-halation was the most important because the other two are usually more readily controlled or avoided by taking simple precautions. Although in an accident or during the clean-up operations it is pos-sible that radionuclides could enter the body through wound puncture, it is considered that this method of intake would be best taken into account in the particular circumstance rather than in the basic toxi-city classification. This in fact was the case in the toxicity classi-fication set up for purposes of safe transport [4J where it was con-sidered that wound injection could occur during and after an accident. However, for the purposes of the basic toxicity grading and classi-fication considered in the present Report, inhalation was taken to be the most significant mode of entry, and other modes were not taken into account.

A further consideration in making the toxicity grading is the rate at which the radioactivity is inhaled. The grading may be based on the toxicity of the radionuclides due to their continuous intake, which is the most important consideration for workers directly en-gaged in radiation work. Alternatively,' the grading,may be based on an intake of short duration. This case is probably more important than continuous intake to the casual users, or those only likely to be in contact with radioactivity once in a life-time — for example, members of the public who inhale radioactive material after an acci-dental release to the environment. In Annex I to this Report the mathematical formulations for continuous and single intakes are set out in conformity with the concepts used by the ICRP [1] . This mathe-matical formulation shows that if equal daily intakes of radioactivity are limited such that after 50-yr continuous intake the dose-rate to the critical organ is, say, R rem per week, then for any given radio-nuclide this daily intake bears a constant relationship to the single intake which delivers a dose of R rem over the subsequent 50 yr to the same critical organ. In other words, within the ICRP concepts it is possible to have a toxicity grading which applies to continuous as well as short-term intakes. Therefore, although the classification is based on the ICRP [1] values for the maximum permissible con-centrations in air (MPC)a* for continuous inhalation as described in the following section, it is also applicable to single inhalation.

* T h e so l e e x c e p t i o n b e i n g Rn 2 2 2 whe re the f i g u r e used i n th is Repor t is an order o f m a g n i t u d e

h i ghe r to c o n f o r m w i t h the I A E A Ba s i c S a f e t y S tandards for R a d i a t i o n ftotection [ 3 ] .

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The only consistent set of data available for calculating the dose to body organs from known intakes of activity are given by the ICRP [1] . Therefore these ICRP data, including their concepts of a stan-dard man and radiosensitivity of the body and organs, have been used in making the present toxicity grading. One major limitation involved in this approach is that the grading strictly applies to adults only and it is possible that some rearrangement might be necessary to take into account the differences in metabolic function and body-organ size between children and adults. However, no consistent set of ap-propriate data is available for a standard child and therefore it was not possible to take children into account.

5. BASIC TOXICITY GRADING OF RADIONUCLIDES

Continuous exposure at the appropriate maximum permissible concentrations (MPC) recommended by the ICRP [1] will eventually give rise to a dose-rate of 0.1, 0.3 or 0.6 rem per week in the critical organ. The three different dose-rates represent the differing radiosensitivities of the three classes of body organs. Hence the basic toxicity grading, based on the arrangement of the radionuclides in order of their most restrictive value of (MPC) a for continuous inhalation, takes into account not only the RBE dose-rate but also the radiosensitivity of the critical organ.

The ICRP [1] give values of the (MPC)a for both soluble and insoluble forms of radionuclides and, for the purposes of the present Report, the more restrictive of these two values is used. The grading obtained in this way is given in Table I* where the 236 radionuclides considered are listed in order of their most restrictive value of (MPC) a .

The radionuclides listed in Table I have been divided into three main toxicity groups, with a division of the large-medium group into two sub-groups to obtain a toxicity classification. In this kind of work the choice of the dividing lines is always somewhat arbitrary and justification for the actual position of the lines can only be made in general terms. Those in Table I were chosen in conjunction with another toxicity classification which takes into account the specific activity of the radionuclides as described in Section 6 of this Report. The boundary lines chosen are summarized in Table II.

In Table II there is not exact equivalence between the values of (MPC)a and (MPI) given in columns 2 and 3 because the definition given in Section 6 shows that an (MPI) of 1 мс is equivalent to 1.37X 10"10цс/cm3. But values of (MPC)a are given by the ICRP [1] to the nearest whole number and the first significant value of (MPC)a

less than 1.37X 10"10/uc/cm3 is 10 "10/лс/ст3 . Hence the lack of exact equivalence between the values of (MPC)a and (MPI) does not affect

* T h e T a b l e s a r e t o b e f o u n d a t t h e e n d o f t h i s R e p o r t .

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the classification. In addition, some advantage lies in choosing round numbers for the boundary values of (MPI) due to the fact that no radionuclides actually fall on these values.

The nuclides in the high-toxicity group include most of the bone-seeking, heavy transuranic nuclides and strontium-90 which is in accordance with common experience with those nuclides. The low-toxicity group contains radionuclides of short effective half-life in the body and low effective energy of disintegration which again is in accordance with common experience. The remainder of the nuclides form the medium-toxicity group. This is the largest group and for some purposes it might be thought desirable to divide the group into sub-groups. This has been done by taking a dividing line at an (MPI) of 100 /uc.

6. BASIC TOXICITY CLASSIFICATION TAKING INTO ACCOUNT SPECIFIC ACTIVITY

The specific activity of a radionuclide affects the probability that a given quantity of radioactivity may enter the body and affects its subsequent behaviour in the body. For example, radionuclides of very low specific activity, such as neodymium- 144, indium-115 and rubidium-87, have such a large mass associated with a unit of activi-ty that it would be impossible for the body to take in a sufficient quan-tity of material for it to become radiologic ally toxic. In terms of the definition given in Section 2 of this Report it is the toxicity hazard which is under consideration when account is taken of the probability of intake and subsequent risk of biological damage. However, as the specific activity is an important inherent property of a radio-nuclide, it cannot be ignored in making a classification. Otherwise, as shown by the examples above, some low-specific-activity radio-nuclides may be assigned an absurdly high toxicity. It is therefore proposed to take specific activity into account but still to consider that the classification so produced is a basic toxicity classification and not a toxicity hazard classification in spite of the definition given in Section 2.

In order to consider the effects of mass on the probability of entry of radioactivity into the body, it is necessary to choose the appropriate amount of radioactivity for each radionuclide so that the mass can be calculated. Guidance for the appropriate amount of activity was obtained from Paragraph 52 (g) of the ICRP Report [1] in which permissible limits of exposure during a period of emergency are given. The recommendations are that the dose to the critical organ during the 50 yr following, an intake shall not exceed the maximum yearly limit of

(a) 12 rem for the whole body and the gonads; (b) 30 rem for the skin, thyroid and bone; and (c) 15 rem for all the other organs.

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* The aiïiount of inhaled radioactive material which produces the doses mentioned above can be calculated from the values of (MPC) a

as these doses will be delivered by the intake for one year. Hence the maximum permissible intake of radioactive material (MPI ) /uc is given by

( M P I ) M C = ( M P C ) a X 2 X 10 7X365 (1 )

where (MPC)A is the most restrictive value for continuous inhalation g i ven by the I C R P [1] and 2 X 1 0 7 X 3 6 5 i s the amount of a i r b r e a t h e d by a standard man in one year. For those radionuclides where the whole body is the critical organ a value for (MPI)MC from Equation (1) has to be multiplied by the ratio 12/5 because the (MPC )a given by the ICRP [1] was calculated for a weekly dose-rate of only 0.1 rem, corresponding to an annual dose of only 5 rem, whereas the allowed annual dose in the above recommendation is 12 rem.

The maximum permissible concentration for one year may be expressed as the product of the mass of the radionuclide and its specific activity; this value is denoted by (MPI)/ug. The values of (MPC)a , (MPI)/uc, and specific activity and (MPI)Mg are given in Table III. These data are also diagrammatically presented in F ig . l * , where a point for each nuclide has been plotted on a graph with axes (MPI)juc and (MPI)Mg. The basic toxicity classification given in Table I is also represented on this diagram by drawing three hori-zontal lines at the values of (MPI)/uc given in Table II.

The effect of mass on the probability of intake was taken into account by considering the maximum amount of radioactive substance which is likely to be inhaled in a short time. It was thought unlikely that more than 10 mg of any radionuclide would be inhaled during the course of a single exposure. It should be noted that most radio-nuclides are associated with a stable isotope or other form of carr ier substance and therefore are associated with a far greater mass than that considered here, which is the ca r r i e r - f r ee mass. Therefore an atmosphere very heavily laden with dust would be required to contain, say, 10 mg of radionuclide per cubic metre, together with its carr ier , which would, even then, have to be breathed for almost an hour before the intake reached 10 mg. Hence all the radionuclides which have a mass of greater than 10 mg as-sociated with the (MPI)AÍC were placed in the lowest toxicity class.

Another vertical line is shown in Fig. 1 at a value of (MPI)/ug of 100 ng. For reasons similar to those given above, it was thought that a radionuclide which had a mass of greater than lOO/ug as-sociated with the (MPI)MC could not be placed in the highest toxicity group. Hence radionuclides which have a mass of between 100/ug and 10 mg associated with the (MPI)/LIC are placed in the medium

* F i g u r e 1, " T a b l e for a Ba s i c T o x i c i t y c l a s s i f i c a t i o n o f R a d i o n u c l i d e s " is a t t a c h ed to the b a c k

c ove r o f th is p u b l i c a t i o n .

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toxicity group, except those which have an (MPI)/лс greater than 104, in which case they are in the lowest toxicity group.

Figure 1 shows graphically how the radionuclides are divided into three main groups —high, medium and low toxicity—by the two vertical and two horizontal full lines. For the purpose of general guidance only, the large medium-toxicity group has been subdivided into two subgroups by the horizontal dotted line drawn at an (MPI)/uc of 100/JC.

No account is taken of the effect of specific activity in making this subdivision because it would be difficult to justify any finer distinc-tions in the choice of the amounts of mass intakes. The choice of IOOMC for the value of (MPI)MC at which to subdivide the medium toxicity group appears to be reasonable on the grounds that it occu-pies a convenient position between the other two dividing lines, and that radionuclides in common use, such as gold-198, iron-59, zinc-65 and strontium-85, are in the lower toxicity subgroup, whereas iodine-l3l, strontium-89, calcium-45 and cobalt-60, which are of recognized fairly high toxicity, fall into the higher toxicity subgroup.

The result shown in Fig. 1 has been presented in Table IV, where the radionuclides are arranged according to their toxicity, and in alphabetical order, for easy reference.

ANNEX I

MATHEMATICAL BASIS OF TOXICITY GRADING. FOR CONTINUOUS OR SINGLE INTAKE OF RADIONUCLDES

The grading of radionuclides according to their toxicity may be based on the relative hazards due to continuous intake, which is probably the important consideration for radiation workers. In this case relative toxicities may be assigned from the values of the (MPC)a as given by the ICRP [1]. However, it may be important to consider a toxicity classification which is based on the hazard from a single intake. This is probably more important than continuous intake to the casual user of radionuclides or to those involved in accidental intakes of radioactive material. The mathe-matical concepts of these two types of toxicity classifications are set out below in order to show clearly the differences, if any, between them. The mathematical formulations given here are all in conformity with the ICRP concepts.

DOSIMETRY OF CONTINUOUS INHALATION

Let I be the permissible weekly inhalation (|ic) as set forth in the recommendations of the ICRP [1 ] ,

X be the effective decay constant in the critical org.-'n, and f a be the fraction of the inhaled activity retained in the critical organ.

In the time interval t to t+dt the amount of activity taken into the critical organ is fa Idt and the amount leaving the organ is X A dt, where A is the accumulation in the organ at time t. Hence the change in accumulation, dA, at time t is given by

dA = faIdt - X Adt.

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The amount of activity accumulated in a working life of 50 yr (2600 weeks) is

2600 / ( f a I - XA)dt = i f ( i - e - 2 6 0 0 \ j 0 x

This amount of activity accumulated in the organ gives rise, after a continuous intake over 50 yr, to a dose-rate R, where R has the values 0.1, 0.3 or 0.6 rem per week depending on which organ is critical for the radionuclide under consideration. In the case of radionuclides with short effective half-lives in the critical organ, the accumulated activity reaches an equilibrium value in a few weeks but in the case of the long effective half- l ives of some of the bone-seeking radionuclides equilibrium is not reached even after 50 yr.

Let к be the dose in rem per week per lie of activity in the critical organ for the radionuclide considered, then R.the permissible weekly dose, is given in the expression

(i-e-2600 X)

and the permissible weekly inhalation is obtained by rearrangement as

XR 1 1 fak ( l - e - 2 6 0 0 X) '

A toxicity grading could be made for all the radionuclides based on the relative values of I for each nuclide.

DOSIMETRY OF SINGLE INHALATION

The dose considered here is that which would be delivered to the critical organ in the 50-yr period subsequent to the intake.

Let P be the amount of activity in microcuries which would result in a dose to the crit ical organ of 12, 15 or 30 rem in the subsequent 50 yr (2600 weeks). These are the doses to the appro-priate critical organs as recommended in Para. 52 (g) of the ICRP Report [1] and used in Section 6 of this Report.

The amount of a single inhalation remaining at t ime t after inhalation is

f a P e ' A t ,

where the symbols f a and X have the same meaning as defined above. The weekly dose-rate is

k f a P e "

and the total dose received by the cr i t ical organ in 50 yr is

2600 k f p ¿ kfaPe-Xt = ïiâil (1-е" 2600 X}.

The permissible doses to the critical organs are 12, 15 and 30 rem, which are roughly 50 times

17

the permissible weekly dose denoted by R in the case of continuous intake. Hence the value of P is obtained from the following equation

5 0 R = ^ ( l - e " 2 6 0 0 \y

or

XR 1 5 0 kfa (i-e-zeoox.)-

On comparing the single intake P with the continuous permissible weekly intake I for a particular radionuclide and appropriate critical organs, we find that

P= 50 I.

Hence a toxicity grading based on P or I will be identical because the two parameters are related by a constant. There is, however, a small difference which has so far been overlooked and that concerns the case when the whole body is the critical organ. The permissible continuous exposure of the whole body is 0.1 rem per week when an equilibrium body burden has been reached. Hence the permissible annual intake of radioactive material produces only 5 rem in the following 50 yr, whereas a single intake which is not likely to be repeated is permissible to be 12 rem. Therefore the position of radionuclides for which the whole.body is the critical organ may change slightly in grading on I or P.

R E F E R E N C E S

[1] INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Report of Committee II on Permissible Dose for Internal Radiation, Pergamon Press (1959) 233 pp.

[2] GOLDWATER, L.J. , Dangerous Properties of Industrial Materials, Reinhold Publ. Corp. (1957)1. [3] INTERNATIONAL ATOMIC ENERGY AGENCY, Basic Safety Standards for Radiation Protection,

Safety Series 9. STI/PUB/26, IAEA, Vienna (1962) 60 pp. [4] INTERNATIONAL ATOMIC ENERGY AGENCY, Regulations for the Safe Transport of Radioactive

Materials, Notes on Certain Aspects of the Regulations, Safety Series 7, STI/PUB/32, IAEA, Vienna (1961) 105 pp.

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SYMBOLS OF THE ELEMENTS USED IN TABLES I-IV

actinium Ac helium He

aluminium Al holmium Ho

americium Am hydrogen H

antimony Sb indium In

argon Ar iodine I

arsenic As iridium Ir

astatine At iron Fe

barium Ba krypton Кг

berkelium Bk lanthanum La

beryllium Be lead Pb

bismuth Bi lithium Li

boron В lutetium Lu

bromine Br magnesium Mg

cadmium Cd manganese Mn

caesium Cs mendelevium Md

calcium Ca mercury Hg

californium Cf molybdenum Mo

carbon С neodymium Nd

cerium Ce neon Ne

chlorine Cl neptunium Np

chromium Cr nickel Ni

cobalt Co niobium Nb

copper Cu nitrogen N

curium Cm nobelium No

dysprosium Dy osmium Os

einsteinium Es oxygen 0

erbium Er palladium Pd

europium Eu phosphorus P

fermium Fm platinum Pt

fluorine F plutonium Pu

francium Fr polonium Po

gadolinium Gd potassium К

gallium Ga praseodymium Pr

germanium Ge promethium Pm

gold Au protactinium Pa

hafnium Hf radium Ra

SYMBOLS OF THE ELEMENTS USED IN TABLES I-IV (cont'd)

radon Rn

rhenium Re

rhodium Rh

rubidium Rb

ruthenium Ru

samarium Sm

.scandium Sc

selenium. Se

silicon Si

silver Ag

sodium Na

strontium Sr

sulphur S

tantalum Ta

technetium Тс

tellurium Те

terbium Tb

thallium TI.

thorium Th

thulium Tm

tin Sn

titanium Ti

tungsten w

uranium и

vanadium V

xenon Xe

ytterbium Yb

yttrium Y

zinc Zn

zirconium Zr

TABLE III (continued)

R A D I O N U C L I D E S A R R A N G E D IN O R D E R O F T H E I R MOST R E S T R I C T I V E (MPC) a V A L U E

HIGH TOXICITY

P.231. cf249,Th-Nat,Pu2 3 9 , Pu240, Pu242, Th 2 3 2 , Pu238, Ac 2 2 7 , Th 2 3 0 , Np237 . Th 2 2 8 , Am2 4 1 , Am2 4 3 ,

Cm 2 4 3 , Cm 2 4 5 , Cm2« , Cf 2 5 0 , Cf 2 5 2 , Cm 2 4 4 , U 2 3 2 , Ra 226 Ra228, S m l 4 7 , U-Nat, N d " 4 , U 2 3 8 , Pu241,

pb2M игзо^ цгзз^ £,234^ u235t и236 Cm 2 4 2 , Th 2 2 7 , Po210 , Ra 2 2 3 S r 9 0 .

MEDIUM TOXICITY

Upper Sub-Group A

Ra224, Pa230, вк 2 4 9 , I 1 2 9 . Eu1 6 4 , Ru106 , Ce 1 4 4 , Bi 2 1 0 , A t 2 " , Na22, Co6 0 , A g " 0 ™ I 1 2 6 , 1131, C s 1 3 4 ,

E u 152(13^ Cs137, Bi207 pb212 A c228, In114m, s b l 2 4 , Ta182_ c l 3 6 , S c46, s b125, Ir192_ T1204_ C a 45 ,

Mil54, Y 9 1 , Zr95 , Sr89 . Cd1!5™, In1 1 5 , Te 1 2 7 " 1 , T e 1 2 9 m , 1I3 3 , Ba1 4 0 , T b 1 6 0 , Tm 1 7 0 , Hf1 8 1 , T h 2 3 4 .

Lower Sub-Group В

p32, y48, Fe59, Co58, Nl63, Zn65, Rb86, Rb87, Tc99, cd" 9 , Sn113, Pm147, Sm151, Os185, Hg203, As76,

Y 9 0 , Zr97 , Nb95, Ru1 0 3 , Agios, Sn 1 2 5 , Csl 3 5 , Eu1 5 5 , Gdl5 3 , B i 2 ! 2 , K 4 2 , As74, Se 7 5 , sr 8 5 , Nb 9 3 m ,

Zr93, je 125m, Te132, J135, La140, Tm171, w181, w185, Na24, Sc48, ^52, y93, Tc97m, sb122, Ce141, 142 Re183, й194, Bi206, Ca47_ Co57, Ga72_ •ft82iCd115i Te131m_ Cs136_ й143_ Ho166i £ 188 _ р^ЗЗ,

Mo99, eel4 3 , Dyl66, Tc96, Ag Щ 1I32, Ndl47, Pml49, Rel36, Au198, ^202, s35, Sr91, osl43, Zn69m, As73, As77, Sr92 , Y 9 2 , Tc 9 7 , Pd109, Bal31, Sm 1 5 3 , E u ^ f 1 - 2 1 1 ) , Gd159 , Erl6 9 , w l 8 7 , Osl9 1 , Ir 1 9 0 ,

Ptl93, Rn220, Rn222, * Se47, Mn56, Ni59, N¡65, ^87, Ru 105 Rh105, I134_ &l7i yb" 5 , Lu"7, Reí87,

pt^l, и197, Au196, Np239, s¡31, Fe55, Pdl°3, Tel27, Au199, Hgl97m , TI200, Tl2°l, Be7, A41, Cu^4,

Hgl97, Th231,Ndl49, Ru97, щ 115m, Pb203, ci38, Dyl65, Cr51, Fl», Cl4, Kr85m, Те"129, Xel35, Csl31.

LOW TOXICITY

H3, Zn69 , Ge.71, Nb97, I n U 3 m , C s 1 3 4 m , pt1 9 3m, ptl97m, TcS9m _ C o 5 8 m , Kr85 , X e 1 3 3 , Osl9!™, Xe 1 3 ! " 1 ,

y91m, sr85m, T c 96m, [^ЮЗт, A37,

* The figure used for this isotope is the same as that given in Basic Safety Standards for Radiation

tection [3 ] .

21

< s-

22


( M P C ) f AND (MPI)MC S P E C I F I C A C T I V I T Y (c/g) A N D (MPC)№

Rad i onu c l i d e s

a r r anged i n

order of i n -

c r e a s i ng a t o m i c

n u m b e r

( M P C ) £ C *

(168 h / w e e k v a l u e )

M a x i m u m p e r -

m i s s i b l e i n t a k e

i n 1 yr

( M P I ) £ C * *

expressed i n цс

as a resul t o f

con t i nuous u n i -

f o r m exposure

at ( M P C ) i ¡ c

S p e c i f i c

a c t i v i t y

expressed as

c / g o f t he

r a d i o n u c l i d e

i n the c a r r i e r -

f ree s ta te


m i s s i b l e i n -

• t a k e i n 1 y r

expressed i n

fig as a resu l t

o f con t i nuous

u n i f o r m e x -

posure at ( M P C ) M g

H 3 2 X 1 0 " 6 1 . 4 6 X 1 0 4 9 . 7 X 1 0 3 1 . 5

Be 7 4 X 1 0 " 7 2 . 9 X 10 3 3 . 5 1 X 10 5 8 . 2 X 1 0 " 3

C 1 4 1 0 " 6 7 . 3 X 10 3 4 . 5 9 1 . 5 8 X 1 0 3

F 1 8 9 X 10~7 6 . 5 7 X 1 0 3 9 . 3 X 1 0 7 7 . 0 6 X 1 0 " 5

N a 2 2 3 X 1 0 " 9 2 . 1 9 X 10 6 . 3 X 10 3 3 . 4 7 X 1 0 " 3

N a 2 4 5 X 1 0 " 8 3 . 65 X 10 2 8 . 7 X 10 6 4 . 2 X Ю " 5

S i 3 1 3 X 1 0 " 7 2 . 1 9 X 1 0 3 3 . 8 6 X 10 7 5 . 6 7 X 10~ 5

p32 2 X 1 0 " 8 1 . 4 6 X 1 0 2 2 . 8 8 X 10 5 5 . 0 6 X 1 0 - 4

s 3 5 9 X 1 0 " 8 6 . 5 7 X "102 4 . 2 9 X 1 0 4 1 . 5 3 1 X 1 0 - 2

C I 3 6 8 X 10~9 5 . 8 4 X 10 0 . 0 3 2 1 1 . 8 1 9 X 1 0 3

C I 3 8 7 X 1 0 " 7 5 . 1 1 X 1 0 3 1 . 3 3 X 10 8 3 . 8 4 X 1 0 " 5

A r 3 7 1 0 " 3 7 . 3 X 10 6 1 . 0 1 X 1 0 5 7 . 3 X 10

A i 4 1 4 X 1 ( T 7 2 . 9 2 X 10 3 4 . 2 5 X 10 7 6 . 8 7 X W 5

К 4 2 4 X 1 0 " 8 2 . 9 2 X 1 0 2 6 X 10® 4 . 8 6 X Ю - 5 -

C a 4 5 10 " 8 7 . 3 X 10 1 . 9 1 X 1 0 4 3 . 8 X 1 0 " 3

C a 4 7 6 X Ю - 8 4 . 3 8 X 1 0 2 5 . 9 X 10 5 7 . 4 2 X 1 0 " 4

S e 4 6 8 X 1 0 " 9 5 . 8 4 X 10 3 . 3 8 X 10 4 1 . 7 2 7 X 1 0 " 3

S e 4 7 2 X 1 0 " 7 1 . 4 6 X 1 0 3 8 . 2 X 1 0 5 1 . 7 8 X 1 0 " 3

S e 4 8 5 X 1 0 " 8 3 . 6 5 X 1 0 2 1 . 4 9 X 1 0 6 2 . 4 5 X 1 0 - 4

v 4 8 2 X 1 ( T 8 1 . 4 6 X 1 0 2 1 . 7 X 1 0 5 8 . 5 8 X 1 0 " 4

C r 5 1 8 X 1 0 " 7 5 . 8 4 X 1 0 3 9 . 2 X 1 0 4 6 . 3 4 X 1 0 " 2

M n 5 2 5 X 1 0 " 8 3 . 6 5 X 1 0 2 4 . 4 2 X 1 0 5 8 . 2 5 X 1 0 " 4

M n 5 4 1 0 " 8 7 . 3 X 10 8 . 3 X 1 0 3 8 . 7 9 X 1 0 " 3

* ( M P C ) £ c The se v a l ue s a re in c o n f o r m i t y w i t h t h e A g e n c y ' s Bas i c S a f e t y Standards for

R ad i a t i o n P r o t e c t i o n [3] .

* * ( M P I ) £ C = ( M P C ) ^ c X 2 X 1 0 7 X 365 . ( M P C ) ^ c = ( M P I ) { ^ / s p e c i f i c a c t i v i t y ( c / g ) .

23

TABLE III ( cont inued)

R a d i o n u c l i d e s

a r r a nged i n

o rder o f i n -

c r e a s i n g a t o m i c

n u m b e r

( M P C ) j f *

(168 h / w e e k v a l u e )



i n 1 yr

( M P I ) £ C * *

expressed i n цс

as a resu l t o f

c on t i n uou s u n i -

f o r m exposu re

at ( M P C ) ^ c

S p e c i f i c

a c t i v i t y

exp ressed as

c / g o f t he


i n t h e c a r r i e r -

f r ee s ta te



t a k e i n 1 yr

expressed i n

|ig as a resu l t

o f c on t i n uou s

u n i f o r m e x -

posure at ( M P C ) ^ S

M n 5 6 2 X 10 " 7 1 . 4 6 X 1 0 3 2 . 1 7 x 1 0 7 6 . 7 X 1 0 " 5

F e 5 5 3 X 1 0 - v 2 . 1 9 X 1 0 3 2 . 2 2 X 1 0 3 0 . 9 8 6 4

F e 5 9 2 X 1 0 - 8 1 . 4 6 X 1 0 2 4 . 9 2 X 1 0 4 2 . 9 6 X 10 " 3

Co57 6 X 1 0 - 8 4 . 3 8 x 1 0 2 8 . 5 X 1 0 3 5 . 1 5 X 1 0 - 2

C o 5 8 m 3 X 1 0 - 6 2 . 1 9 X 1 0 4 5 . 9 X 106 3 . 7 X 1 0 - 3

C o 5 8 2 X 1 0 - 8 1 . 4 6 X 1 0 2 3 . 1 X l O 4 4 . 7 X 1 0 " S

C06O 3 X 1 0 - 9 2 . 1 9 X 10 1 . 1 4 X 1 0 3 1 . 9 2 X l O " 2

N ¡ 5 9 2 X 1 0 - 7 1 . 4 6 x 1 0 3 8 . 1 X 1 0 - 2 1 . 8 X 1 0 4

N i 6 3 2 X 1 0 - 8 1 , 4 6 X 1 0 2 7 . 1 5 X 10 2 . 0 4

N i 6 5 2 X 1 0 " 7 1 . 4 6 X 1 0 3 1 . 8 8 x 1 0 7 7 . 7 6 X 1 0 - 5

C u 6 4 4 X 10 " 7 2 . 9 2 X 1 0 3 3 . 9 3 X 1 0 6 7 . 6 X 1 0 " 4

Z n 6 5 2 X 1 0 " 8 1 . 4 6 X 1 0 2 8 . 2 X 1 0 3 1 . 7 8 X 1 0 " 2

Z n 6 9 m 10 " 7 7. 3 X 1 0 2 3 . 2 9 X 1 0 6 2 . 2 1 X 1 0 " 4

Z n 6 9 2 X 1 0 " 6 1 . 4 6 x 1 0 4 5 . 3 X 1 0 7 2 . 7 X 1 0 " 4

G a 7 2 6 X 1 0 " 8 4 . 3 8 X 1 0 2 3 . 0 9 x 1 0 6 1 . 4 2 X 1 0 " 4

G e 7 1 2 X 1 0 " 6 1 . 4 6 X 1 0 4 1 . 6 1 X 1 0 5 9 . 1 X 1 0 " 2

A s 7 3 10 " 7 7 . 3 X 1 0 2 2 . 3 6 X 1 0 4 3 . 0 9 X 1 0 " 2

A s 7 4 4 X 1 0 " 8 2 . 9 2 X 1 0 2 1 . 0 1 x 1 0 5 2 . 8 9 X 1 0 " 3

A s 7 6 3 x 1 0 " 8 2 . 1 9 X 1 0 2 1 . 5 6 X 1 0 6 1 . 4 0 3 X 1 0 " 4

A s 7 7 10 " 7 7 . 3 X 1 0 2 1 . 0 5 X 1 0 6 6 . 9 5 X 1 0 " 4

S e 7 5 4 X 1 0 " 8 2 . 9 2 X 1 0 2 1 . 4 4 X 1 0 4 2 . 0 2 X 1 0 " 2

B r 8 2 , : 6 x i o " 8 4 . 3 8 x 1 0 2 1 . 0 6 X 1 0 6 4 . 1 3 X 10 " 4

K r 8 5 m 10 " 6 7 . 3 X 1 0 3 ' 8 . 4 X 1 0 6 8 . 7 X 1 0 " 4

ю

to ¿2 3 X 1 0 " 6 2 . 1 9 X 1 0 4 3 . 9 7 X 1 0 2 5 . 5 1 X 10

K r 8 7 2 X 10 " 7 1 . 4 6 X 1 0 3 2 . 7 7 X 1 0 7 5 . 2 7 X 1 0 " 5

R b 8 6 2 X 10 " 8 1 . 4 6 X 1 0 2 8 . 1 x 10 4 1.8 x 1 0 " 3

R b 8 7 2 X 10 " 8 1 . 4 6 X 1 0 2 6 . 6 X 1 0 " 8 2 . 2 X 1 0 9

S r 8 5 m , 1 0 " 5 7 . 3 X 1 0 4 3 . 1 6 X 1 0 7 2 . 3 1 X 10 " 3

S r 8 5 4 X 10 " 8 2 . 9 2 X 1 0 2 2 . 3 7 X 1 0 4 1 . 2 3 X 1 0 " 2

24


Rad i onuc l i d e s

a r ranged i n

o rder of i n -

c r eas i ng a t o m i c

n u m b e r

( M P C ) £ ° *

(168 h / w e e k v a l u e )


m i s s i b l e i n t a ke

i n 1 yr

( M P I ) £ C * *

expressed i n дс

as a result o f

S p e c i f i c

a c t i v i t y

expressed as

c / g o f t h e





t a ke i n 1 y r

expressed i n

as a result

o f con t inuous

cont inuous u n i -

f o rm exposure

at ( M P C ) £ c

f ree state u n i f o r m e x -

posure at ( M P C )

S r 8 9 10 " 8 7 . 3 X 10 2 . 8 8 X 1 0 4 2 . 5 3 X 10 " 3

S r 9 0 1 0 - 1 0 0 . 7 3 1 . 4 5 X 1 0 2 5 X 10 " 3

S r 9 1 9 X 1 0 " 8 6 . 5 7 x 1 0 2 3 . 5 6 X 1 0 6 1 . 8 4 5 X 1 0 " 4

S r 9 2 10 " 7 7 . 3 X I t ? 1 . 2 6 X 1 0 7 5 . 7 9 X 1 0 " 5

y 9 0 3 X 1 0 " 8 2 . 1 9 x 1 0 2 5 . 3 X 1 0 5 4 . 1 X 1 0 " 4

Y 9 1 m 6 x 1 0 " 6 4 . 3 8 x 1 0 4 4 . 1 1 X 10 7 . 1 . 0 9 X 1 0 " 3

y 9 1 10 " 8 7 . 3 X 10 2 . 5 X 1 0 4 2 . 9 2 X 1 Q " 3

y 9 2 1 0 - 7 7 . 3 X 1 0 2 9 . 5 X 1 0 6 7 . 6 X 1 0 " 5

y 9 3 5 X 1 0 " 8 3 . 6 5 X 1 0 2 3 . 2 4 X 1 0 6 1.12 x 10" 4

Z r 9 3 4 X 1 0 " 8 2 . 9 2 X 1 0 2 3 . 5 X 1 0 " 3 8 . 3 X 1 0 4

Z r 9 5 10 " 8 7 . 3 X 10 2 . 1 2 X 1 0 4 3 . 4 X 1 0 " 3

Z r 9 7 3 X 1 0 " 8 2 . 1 9 X 1 0 2 1 . 9 X 1 0 6 1 . 1 5 X 1 0 " 4

N b 9 3 m 4 X 1 0 " 8 2 . 9 2 X 1 0 2 3 . 7 9 X 1 0 2 7 . 7 X 1 0 " 1

N b 9 5 3 X 1 0 " 8 2 . 1 9 x 1 0 2 3 . 9 3 X 1 0 4 5 . 5 7 X 1 0 " 3

N b 9 7 2 X 1 0 " 6 1 . 4 6 X 1 0 4 2 . 6 1 X 1 0 7 5 . 5 9 X 1 0 " 4 '

M o 9 0 7 X 1 0 " 8 5 . 1 1 x 1 0 2 4 . 7 3 X 1 0 5 1 . 0 8 X 1 0 " 3

T c 9 6 m 10~ 5 7 . 3 X 1 0 4 3 . 8 1 X 10 7 1 . 9 X 1 0 " 3

T c 9 6 , 8 X 1 0 " 8 5. 84 X 1 0 2 3 . 2 4 X 1 0 5 1 . 8 X 1 0 " 3

T c 9 7 m 5 X 1 0 " 8 3 . 6 5 X 1 0 2 1 . 8 4 X 1 0 4 1 . 9 8 X 1 0 " 2

T c 9 7 10 " 7 7 . 3 X 1 0 2 3 . 7 X 1 0 " 1 2 X 1 0 3

T c 9 9 m 5 X 1 0 " 6 3 . 6 5 X 1 0 4 5 . 2 X 1 0 6 7 . 0 2 X 10"3

T c 9 9 2 X 1 0 " 8 1 . 4 6 X 1 0 2 1 . 7 1 X 1 0 " 2 8 . 5 3 X 1 0 3

R u 9 7 6 X 10 " 7 4 . 3 8 X 1 0 3 5 . 5 X 1 0 5 7 . 9 X 1 0 " 3

R u 1 0 3 3 X 1 0 " 8 2 . 1 9 X 1 0 2 3 . 1 9 x 1 0 4 6 . 8 6 X 1 0 " 3

R u 1 0 5 2 X 1 0 " 7 1 . 4 6 X 1 0 3 6 . 6 X 1 0 6 2 . 2 . x 1 0 " 4

R u 1 0 6 2 X 1 0 " 9 1 . 4 6 X 10 3 . 3 8 X 1 0 3 4 . 3 X 1 0 " 3

№ 1 0 3 ш 2 X 1 0 " 5 1 . 4 6 X 1 0 5 . 3 . 2 1 X 1 0 7 4 . 5 4 X 10 " 3

R h 1 0 5 2 X 10 ~7 1 . 4 6 X 1 0 3 8 . 2 X 1 0 5 1 . 7 8 X 1 0 " 3

P d 1 0 3 3 X 1 0 " 7 2 . 1 9 X 1 0 3 7. 5 X 1 0 4 2 . 9 2 X 10 " 2

P d 1 0 9 10 " 7 7 . 3 X 1 0 2 2 . 1 2 X 1 0 6 3 . 4 4 X 10 " 4

25



a r r a nged i n

o rde r o f i n -


n u m b e r

( M P C ) f *

(168 h / w e e k v a l u e )



i n 1 yr

( M P I ) g c * *

expressed i n дс

as a resu l t o f

c o n t i n uou s u n i -

f o r m exposure

at ( M P C )

S p e c i f i c

a c t i v i t y

expressed as

c / g o f t he



f r ee s ta te



t a k e i n 1 y r

exp ressed i n

p g as a resu l t


u n i f o r m e x -

posu re at ( M P C ) №

Ag 1 0 5 3 X 1 0 " 8 2 . 1 9 X 1 0 2 3 . 1 1 x 1 0 4 7 X 1 0 " 3

A g U 0 m 3 X 1 0 " 9 2 . 1 9 X 1 0 1 4 . 7 X 1 0 3 4 . 6 5 X 1 0 " 3

V11 8 X 1 0 " 8 5 . 8 4 X 1 0 2 1 . 5 7 x 1 0 5 3 . 7 1 X 1 0 " 3

C d 1 0 9 2 X 1 0 " 8 1 . 4 6 X 1 0 2 2 . 5 5 X 10 3 5 . 7 2 X 1 0 " 2

c d 1 1 5 m 10 " 8 7 . 3 X 10 2 . 6 4 X 1 0 4 2 . 7 7 x 1 0 " 3

C d 1 1 5 6 X 1 0 " 8 4 . 3 8 X 1 0 2 5 . 1 X 1 0 5

8 . 5 8 X 1 0 " 4

I n 1 1 3 m 2 X 1 0 " 6 1 . 4 6 X 1 0 4 1 . 6 X 1 0 7 ' 9 . 1 X 1 0 " 4

I n 1 1 4 m 7 X 1 0 " 9 5 . 1 1 X 10 2 . 2 9 X 1 0 4 2 . 2 3 X 1 0 " 3

I n 1 1 5 m 6 X 1 0 " 7 4 . 3 8 X 1 0 3 6 . 1 x 1 0 6 7 . 1 8 X 1 0 " 4

i n 1 1 5 10 " 8 7 . 3 X 10 5 . 2 X 1 0 " 1 2 1 . 4 X 1 0 1 3

S n 1 1 3 2 X 1 0 " 8 1 . 4 6 X 1 0 2 9 . 7 X 1 0 3 1 . 5 X 1 0 " 2

S n 1 2 5 3 X 1 0 " 8 2 . 1 9 X 1 0 2 1 . 1 X 1 0 5 1 . 9 9 X 1 0 " 3

S b 1 2 2 5 X 1 0 " 8 3. 65 X 1 0 2 3 . 9 x 1 0 5 9 . 3 5 X 1 0 ' 4

S b 1 2 4 7 X 1 0 " 9 5 . 1 1 X 10 1 . 7 6 X 1 0 4 2 . 9 X 1 0 " 3

S b 1 2 5 9 X 1 0 " 9 6 . 5 7 X 10 1 . 4 3 X 1 0 3 4 . 5 9 X 1 0 " 2

T e 1 2 5 m 4 X 1 0 " 8 2 . 9 2 X 1 0 2 1 . 8 x 104 1 . 6 2 X 1 0 " 2

T e 1 2 7 m 10 " 8 7 . 3 X 10 9 . 8 X 1 0 3 7 . 4 X 1 0 " 3

T e 1 2 7 . 3 X 1 0 " 7 2 . 1 9 X 1 0 3 2 . 6 3 X 1 0 6 8 . 3 X 1 0 " 4

T e 1 2 9 m 10 " 8 7 . 3 X 10 2 . 4 7 x 1 0 4 2 . 9 6 X 1 0 " 3

T e 1 2 9 10 " 6 7 . 3 X 1 0 3 1 . 9 7 x 1 0 7 3 . 7 X 1 0 " 4

T e 1 3 1 m 6 X 1 0 " 8 4 . 3 8 X 1 0 2 8 X 1 0 5 5 . 4 7 X 1 0 " 4

Т е 1 3 2 4 X 1 0 " 8 2 . 9 2 X 1 0 2 3 . 0 6 X 1 0 5 9 . 5 4 X 1 0 " 4

¡126 3 X 1 0 " 9 2 . 1 9 X 10 7 . 8 X 1 0 4 2 . 8 X 1 0 " 4

¡129 6 X 10 ~ 1 0 4 . 3 8 1 . 6 2 X 1 0 " 4 2 . 7 X 1 0 4

j l 3 1 3 X 1 0 " 9 2 . 1 9 X 10 1 . 2 3 X 1 0 5 1 . 7 8 X 1 0 " 4

¡132 8 X 10 " 8 5 . 8 4 X 1 0 2 1 . 0 7 X 1 0 7 5 . 4 5 X 10 " 5

j l 3 3 10 " 8 7 . 3 X 10 1 . 1 3 X 1 0 6 6 . 4 6 X 1 0 " 5

j l 3 4 2 X 1 0 " 7 1 . 4 6 X 1 0 3 2 . 6 8 X 1 0 7 5 . 4 4 X 1 0 " 5

¡ 135 4 X 10 " 8 2 . 9 2 X 1 0 2 3 . 4 8 X 1 0 6 8 . 3 9 X 1 0 " 5

26

TABLE III (cont inued)


a r r anged i n

o rder of i n -


n u m b e r

( M P C ) ^ c *

(168 h / w e e k v a l u e )



i n 1 yr

(MP I ) *

expressed i n цс

as a resul t o f


f o r m exposure

a t ( M P C )

S p e c i f i c

a c i t i v i t y

expressed as

c / g o f t he


i n t h e c a r r i e r -

f ree s tate



t a k e i n 1 y r

exp ressed i n

|jg as a resu l t

of c on t i nuous

u n i f o r m e x -

posure a t ( M P C ) M g

X e 1 3 1 m 4 X ' 1 0 " 6 2 . 9 2 X 1 0 4 8 . 3 X 1 0 4 3 . 5 X 1 0 " 1

X e 1 3 3 3 X 1 0 " 6 2 . 1 9 X 1 0 4 1 . 8 6 X 1 0 5 1 . 1 7 x 1 0 " 1

X e 1 3 5 1 0 " 6 7 . 3 X 1 0 3 2 . 5 4 X 1 0 6 2 . 8 7 X 1 0 " 3

C s 1 3 1 10 " 6 7 . 3 X 1 0 3 1 . 1 0 5 7 . 3 X 1 0 " 2

C s 1 3 4 m 2 X 1 0 " 6 1 . 4 6 X 1 0 4 . 7 . 4 X 1 0 6 1 . 9 X 1 0 " 3

C s 1 3 4 4 X 1 0 " 9 2 . 9 2 X 10 1. 22 X 1 0 3 2 . 3 9 X 1 0 " 2

C s 1 3 5 3 X 10 " 8 2 . 1 9 X 1 0 2 8 . 8 X 1 0 " 4 2 . 4 8 x 1 0 5

C s 1 3 6 6 X 1 0 " 8 4 . 3 8 x 1 0 2 7 . 4 x 1 0 4 5 . 9 X 1 0 " 3

C s 1 3 7 5 X 10 " 9 3 . 6 5 X 10 9 . 8 2 X 10 3 . 7 1 X 1 0 " 1

B a 1 3 1 10 " 7 7 . 3 X 1 0 2 8 . 7 X 1 0 4 8 . 3 9 X 1 0 " 3

B a 1 4 ° 10 " 8 7. 3 X 10 7 . 3 X 1 0 4 10 " 3

L a 1 4 0 4 X 1 0 " 8 2 . 9 2 X 1 0 2 5 . 6 X 1 0 5 5 . 2 1 X 1 0 " 4

C e 1 4 1 5 X 1 0 " 8 3 . 6 5 X 1 0 2 2 . 8 x 1 0 4 1 . 3 X 1 0 " 2

C e 1 4 3 7 X 10 " 8 5 . 1 1 X 1 0 2 6 . 6 X 1 0 5 7 . 7 X 1 0 " 4

C e 1 4 4 2 X 1 0 " 9 1 . 4 6 X 10 3 . 1 8 X 1 0 3 4 . 5 X 1 0 " 3

P r 1 4 2 5 X 1 0 " 8 3 . 6 5 X 1 0 2 1 . 1 5 X 1 0 6 3 . 1 7 X 1 0 " 4

P r 1 4 3 6 X 10 " 8 4 . 3 8 X 1 0 2 6 . 6 x 1 0 4 6 . 6 4 X 1 0 " 3

N d 1 4 4 3 X 10 " n 2 . 1 9 X 10 1 . 2 4 X 1 0 " 1 2 1 . 7 6 X 1 0 1 1

N d 1 4 7 8 X 10 " 8 5 . 8 4 X 1 0 2 8 X 1 0 4 7 . 3 X 1 0 " 3

N d 1 4 9 5 X 1 0 " 7 3 . 6 5 X 1 0 3 1 . 0 7 X 1 0 7 3 . 5 X 1 0 " 4

P m 1 4 7 2 X 1 0 " 8 1 . 4 6 X 1 0 2 9 . 6 X 1 0 2 1 . 5 2 X 1 0 " 1

P m 1 4 9 8 X 10 " 8 5 . 8 4 X 1 0 2 4 . 2 1 X 1 0 5 1 . 3 8 X 1 0 " 3

S m 1 4 7 2 X 1 0 " 1 1 1 . 4 6 X 1 0 " 1 1 . 9 5 X 1 0 " 8 7 . 4 8 x 1 0 6

S m 1 5 1 2 X 10~ 8 1 . 4 6 X 1 0 2 2 . 5 5 X 10 5 . 7

S m 1 5 3 10 " 7 7 . 3 X 1 0 2 4 . 3 5 X 1 0 5 1 . 6 7 X 1 0 " 3

E u 1 5 2 ( 9 . 2 h ) 10 " 7 7 . 3 X 1 0 2 2 . 2 4 X 1 0 6 3 . 2 5 X 1 0 " 4

E u 1 5 2 ( 13 y r ) 4 X 1 0 " 9 2 . 9 2 X 10 1 . 8 5 X 1 0 2 1 . 5 7 X 1 0 " 1

E u 1 5 4 10 " 9 7 . 3 1 . 4 5 X 1 0 2 5 . 0 3 X 1 0 " 2

E u 1 5 5 3 X 1 0 " 8 2 . 1 9 X 1 0 2 1 . 3 6 X 1 0 3 1 . 6 1 X 10

27


Rad i o nu c l i d e s

a r r a nged i n

o rde r o f i n -


n u m b e r

( M P C ) ^ c *

( 1 6 8 h / w e e k v a l u e )



i n 1 yr

( M P I ) ^ C * *

expressed i n ¡Ас

as a resu l t of

c on t i nuous u n i -

f o r m exposure

at ( M P C ) ^ c

S p e c i f i c

a c t i v i t y

expressed as

c / g o f t he



f ree s ta te



t a k e i n 1 y r

expressed i n

jig as a resu l t

o f c on t i nuous

u n i f o r m e x -

posure at ( M P C )

G d 1 5 3 3 X 1 0 " 8 2 . 1 9 X 1 0 2 3 . 6 2 x 1 0 3 6 . 0 4 X 10~ 2

G d 1 5 9 l o " 7 7 . 3 X 1 0 2 1 . 1 X 1 0 6 6 . 6 3 X 1 0 " 4

T b 1 6 0 10 " 8 7 . 3 X 10 1 . 1 1 X 1 0 4 6 . 5 8 X 1 0 " 3

D y 1 6 5 7 X 10 " 7 5 . 1 1 X 1 0 3 8 . 2 X 1 0 6 6 . 2 X 1 0 " 4

D y 1 6 6 7 X 10 " 8 5 . 1 1 X 1 0 2 2 . 3 X 1 0 5 2 . 2 2 X 1 0 " 3

H o 1 6 6 6 X 10 " 8 4 . 3 8 X 1 0 2 6 . 9 X 1 0 5 6 . 4 X 1 0 " 4

E r 1 S 9 10 " 7 7 . 3 X 1 0 2 8 . 2 X 1 0 4 8 . 9 X 1 0 " 3

E t 1 7 1 2 X 10 " 7 1 . 4 6 x 1 0 3 • 2 . 3 5 X 1 0 6 6 . 2 X 1 0 " 4

T m 1 7 0 10 " 8 7 . 3 X 10 6 X 1 0 3 1 . 2 1 X 1 0 " 2

Т Ш 1 1 1 4 X 1 0 " 8 2 . 9 2 x 1 0 2 1 . 1 2 X 1 0 3 2 . 6 X 10"-1

Y b 1 7 5 2 X 10 " 7 1 . 4 6 X 1 0 3 1 . 7 8 X 1 0 5 8 . 2 X 1 0 " 3

L u 1 7 7 2 X 1 0 " 7 1 . 4 6 X 1 0 3 1 . 0 9 x 1 0 5 1 . 3 1 X 1 0 " 2

H f 1 8 1 10 " 8 7 . 3 X 10 1 . 6 2 X 1 0 4 4 . 5 0 X 1 0 " 3

T a 1 8 2 7 X 10 " 9 5 . 1 X 10 6 . 2 X 1 0 3 8 . 2 X 1 0 " 3

W 1 8 1 4 X 1 0 " 8 2 . 9 2 X 1 0 2 4 . 9 8 x 1 0 3 5 . 8 6 X 1 0 " 2

W 1 8 5 4 X 1 0 " 8 2 . 9 2 x 1 0 2 9 . 7 X 1 0 3 3 X 10 " 2

W 1 8 7 10 " 7 7 . 3 X 1 0 2 7 x 1 0 5 1 . 0 4 X 1 0 " 3

R e 1 8 3 5 X 1 0 " 8 3 . 6 5 X 1 0 2 9 . 7 X 1 0 3 3 . 6 7 X 1 0 " 2

R e 1 8 6 8 X 1 0 " 8 5 . 8 4 X 1 0 2 1 . 9 x 1 0 5 3 . 0 7 X 1 0 " 3

R e 1 8 7 2 X 10 " 7 1 . 4 6 x 1 0 3 3 . 8 3 X 1 0 " 8 3 . 8 1 x 1 0 1 0

R e 1 8 8 6 X 1 0 " 8 4 . 3 8 X 1 0 2 1 X 1 0 6 4 . 38 x 1 0 " 4

O S 1 8 5 2 X 1 0 " 8 1 . 4 6 X 1 0 2 7 . 3 X 1 0 3 2 X 1 0 " 2

0 s 1 9 1 m 3 X 1 0 " 6 2 . 1 9 X 1 0 4 1 . 1 7 X 10® 1 . 8 7 X 1 0 " 2

O s 1 9 1 10 " 7 7 . 3 X 1 0 2 4 . 56 X 1 0 4 1 . 6 0 X 1 0 " 2

O s 1 9 3 9 X 1 0 " 8 6 . 5 7 x 1 0 2 5 . 3 X 1 0 5 1 . 2 3 9 X 1 0 " 3

I r 1 9 0 1 0 ' 7 7 . 3 X 1 0 2 6 . 2 X 1 0 4 1 . 1 7 7 X 1 0 " 2

I r 1 9 2 9 X 10 " 9 6 . 5 7 X 10 9 . 1 x 1 0 3 7 . 2 2 X 1 0 " 3

l r 1 9 4 5 X 1 0 " 8 3 . 6 5 X 1 0 2 8 . 5 X 1 0 5 4 . 2 9 X 1 0 " 4

P t 1 9 1 2 X 1 0 " 7 1 . 4 6 X 1 0 3 2 . 2 8 x 1 0 5 6 . 4 X 1 0 " 3

28


Rad i onuc l i d e s

a r r anged i n

o rde r o f i n -


numbe r

( M P C ) £ c *

(168 h / w e e k v a l u e )


m i s s i b l e i n t a ke

i n 1 yr

( M P I ) f * *

expressed i n ¡te

as a resul t of

con t inuous u n i -

f o rm exposure

at ( M P C ) £ c

S p e c i f i c

a c t i v i t y

expressed as

c / g of the


in the c a r r i e r -

f ree state

• M a x i m u m p e r -


t a ke in 1 yr

expressed in

i ig as a result

o f con t i nuous

u n i f o r m e x -

posure at ( M P C )

p t 1 9 3 m 2 X 1 0 " 6 1 . 4 6 X 10 4 1 . 9 9 x 10 5 7 . 3 3 x 10~2

p t 1 9 3 l O " 7 7 . 3 X 10 2 3 . 7 6 1 . 0 94 X 10 2

p t 1 9 7 m 2 X 1 0 " 6 1 . 4 6 X 10 4 1 . 2 2 X 10 7 1 . 1 96 X 10~3

P t 1 9 7 2 X 1 0 " 7 1 . 4 6 X 10 3 8 . 8 x 10 5 1 . 6 5 x 1 0 " 3

A u 1 9 6 2 X 1 0 " 7 1 . 4 6 X 1 0 3 1 . 2 X 10 5 1 . 2 2 x 1 0 " 2

A u 1 9 8 8 x 1 0 " 8 5 . 8 4 X 10 2 2 . 4 5 x 1 0 5 2 . 3 8 X 1 0 " 3

A u 1 9 9 3 X 1 0 " 7 2 . 1 9 X 10 3 2 . 0 9 X 10 5 1 . 0 4 X 1 0 " 2

H g 1 9 7 m 3 X 1 0 " 7 2 . 1 9 X 10 3 6 . 6 X 1 0 5 3 . 3 2 X 1 0 " 3

H g 1 9 7 4 X 1 0 " 7 2 . 9 2 X 10 3 2 . 4 5 X 10 5 1 . 1 9 X 10 " 2

H g 2 0 3 2 X 1 0 " 8 1 . 4 6 X 10 2 1 . 3 7 x 10 4 1 . 0 X 1 0 " 2

T J 2 0 0 4 X 1 0 " 7 2 . 9 2 X 1 0 3 5 . 8 x 1 0 5 5 . 0 3 X 1 0 " 3

T 1 2 0 1 3 X 1 0 " 7 2 . 1 9 X 10 3 2 . 1 7 X 1 0 5 1 X 1 0 " 2

T 1 2 0 2 8 x 1Q" 8 5 . 8 4 X 10 2 5 . 4 X 1 0 4 1 . 0 8 X 1 0 " 2

T 1 2 0 4 9 X 1 0 " 9 6 . 5 7 X 10 4 . 2 8 X 10 2 1 . 5 0 X 1 0 " 1

p b 2 0 3 6 x 1 0 " 7 4 . 3 8 X 10 3 2 . 9 7 X 10 5 1 . 4 7 X 1 0 " 2

P b 2 1 0 4 X 1 0 " 1 1 2 . 9 2 X 1 0 " 1 88 3 X 10 " 3

p b 2 1 2 6 X 10 ~9 4 . 3 8 X 10 1 . 4 X 10 6 3 . 1 3 X 1 0 " 5

B i 2 0 6 . ' 5 X 1 0 " 8 3 . 6 X 10 2 9 . 9 x 1 0 4 3 . 6 8 X 1 0 " 3

B i 2 0 7 ' 5 X 1 0 " 9 3 . 6 5 X 10 2 . 1 6 X 10 2 1 . 6 8 X 1 0 " 1

B i 2 1 0 2 X 1 0 " 9 1 . 4 6 X 10 1 . 2 4 X 1 0 5 1 . 1 7 X 1 0 " 4

B i 2 1 2 3 X 1 0 " 8 • 2 . 1 9 X 10 2 1 . 4 7 X 10 7 1 . 4 8 9 X 1 0 " 5

P o 2 1 0 7 X 1 0 " 1 1 5 . 1 1 X 1 0 " 1 4 . 5 X 1 0 3 1 . 1 4 X 1 0 " 4

A t 2 1 1 2 X 10 " 9 1 . 4 6 X 10 2 . 0 6 x 10 6 7 . 1 X 10~6

R n 2 2 0 10 " 7 7 . 3 X 10 2 9 . 4 x 10 8 7 . 8 X 10~7

R n 2 2 2 10 " 7 7 . 3 X 1 0 2 1 . 5 4 X 1 0 5 4 . 9 X 1 0 " 3

R a 2 2 3 8 X 1 0 " 1 1 5 . 8 4 X 1 0 " 1 .5 X 1 0 4 1 . 2 X 10~ 5

R a 2 2 4 2 X 10 " 1 0 1 . 4 6 1. 6 X 1 0 5 9 . 1 X 1 0 " 6

R a 2 2 6 l O " 1 1 7 . 3 X 1 0 " 2 0 . 9 8 7 . 5 X 10~ 2

R a 2 2 8 1 0 - 1 1 7 . 3 X 10 " 2 2 . 3 4 X 1 0 2 3 . 1 X 1 0 " 4

A c 2 2 7 8 X 1 0 " 1 3 5 . 8 4 X 1 0 " 3 72 8 X 1 0 " 5

29



a r r a nged i n

o rde r o f i n -


n u m b e r

( M P C ) M c *

(168 h / w e e k v a l u e )



i n 1 yr

( M P I ) f * *

expressed i n цс

as a resu l t o f


f o r m exposure

at ( M P C ) ^ c

S p e c i f i c

a c t i v i t y

expressed as

c / g o f t he



f ree s ta te



t a k e i n 1 y r

expressed i n

ig as a resu l t


u n i f o r m e x -

posure at ( M P C ) j ®

A c 2 2 8 6 X 1 0 " 9 4 . 3 8 X 10 2 . 2 4 X 10 6 1 . 9 5 X 1 0 " 5

T h 2 2 7 6 X 1 0 " 1 1 4 . 3 8 X 10 3 . 1 7 X 1 0 4 1 . 3 8 X 10 " 5

T h 2 2 8 2 X 1 0 " 1 2 1 . 4 6 X 1 0 " 2 8 . 3 X 1 0 2 1 . 7 5 X 10 " 5

T h 2 3 0 8 X 1 0 " 1 3 5 . 8 4 X 1 0 " 3 1 . 9 4 X 1 0 " 2 3 . 0 1 X 1 0 " 1

T h 2 3 1 4 X 1 0 " 7 2 . 9 2 X 10 3 5 . 3 X 1 0 5 5 . 5 X 1 0 " 3

T h 2 3 2 l o " 1 1 . 7 . 3 X 10~ 2 1 . 1 1 X 1 0 " 7 6 . 6 4 X 1 0 5

T h 2 3 4 10 " 8 7 . 3 X 10 2 . 3 2 X 1 0 4 3 . 1 0 X 1 0 " 3

T h - N a t 1 0 - 1 1 7 . 3 X 1 0 " 2 1 . 1 X 10 " 7 6 . 6 4 X 1 0 5

P a 2 3 0 3 X 1 0 " 1 0 2 . 1 9 3 . 2 1 X 1 0 4 6 . 8 X 10 " 5

P a 2 3 1 4 X 1 0 " 1 3 2 . 9 2 X 1 0 " 3 4 . 5 2 X 1 0 " 2 6 . 4 7 x 1 0 " 2

P a 2 3 3 , 6 X 1 0 " 8 4 . 3 8 x 1 0 2 2 . 0 8 x 1 0 4 2 . 1 0 X 1 0 " 2

ц 2 3 0 4 X 1 0 " 1 1 2 . 9 2 X 1 0 " 1 2 . 7 3 X 1 0 4 1 . 0 6 X 10~ 5

ц 2 3 2 9 x 1 0 " 1 2 6 . 5 7 X 1 0 " 2 2 0 . 8 3 . 1 5 X 1 0 " 3

ц 2 3 3 4 X 1 0 " 1 1 2 . 9 2 X 10 9 . 5 X 1 0 " 3 3 . 0 7 X 10

и 2 3 4 4 X 1 0 " 1 1 2 . 9 2 X 1 0 " 1 6 . 2 X 1 0 " 3 4 . 7 0 X 10

и 2 3 5 4 X 1 0 " 1 1 2 . 9 2 X 1 0 " 1 2 . 1 4 X 1 0 " 6 1 . 3 6 X 1 0 5

ц 2 3 6 4 X 10 " П 2 . 9 2 X 10 6 . 3 X 1 0 " 5 4 . 7 x 1 0 3

ц 2 3 8 3 X 1 0 " 1 1 2 . 1 9 X 1 0 - 1 3 . 3 3 X 1 0 " 7 6 . 5 7 X 1 0 5

U - N a t 2 X 1 0 " 1 1 1 . 4 6 X 1 0 " 1 3 . 3 X 1 0 " 7 4 . 4 X 1 0 5

N p 2 3 7 l O " 1 2 7 . 3 X 1 0 " 3 6 . 9 X 1 0 " 4 1 . 0 5 X 10

N P2 3 9 2 X 1 0 " 7 1 . 4 6 X 1 0 3 2 . 3 3 X 1 0 5 6 . 2 6 X 1 0 " 3

P u 2 3 8 7 x 1 0 " 1 3 5 . 1 1 X 1 0 " 3 1 6 . 8 3 X 1 0 - 4

P u 2 3 9 6 X 1 0 " 1 3 4 . 3 8 X 10 " 3 6 . 1 X 1 0 " 2 7 . 1 8 X 1 0 " 2

P u 2 4 0 6 x 1 0 " 1 3 4 . 3 8 X 10 " 3 0 . 2 2 7 1 . 9 2 9 X 1 0 " 2

P u 2 4 1 3 x 1 0 " 1 1 2 . 1 9 X 1 0 " 1 1 . 1 4 X 1 0 2 1 . 9 2 X 1 0 " 3

P u 2 4 2 6 x 1 0 " 1 3 4 . 3 8 X 1 0 " 3 3 . 9 X 1 0 " 3 1 . 1 2

A m 2 4 1 2 x 1 0 " 1 2 1 . 4 6 X 10 " 2 3 . 2 4 4 . 5 X 10 " 3

A m 2 4 3 2 x l o " 1 2 1 . 4 6 X 10 " 2 0 . 1 8 5 7 . 8 9 X 1 0 " 2

C m 2 4 2 4 x 1 0 " 1 1 2 . 9 2 X 10 3 . 3 2 X 1 0 3 8 . 7 9 X 1 0 " 5

30


Rad ionuc l i des

a r ranged i n

order of i n -

c reas ing a t o m i c

number

( M P C ) *

( 1 6 8 h / w e e k va l ue )


m i s s i b l e in take

in 1 yr

(MP I ) j J c * *

expressed i n цс

as a result of -

cont inuous u n i -

f o rm exposure

a t ( M P C ) M c

S p e c i f i c

a c t i v i t y

expressed as

c / g o f the

r a d i onu c l i d e


f ree state



t a ke i n 1 yr

expressed i n

fig as a result

o f con t inuous

u n i f o r m e x -

posure at ( M P C ) №

C m 2 4 3 2 X 1 0 " 1 2 1 . 4 6 X 10 " 2 4 2 . 1 3 . 4 X 1 0 " 4

C m 2 4 4 3 X 1 0 " 1 2 2 . 1 9 X 1 0 " 2 82 2 . 6 X 1 0 " 4

C m 2 4 5 2 X 1 0~ 1 2 1 . 4 6 X 10 " 2 1 . 0 4 X 1 0 " 1 1 . 4 X 1 0 " 1

C m 2 4 6 2 X 10 " 1 2 1 . 4 6 X 10 " 2 3 . 6 4 X 1 0 " 1 4 . 0 1 X 1 0 " 2

B k 2 4 9 3 X 1 0 " 1 0 2 . 1 9 1 . 8 0 x 10 3 1 . 216 X 1 0 " 3

C f 2 4 9 5 X 1 0 " 1 3 3 , 6 5 X 10 " 3 3 . 0 5 1 . 19 X 1 0 " 3

c f 2 5 0 2 X 1 0 " 1 2 1 . 4 6 X 10 " 2 1 . 3 1 X 10 2 1 . 1 1 X 1 0 " 4

C f 2 5 2 2 X 1 0 " 1 2 1 . 4 6 X 10 " 2 6 . 5 X 1 0 2 2 . 2 4 X 1 0 " 6

31


R A D I O N U C L I D E S C L A S S I F I E D A C C O R D I N G T O T H E I R R A D I O T O X I C I T Y

Radionuclides Number* indi- Radionuclides arranged Number* indi-(in alphabetical cating rank of according to their cating rank of

order) radionuclides relative radiotoxicity radionuclides in the Table in the Table

A c 2 2 7 7 Pa 2 3 1 1

A c 2 2 8 50 C f 2 4 9 2

A g 1 0 5 95 P u 2 4 0 3

A g 1 1 0 m 44 P u 2 3 9 > * * 4

A g 1 U 140 PU 2 4 2 5

Am 2 4 1 14 P u 2 3 8 6

Am 2 4 3 16 Ac 2 2 7 • * *

7

Ar37 236 T h 2 3 0

• * *

8

Ar41

As73

185

161

NP 2 3 7

H T h 2 2 8 . '

9

10

As7 4

As76

102

90

- C f 2 5 2 U - C f 2 5 0

11

12

As77 154 * C m 2 4 3 13

A t 2 1 1 37 H Am 2 4 1 • * * 14

Au 1 9 6 176 Œ

Au 1 9 8 138 ° C m 2 4 6 15

Au 1 9 9 182 X Am 2 4 3 16

Ba 1 3 1 157 C m 2 4 5 . 17

В а 1 4 0 61 C m 2 4 4 18

Be7 189 ц 232 19

B i 2 0 6 117 Ra2 2 8 * * 20

B i 2 0 7 48 Ra2 2 6 , * *

21

B i 2 1 0 38 Pu 2 4 1 22

B i 2 1 2 88 Ц23Ь 23

Bk 2 4 9 35 C m 2 4 2 * * 24

Br82 122 Pb210 25

* This number only serves as an Indication of where to find the radionuclide (rank) and has no numerical significance beyond that.

* * This bracket indicates that these radionuclides have the same value for MPI expressed in fic and they are arranged according to the MPI expressed in )jg in increasing order.

32


Radionuclides Number * indi- Radionuclides arranged Number * indi-(in alphabetical cating rank of according to their cating rank of

order). radionuclides relative radiotoxicity radionuclides in the Table in the Table

c 1 4 203 u233 26

C a 4 5 68 G "234 Г * 27

Ca 4 7 126 £ T h 2 2 7 О

28

Cd 1 0 9 83 H p o210 29

c d 1 1 5 m 63 1 Ra 2 2 3 30

C d 1 1 5 127 ï S r 9 0 31

C e 1 4 1 118 U 2 3 6 32

C e 1 4 3 132 Ra 2 2 4 33

C e 1 4 4 40 Pa 2 3 0 1 34

c f 2 4 9 2 Bk 2 4 9 Г * 35

c f 2 5 0 12 Eu 1 5 4 36

c f 2 5 2 11 At 2 1 1 37

C I 3 6 56 B i210 38

C I 3 8 195 * Ru1 0 6 > * îjc

39

C m 2 4 2 24 b C e 1 4 4 40

C m 2 4 3 13 " ,131 и 1 41

C m 2 4 4 18 „ j 126 42

C m 2 4 5 17 * 92 О N a

> • * 43

C m 2 4 6 15 Upper A (_ A g l l 0 m 44

Co 5 7 131 2 C o 6 0 . 45

Co5 8™ 226 ! C s 1 3 4 1 • 46

CO58 78 D EU152>- Г * 47

C o 6 0 45 ^ B i 2 0 7 : i 48

Cr 5 1 197 C s 1 3 7 . • * *

49

C s 1 3 1 202 A c 2 2 8 50

C s134m 222 . P b 2 1 2 • * *

51

C s 1 3 4 46 I n114m : 52

C s 1 3 5 214 S b 1 2 4 > * * 53

C s 1 3 6 128 Т а 1 8 2 . 54

C s 1 3 7 49 ' S e 4 6 . ' > * * 55

Cu 6 4 186 C l 3 6 J 56

33


Radionuclides (in alphabetical

order)

Number * indi-cating rank of radionuclides in the Table

Radionuclides arranged according to their

relative radiotoxicity

Number * indi-cating rank of radionuclides

in the Table

Dy 1 6 5 196 !" I r 1 9 2 S H Ir 57

Dy 1 6 6 134 S У oul25 S * sb 58

E r169 158 2 g T ,204 59

E r 1 7 1 169 ,133 60

E u152(h) 151 Ba 1 4 0 61

E u 1 5 2 W 47 S r 8 9 62

Eu1 5 4 36 * C d 1 1 5 m 63

Eu 1 5 5 97 „ y 9 1 64 '

F 1 8 198 " T e 129m 65

Fe 5 5 184 X x h 2 3 4 66

О Fe 5 9 77 Upper A H Z r 9 5 • * * 67

Ga 7 2 121 2 Ca 4 * 68

Gd 1 5 3 96 a Hf 1 8 1 69

Gd 1 5 9 153 D G e " 224 ы T b 160 70

H3 225 2 T e 1 2 7 m 71

H f181 69 Mn54 72

H g197m 180 T m 1 7 0 . 73

Hg1 9 7 190 p32 74

Hg 2 0 3 79 V 4 8 75

Но1 6 6 125 Rb86 76

,126 42 H Fe 5 9 77

j 129 211 " Co 5 8 и 78

j 131 41 - Hg2 0 3 79

,132 135 o sn"3 80

,133 60 Lower В H Z n 6 5 > * *

81

,134 165 S Os 1 8 5 82

,135 99 = C d 1 0 9 . 83

,n113m 220 O Pm 1 4 7 84

,n114m 52 " Ni6 3 2

85

,n115m 192 S m 1 5 1 86

I n 1 1 5 212 T e 9 9 87

34



order)





in the Table

Ir190 159 Bl212 88

Ir192 57 Zr 9 7 89

Ir194 114 As76 90

K 4 2 98 y 90 91

Kr85m 200 Sn 1 2 5 92

Kr85 229 Nb95 93

Kr87 164 Ru103 94

La1 4 0 100 Ag1 0 5 95

Lu177 177 Gd 1 5 3 96

Mn52 115 Eu155 • 97

Mn54 72 К 4 2 . 98

Mn56 166 j 135 99

M o " 138 !" La1 4 0 100

Na22 43 * Т е 1 3 2 101

Na2 4 110 и

№93Ш 109 К As74 102

Nb95 93 О S r S5 > * & 103

Nb97 219 Lower В H X e125m 104 . Nb97

s Nd1 4 4 209 B Se 105

Nd147 141 « w 185 106 Q

Nd149 191 « w 1 8 1 107

Ni59 216 S T m 1 7 1 108

Ni63 85 Nb 9 3 m 109

№ 6 5 167 Na24 ' 110

Np237 9 Y93 111

Np239 173 . Sc 4 8 112

OS185 82 P r142 113

0 s191m 227 Ir194 114

Os1 9 1 160 Mn52 ' * * 115

Os 1 9 3 144 Sb 1 2 2 116

p32 74 Bi206 117

Pa 2 3 0 34 C e 1 4 1 • 118

Pa 2 3 1 1 T c 97m 119

Pa 2 3 3 130 Re1 8 3 120

35



order)





in the Table

p b203 194 G a 7 2 121

p b210 25 Br 8 2 122

P b 212 51 Re 1 8 8 123

P d 1 0 3 183 T e 1 3 1 m 124

p d 1 0 9 152 Ho 1 6 6 125

P m 1 4 7 . 84 Ca 4 7 126

P m 1 4 9 136 C d 1 1 5 127

P o210 29 C s 1 3 6 . 128

P r 142 113 p r 143 129

P r 143 129 P a 2 3 3 130

p t 1 9 1 174 Co 5 7 . 131

P t 193m 223 C e 1 4 3 132

P t 1 9 3 >-

P t 1 9 3 162 ' H Mo9 9 - 133

P t 1 9 7 m 221 ~ D y 1 6 6 и '

134

p t 1 9 7 170 « ¡132 135

P u 238 6 О p - 1 4 9 136

P u239 4 Lower В H Т с 9 6 137

Pu 2 4 0 3 S Au 1 9 8 138

Pu 2 4 1 22 ® R e 1 8 6 > * * ,

139

Pu 2 4 2 5 O A g 1 1 1 140

R a 2 2 3 30 » N d " 7 141

R a 2 2 4 33 T 1 2 0 2 142

Ra 2 2 6 21 S r 9 1 143

R a 2 2 8 20 O s 1 9 3 • * * 144

Rb86 76 S 3 5 145

Rb87 213 Rn 2 2 0 ' 146

R e 1 8 3 120 Rn 2 2 2 147

Re 1 8 6 139 S r 9 2 148

Re 1 8 7 217 y 9 2 149

Re 1 8 8 123 Z n 69m • * * 150

R h 1 0 3 m 235 E u 1 5 2 h 151

R h 1 0 5 172 P d109 152

R n 2 2 0 146 G d 1 5 9 153

36



order)

Number * indi-cating rank of radionuclides in the Tab le




in the Table

Rn 2 2 2 147 As77 154

Ru97 193 W 1 8 7 155

Ru 1 0 3 . 94 S m 1 5 3 156

Ru 1 0 5 1 6 8 B a 1 3 1 157

Ru 1 0 6 39 E r 1 6 9 158

s 35 145 I r 190 > * * 159

S b 1 2 2 116 O s 1 9 1 160

S b 1 2 4 53 As7 3 161

S b 1 2 5 58 p t 1 9 3 162

S c 4 6 55 T c 9 7 . 163

S c 4 7 171 Kr 8 7 1 6 4

S c 4 8 112 r" H I 1 3 4 165

S e 7 5 105 - Mn 5 6 166 и

S i 3 1 1 7 8 - Ni 6 5 167

S m 1 4 7 207 S 168

S m 1 5 1 86 Lower В H E r 1 7 1 169

S m 1 5 3 156 S P t 1 9 7 170

S n 1 1 3 80 О S e 4 7 • ' ' '

171

S n 1 2 5 • 92 Q R h 1 0 5 . " 1 7 2

S r 8 5 m 234 g N p 2 3 9 173

S r 8 5 103 P t 1 9 1 174

S r 8 9 62 Y b 1 7 5 175

S r 9 0 31 A u 1 9 6 176

S r 9 1 143 Lu 1 7 7 : 177

S r 9 2 148 S i 3 1 178

T a 1 8 2 54 ' T e 1 2 7 179

T b 1 6 0 70 H g 1 9 7 m 180

T c 9 6 m 233 T 1 2 0 1 • * * 181

T c 9 6 137 A u 1 9 9 182

T c 9 7 m 119 P d 1 0 3 183

T c 9 7 1 6 3 F e 5 5 184

37


Radionuclides Number * indi- Radionuclides arranged Number* indi-(in alphabetical cating rank of according to their cating rank of

order) radionuclides relative radiotoxicity radionuclides in the Table in the Table

T c 9 9 m 231 ^ A r 4 1 185

T c 9 9 87 ^ C u 6 4 186

j e 1 2 5 m 104 U T 1 2 0 0 187

T e 1 2 7 m 71 X T h 2 3 1 188

T e 1 2 7 179 О Be7 189

T e 1 2 9 m 65 Lower В H 197 Hg

• 190

T e 1 2 9 199 S N d 1 4 9 191

T e 1 3 1 m 124 - I n 115m 192

T e 1 3 2 101 ^ Ru9 7 193

T h 2 2 7 28 s P b 2 0 3 194

T h 2 2 8 10 ! " C I 3 8 195

T h 2 3 0 8 5 D y 1 6 5 196

T h 2 3 1 188 S Cr51 197

T h 2 3 2 205 H p 18 198

T h 2 3 4 66 1 т е 1 2 9 199

Th-Nat 204 S K r 8 5 m 200

T 1 2 0 0 187 I X e 1 3 5 • * * 201

T 1 2 0 1 181 ? C s 1 3 1 202

T 1 2 0 2 142 2 C 1 4 203

T 1 2 0 4 59 T h n a t - 204

T m 1 7 0 73 T h 2 3 2 205

T m 1 7 1 108 * u n a t 206

ц 2 3 0 23 ^ S m 1 4 7 • * *

207

ц 2 3 2 19 U 0 2 3 8 208

ц 2 3 3 26 К N d 1 4 4 . 209

и 2 3 4 27 O j j235 210

ц 2 3 5 210 H j 129 211

ц 2 3 6 32 S I n 1 1 5 о

212

ц 2 3 8 208 -J Rb8 7 213

U-Nat 206 C s 1 3 5 214

у 4 8 75 Z r 9 3 215

38



order)




Number* indi-cating rank of radionuclides in the Table

w 1 8 1 107 Ni5 9 216

w 1 8 5 106 Re 1 8 7 217

w 187 165 .Zn 6 9 ' 218

X e 1 3 1 m 230 Nb 9 7 " 219

X e 1 3 3 228 I n113m 220

X e 1 3 5 201 p t 197m 221

y 9 0 91 C s 1 3 4 m • * *

222 >•

Y 91m 232 H P t 1 9 3 m 223

y91 64 о G * 7 1 224

Y 9 2 149 - H3 J 225

y 9 3 111 O C o 5 8 m 226

Y b 1 7 5 175 И O s 1 9 1 m 227

z 9 3 215 Э X e 1 3 3 > * *

228

Zn 6 5 81 О KJ.85 229

Z n 6 9 m 150 X e 1 3 1 m 230

Zn 6 9 218 T c 9 9 m 231

Z r 9 5 67 y 9 1 m 232

Zr 9 7 87 T c 9 6 m 233

S r 8 5 m 234

R h 1 0 3 m 235

Ar3 7 236

39

C O N S U L T A N T S

United Kingdom Atomic Energy Authority, Harwe l l

United Kingdom Atomic Energy Authority, R is ley , Warrington

Centre d 'é tudes nucléaires, Fontenay-aux-Roses , France

United States Atomic Energy Commiss ion, Washington, D. C.

A G E N C Y S T A F F MEMBERS

Dr. H. T . DAW Divis ion of Health, Safety and (Scient i f ic Secre tary ) Waste Disposal

P r o f e s s o r R. J A E G E R Divis ion of Isotopes

D r . G . W. D O L P H I N

M r . A . F A I R B A I R N

Dr. H. J A M M E T

Mr . L . R. ROGERS

Mr . G. E. S W I N D E L L Div is ion of Health, Safety and Waste Disposal

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BIBLIOGRAPHICAL SERIES

No. 5 (1962): Disposal of Radioactive Wastes into Marine and Fresh Waters

365 pp. (16 X 24 cm) US $3.00; Elsewhere 18s. stg.

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O Rh ,103m TABLE FOR A BASIC TOXICITY CLASSIFICrASSIFICATION OF RADIONUCLIDES

(MPI ) }J

H o -

LOWER В

h o ;

W-O Rn 220

7.8 "Ю ,-7

MEDIUM

Mo'

UPPER A

At 211

LlO'-

LOW

CI 38

Kr

О Si31

¡134 Mn56

° ° ° ° N i 6 5 87 ™

,Zn 69 Mh97 o N b о

In

Tc96m o oSr85"1

Оу91ш

Tc99m о

о Co' 58 m

n.197m r „134 m

113m

•>Te 129 Kr85m Xe ,135

о In ,115m 97

ONd 149

oCu

Te,2Z-o

64 Tl

Ru

200 Be7

,Ru Ю5

Sr92

O OY

Er .171

231

OOs 191m

Pt ,193m

O Xe 131m

O Xe .133

°Ge7'

O»* °Cr51

Pb о

j197

,201

203

Rh105

Se 193

о Hg ,197m л TI"

? Au'99 o Pd ,103

_239

Í.175 О Lu

,92 Zn о F 152h 159 EU ,109 Gd

Oj132

ON» 24

OQPd

- I — P « W187 / с О J

O Y

to72 О

•93

°Sr91 131m

Re — Br«2_

.. , Sm153 Rn222

4 7 ° ? s " ? ° ТС9® A'J98 ;86 ° jg ,147 ' 143 Mn®® o o o oRe N d o

;0 M?0 9 о . . ° oAg111

Npo

o Yb1 , pt191 I Au

Fp'69

.177

.196

Cei

S c 4 - ° / °° «4 H0B6 » , ¿142 О La'4® O r ®

As РГ OP32

^ I " , Prcr O O o Cd 15

OK42 OI135 Mn 52

эТе';

Sb

O B¡ 212 I О О Zr97

.122 Dy166

B ¡ 2 0 6 О ооРг'

Cs136 .143

OAs .74

О у90

г 133

Ас О 228

°РЬ212

Ра' О

230

О Ra 224

Но1

H I G H

МО -1

МО - 2

О Ra 223

о и

O Th

230

227

°Sn 125 95 Ag

Nb О сР

105

Ru»3

О V 48 Rb»i-0 О Fe59

О Со58

Y91 Te,29mCa45'

,190 « i 73

Os35

As

Tl 202

О Pa' 233 О Co 57

Ce .141 o Tc97m о Re183

О О О w185

Те12 5m Se75 o w 181

О Gd .153

0Ba,4° SrH. \

.,210

131 ,126

PO 210

О Cm 242

Th 228

O Oq 252

Ac' О 227

10 ,-15

O Ra 228

O Cm 244

OCf 250 О Cm243

о Pu 238

10 - к

Se46 Cd1l5m q Hf

/ T b w V ° 9 .«181 o p '

Te

Hg203 Zn65

о 0 ooos Sn"3

127m. i

185 O Cd ,109

.95 о о Z r /

|n144mSbl24 Ir192

,_ . O Tm о O j

I "Mn O î a 1 8 2

.170

54 О Sb .125

Na22 Ag"0m О о

Ru106 OOCe'44

OTh 234

O Bk 249

О Sr90

О Pu

О Pb 241

210

О U 232

О Am24'

10

О Cf

-13

249

О Co

О Eu ,154

О I

O Fe 55

o Tm 171 О Nb'

,155 О Eu

О Pm147

o Tl 204

OBI207 OCS137

О Eu152y

O Ra 226

O Cm246 О I о с т 2 4 5

Am 243

O Th 230

О Pu 240 О Pu 239

О Pa 231

1 0 .-12

10 - 1 1

10

О Pu

•10

о HJ

o Fe 55

93т О Nb' 93 т

242 О Pu 242

ю - ю

,.63 о

Sm O

151

ó A37

(MPI)£ 7.3 ИО®

Kr О

85

O Pt 193

и233 и234

О о

O Np 237

10 - 9

J2 - 8

о с"

о Тс 97

Тс99 о

о Cl 36

о и 236

10

O Ni .59

Zr 93

О 1 129

J2 - 6

( M P C ) j jc

1 0 " 6 — I

Re 187

•10

3.8 *10 O

- 7

O Cs 135

Rb87

2.3 «109

10 - 8

o » |

1.4.10,3I

-10 - 9

-io-10—I

Nd 144 1.76 «10

O U 235

и238 o o „147 Sm"

U-Nat O O 7.5 "Ю6

10' -11

T h 2 ^ o Th-Nal-^

-10 .-12

fi* ( M P C ) p g

10"! 10~4 10 - 3 10 - 2 10

-1 10 10 10' 10' 1 0 ' 10' 105 ( M P I ) Jig

INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA 1963

PRICE: North America, US$1.00 Elsewhere: Sch 21,-I6s.stg, NF 4,-; DM 3,20)

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