This document is copyright protectedJ. VENNART The Commission wishes to acknowledge its indebtedness to J. Vennart for his unselfish efforts in providing direction and leadership to

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PREFACE

In 1977 the Commission issued new radiation protection guidance in its ICRP Publication 26. Subsequently Committee 2 was asked to prepare a new version of its report on Permissible Dose for Internal Radiation, which was issued in 1959 as ICRP Publication 2. The revised report, Limits for Intakes of Radionuclides by Workers, was issued in three parts with supplements as ICRP Publication 30 between 1979 and 1982. Preparation of Publication 30 drew heavily upon the advice given by Task Groups on reference man, on lung dynamics, on the radiosensitivity of the tissues of bone, and on metabolism of compounds of plutonium and other actinides.

In 1981 the Commission established a Task Group to review, update and extend the information on the metabolism of plutonium, neptunium and trivalent actinides, previously reviewed in ICRP Publication 19. Specific attention was directed towards information regarding absorption from the gastrointestinal tract and the distribution between, and retention within the skeleton and the liver. In 1986 the report of this Task Group was issued as ZCRP Publication 48 entitled “The Metabolism of Plutonium and Related Elements”. Because Publication 30 relied on ZCRP Publication 19 for information regarding the metabolic behaviour of plutonium, neptunium, and the trivalent actinides, the suggested changes in metabolic parameters for these elements have implications to the values of the secondary limits presented in ICRP Pubiication 30. In this addendum to ICRP Publication 30, secondary limits for isotopes of neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium and mendelevium are presented.

Secondary limits are also presented for the first time for a number of isotopes of elements other than those discussed in ICRP Publication 48. These are for *‘Sr, g5mT~, 95T~, ‘l?Sb. 246Pu and 250Cm.

During the period of preparation of this report (1986-1987) the membership of Committee 2 was:

C. B. Meinhold (Chairman) G. Drexler J. P. Moroni J. 0. Snihs W. J. Bair K. F. Eckerman Y. I. Moskalev* D. M. Taylor X. Chen A. Kaul N. Parmentier R. H. Thomas R. H. Clarke 0. Matsuoka C. R. Richmond

The dosimetric calculations have been the responsibility of the Task Group on dose calculations, originally established to perform the calculations for ICRP Publication 30. The membership of the Task Group during the preparation of this report was:

K. F. Eckerman (Chairman) L. T. Dillman M. Cristy R. W. Leggett

The Task Group gratefully acknowledges the assistance of J. C. Ryman in performing the calculations on which this report is based.

V

DEDICATION

J. VENNART

The Commission wishes to acknowledge its indebtedness to J. Vennart for his unselfish efforts in providing direction and leadership to Committee 2 and for his innumerable contributions to Publication 30 and many other ICRP reports. Dr Vennart’s skilled leadership of Committee 2 fostered a collegial atmosphere which made it possible to complete Publication 30, a document whose preparation required enormous amounts of time and energy. Dr Vennart was tireless in his own efforts and always welcomed and encouraged further discussion within the Committee. He masterfully guided resolution of controversial issues through his insights into and knowledge of a wide range of topics. The Commission and Committee 2 extend their deepest appreciation to Dr Vennart and respectfully dedicate to him this addendum to Publication 30.

vi

INTRODUCTION

In 1979 the International Commission on Radiological Protection issued ICRP Publica- tion 30; Limits for Intakes of Radionuclides by Workers.’ In 1981 the Commission established a Task Group to review, update and extend the information on the metabolism of plutonium, neptunium and trivalent actinides as previously reviewed in 1972 in ICRP Publication 19.2 Specific attention was directed towards information regarding absorption from the gastrointestinal tract and the distribution between, and retention within, the skeleton and the liver. In 1986 the report of this Task Group was issued as ICRP Publication 483 entitled “The Metabolism of Plutonium and Related Elements”. Because Publication 30 had relied heavily upon ZCRP Publication 19, the information presented in ICRP Publication 48 regarding the behaviour in the body of plutonium, neptunium, and the trivalent actinides has implications for the values of the secondary limits presented in ICRP Publication 30. In this addendum to ICRP Publication 30, secondary limits for isotopes of neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium, and mendelevium are presented, based on the recommendations of ICRP Publication 48.

Secondary limits are also presented for a number of isotopes of elements other than those discussed in ICRP Publication 48. For these radionuclides, nuclear decay data were not available at the time the calculations for the element were performed, but details were later tabulated in ZCRP Publication 38.4 For this reason secondary limits are presented here for the first time for **Sr, 95mT~ 95T~, 1 ‘%b, 246Pu and *“Cm. With the exception of the latter two radionuclides, the metabolic models used in this calculation are those given in ZCRP Publication 30 and will not be discussed further. The data for 246Pu and 250Cm are presented with the revised secondary limits for plutonium and curium.

This report is concerned with the numerical value of the secondary limits, the Annual Limit on Intake (ALI) and the Derived Air Concentration (DAC), for a limited number of radionuclides. For neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium and mendelevium, the secondary limits are presented following a brief description of the metabolic data for the element. The text simply indicates the metabolic parameters used in the calculations; for an indepth discussion of the metabolic information, the reader should consult ZCRP Publication 48. The dosimetric models used in the calculations are not discussed here; the reader is referred to ICRP Publication 30, Part 1. For the additional radionuclides no description of the metabolic models for these elements is included here. That information can also be found in ICRP Publication 30. Dosimetric data for the radionuclides are given in an appendix to this report; these data supersede that contained in the Supplements to ICRP Publication 30.

METABOLIC DATA FOR NEPTUNIUM

1. Metabolism

Neptunium is not a naturally occurring element and data are not available on its distribution in man. Reliance must therefore be placed on animal data. These data have been recently reviewed by a Task Group and their report ICRP Publication 48,3 provides the basis for the metabolic data presented here. Only information directly applicable to the calculation of secondary limits for neptunium is presented; further information can be found in ZCRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

Data on the absorption of neptunium from the gastrointestinal tract of several species were reviewed by the Task Group. Early studies, using the nitrate, showed that in rats gavaged with several mg of 237Np per kg body mass the fractional absorption was about 0.01 to 0.02.5 Subsequent experiments,6-8 again using the nitrate, clearly showed a marked effect of administered mass on neptunium absorption. At mass levels between 22 and 43 mg of 237Np per kg body mass, the fractional absorption by rats varied from about 0.01 to about 0.03. However, for an administered mass of only 10 mg per kg body mass, absorption was about a factor of 10 less. The Task Group considered that a value of 10m3 was appropriate as a best estimate of absorption of neptunium from the gastrointestinal tract.

(b) Inhalation classes

The Task Group reviewed recent information on the behaviour on inhaled neptunium compounds and concluded that the small amount of available data were not inconsistent with the assignment in ZCRP Publication 301 of all neptunium compounds to inhalation Class W.

Inhalation class ./;

D W 10-a Y

(c) Distribution and retention

Data on the distribution of neptunium indicate that its metabolic behaviour is not dissimilar to that of plutonium; however, in the skeleton, neptunium may be distributed more like calcium than plutonium. The Task Group suggested that, of neptunium leaving the transfer compartments, 75% should be assumed to translocate to mineral bone and 15% to the liver. The fraction of neptunium transiocated to gonadal tissue is estimated to be 10e5 per gramme which corresponds to a fractional transfer of 3.5 x 10V4 for the testes and 1.1 x 10e4 for the ovaries. The remainder of neptunium leaving the transfer compartment is assumed to clear with a half-time of 0.25 days.

Neptunium translocated to mineral bone is assumed to be removed with a half-time of

?

4 REPORT OF COMMITTEE 2

50 years, while neptunium translocated to the liver is assumed to be removed with a half-time of 20 years. Neptunium translocated to the gonads is assumed to be permanently retained.

3. Classification of Isotopes for Bone Dosimetry

The initial deposition of neptunium in bone is more like calcium than plutonium.’ It is, nevertheless, primarily associated with bone surfaces at early times after deposition and is unlikely to be as mobile in the bone matrix as are the alkaline earths. For these reasons neptunium, like the other actinides, is assumed to be uniformly distributed over the endosteal surfaces of mineral bone at all times following its deposition in the skeleton.

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m”) (40 h/wk) for isotopes of neptunium

Inhalation

Oral Class W

Radionuclide f,=lO_s f,=lO_3

‘=Np

236Np T,,,= 1.15 x 10’~

236Np T,,, =22.5 h

237Np

23sNp

239Np

240Np

ALI

DAC AL1 DAC AL1 DAC AL1

DAC AL1

DAC AL1

DAC AL1

DAC AL1

DAC AL1

DAC AL1 DAC

5x109

3 x 10’0

8 x 10’

8 x lo* (9 x 108) LLI wall

9x10& (2 x 105) Bone surf.

1 x 108 (1 x 106) Bone surf.

2x lo4 (5 x 104) Bone surf.

5 x 10’

6x10’ (6 x 10’) LLI wall

8 x 10

I x 10’ (2 x 108) Bone surf. 3 x lo4 1 x 10” 5 x 10’ 1 x 10s 4x lo4 3 x 10’

(5 x 10’) Bone surf. 1 x lo4

(2 Yo3, Bone surf.

0.3 1 x lo6

(3 x 106) Bone surf.

400

(E) Bone surf.

0.06 2 x lo6

(6 x 106) Bone surf. 1 x lo3 8 x 10’

3x104 3 x lo9 1 x IO6

LIMITS FOR INTAKES OF RADIONUCLIDES BY WORKERS

2. METABOLIC DATA FOR PLUTONIUM

1. Metabolism

No data are given in ICRP Publication 23’ O for plutonium. However, there are measurable quantities of this element in food and in human tissues as a result of contamination with world- wide fallout from nuclear weapon tests. There are also data on the distribution of plutonium in people occupationally exposed to plutonium. These limited human data support and confirm, in general, the much more extensive metabolic data from studies with experimental animals. The metabolism of plutonium was recently reviewed by a Task Group and their report, ICRP Publication 4d3, supplements the report of an earlier Task Group’ and provides the basis for the metabolic data presented here. Only information directly applicable to the calculation of secondary limits for plutonium are presented; further information can be found in ZCRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

Absorption of plutonium from the gastrointestinal tract is low. Data reviewed by the Task Group suggest anfi value larger than that assumed in ZCRP Publication 30,’ but not greater than 10-3. This value would appear to provide a sufficient margin of safety for radiation protection in situations where the intake or the chemical or physical state cannot be described precisely. For occupational exposure, smaller values may be justified where the chemical and physical state of the ingested material can be confidently established. For insoluble oxides, free of very small (nanometre-sized) particles, the Task Group retained the ICRP Publication 30 value of 10W5. Similarly, for plutonium nitrate, the Task Group retained the current value of 10-4.

The Task Group noted that data on the absorption of plutonium cannot permit determination offi at better than one order of magnitude unless the chemical and physical state of the ingested material can be confidently established. The Task Group provides a three-level classification of compounds with respect to absorption of plutonium.

Chemical compound / I

Oxides 1O-5 Nitrates 10-b Others 10-J


The Task Group concluded that recent information on the behaviour of inhaled plutonium is not always consistent with the assumptions of the current ICRP Lung Model’ and noted that such discrepancies were being considered by the Task Group on Respiratory Tract Models. For the purpose of calculation of secondary limits the classification scheme empioyed in ZCRP Publication 30 for plutonium is adopted here. No plutonium compounds are assigned to


inhalation Class D, PuO, is assigned to inhalation Class Y, and all other commonly occurring compounds of plutonium are assigned to inhalation Class W.

Chemical Inhalation compound class f,

None Others Oxides

D -

w 10-S Y 10-5

(d) Distribution and retention

Plutonium absorbed into the blood stream is deposited principally in liver and skeleton. The relative deposition in these two organs was examined critically by the Task Group, who noted “ . . . variability of the deposition of plutonium, americium and curium between individuals is such that, for radiation protection purposes, the ICRP 30 model of equal distribution between skeleton and liver (45% in each) remains an adequate assumption”. Furthermore, the Task Group retained the currently-assumed deposition of 0.035% in testes and 0.011% in ovaries,‘l but commented that these values gave an unjustified impression of precision.

With regard to retention parameters, the Task Group considered “that both the 40-year half- time for plutonium in liver and the loo-year half-time for plutonium in the skeleton, recommended in ZCRP Publication 30 are too long”. The Task Group recommended values of 20 and 50 years for retention half-times in liver and skeleton, respectively.

In the calculations presented here, of the plutonium entering the transfer compartment, 0.45 is assumed to be translocated to bone and 0.45 to liver. The fraction translocated to the gonads is assumed to be 3.5 x low4 for males and 1.1 x 10m4 for females. Plutonium deposited in gonadal tissue is assumed to be permanently retained there, whereas plutonium deposited in the liver is assumed to be retained with a half-time of 20 years and plutonium deposited in the skeleton is assumed to be retained with a half-time of 50 years.


Plutonium deposits primarily on the endosteal surfaces of mineral bone and is slowly redistributed throughout its volume by processes such as resorption and burial.3 For this reason all isotopes of plutonium considered in this report are assumed, for the purpose of dosimetry, to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

LIMITS FOR INTAKES OF RADIONUCLIDES BY WORKERS 7

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of plutonium

Oral Class W Class Y

Radionuclide f,=lO_3 f,=lO_’ f, =10-j f,=lO_3 ft=lO_5

ALI 3 x IO8 DAC ALI 3 x 1O’O DAC ALI 9x IO4


DAC AL1 5x 10s DAC AL1 3x IO4


DAC AL1 3x lo4


DAC AL1 3 x IO4


DAC AL1 1 x 106


DAC AL1 3 x lo4


DAC AL1 6x IO8 DAC AL1 3 x lo4


DAC AL1 8 x 10’ DAC AL1 1 x IO’

(1 x IO’) LLI wall

DAC

3x 10s 3x 10s

3 x lo’* 3 x 10’0

9 x IO5 (1 x 106) Bone surf.

7x lo6

5 x 10s 5x lo*

3 x IO5 3 x lo6 (6 x 10’) (4 x 106) Bone surf. Bone surf.


3x 106 (4 x 106) Bone surf.



1 x IO’ (3 x IO’) Bone surf.

1 x 10s (2 x 108) Bone surf.

3x IO5 (6 x 10’) Bone surf.


6x10s 6x 10’

3 x 105 (5 x IO’) Bone surf.


8 x 10’ 8 x 10’

1 x IO’ (1 x IO’) LLI wall

1 x 10’ (1 x 10’) LLI wall

8x IO6 3 x 103 1 x IO” 5x 10:

700 (I x 103) Bone surf.

0.3 1 xl08 5x104

(::) Bone surf.

0.1

(Z) Bone surf.

0.1

(E) Bone surf.

0.1 1 x 104


5

(Z) Bone surf.

0.1 1 x 109 6x10’

(Z) Bone surf.

0.1 2 x 10s 7x104 9x 106

4x 103

7x IO6 3 x IO3 9 x lo’o 4x IO’ 2 x lo3

0.7 1 x IO8 5x IO4

700

0.3

E) Bone surf.

0.3

(2) Bone surf.

0.3 3x104


10

(E, Bone surf.

0.3 1 x109 6 x IO5

(El) Bone surf.

0.3 2x 10s 6x IO4 1 x 10’

4x103

REPORT OF COMMITTEE 2

METABOLIC DATA FOR AMERICIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for americium. Although americium has been distributed world-wide in measurable quantities as a result of fall-out from nuclear weapon tests, extensive data have not been obtained on the distribution of americium in man. Reliance must therefore be placed on animal data. Those data have been reviewed by a Task Group whose report3 provides the basis of the discussion presented here. Only information directly applicable to the calculation of secondary limits for americium are discussed; further information can be found in ICRP Publication 48.3

2. Metabolic Model

(a) Uptake to blood

Very limited information is available concerning the absorption of americium from the gastrointestinal tract. The data reviewed by the Task Group (see Table 4.8 of ICRP Publication 48) suggests thefi value lies in the range of 6 x 10d5 to 3 x 10e4. This range accords well with thef, value of 5 x 10m4 given in ZCRP Publication 3O.l However, the Task Group considered it prudent to assume that the absorption of americium may also be enhanced by dietary and other factors, similarly to that of plutonium; thus, the Task Group recommended that the samefi value as given for plutonium be used for americium, namely 10-3.


The Task Group reviewed incidents of accidental exposure to aerosols of insoluble forms of americium, noting that most of the material deposited in the pulmonary region cleared with a half-time of 10 to 20 days, but the clearance half-time of the remaining material varied between a few tens to almost 1000 days. Thus, the Task Group concluded that all americium compounds translocate to blood with half-times of several days, in broad agreement with the definition of a Class W compound.

Inhalation class f,

D W 10-J Y -


Although the limited human data suggests only a small deposition in the liver, data from experimental animals are generally in accord with the metabolic model used for plutonium. The Task Group concluded that it was reasonable to retain the assumption made in ZCRP Publication 30 that americium behaves like plutonium with regard to initial partition between liver and skeleton.

In this report it is assumed that of the americium entering the transfer compartment, 0.45 is translocated to bone and 0.45 to liver. The fraction of americium translocated to the gonads is assumed to be 3.5 x 10e4 for the testes and 1.1 x 10e4 for the ovaries. The remainder of


americium entering the transfer compartment is assumed to be excreted. Americium deposited in gonadal tissue is assumed to be permanently retained there, whereas americium deposited in the liver is assumed to be retained with a half-time of 20 years and americium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group.3

(d) Chelated compounds

Chelated forms of americium are not considered in this report. It is known that they are more biologically mobile than are other compounds of americium. l2


Americium mainly deposits upon periosteal and endosteal bone surfaces, although endosteal surfaces are usually more heavily labelled. The element is slowly redistributed throughout the volume of mineral bone by processes such as resorption and burial3 Thus, for the purposes of dosimetry, all isotopes of americium considered in this report are assumed to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.


Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of americium

Radionuclide

Oral

f, = lo-’

Inhalation

Class W

f,=lO_3

ALI DAC ALI

DAC AL1 DAC AL1 DAC ALI

DAC AL1

DAC AL1

DAC AL1

DAC ALI

DAC ALI

DAC AL1 DAC ALI

DAC ALI DAC

2 x 108

8 x 10’

3x 104 (5 x 104) Bone surf.

3 x 104 (5 x 104) Bone surf.

1 x 10s

3 x 104 (5 x 104) Bone surf.

2 x 109 (3 x 109) ST Wall

1 x 108

2x109 (2 x 109) ST Wall

1 x 10’9 4x10” 1 x10*

(2 x 108) Bone surf. 5 x lo4 5 x 10s 2 x lo5 1 x 10s 4x104

(E) Bone surf.

0.1

(E) Bone surf.

0.1 3 x lo6

(3 x 106) Bone surf. 1 x 10”

(Z) Bone surf.

0.1 2 x 10s

(3 x 106) Bone surf. lx lo4 7x106

(1 x 10’) Bone surf. 3 x 103 3 x 109 1 x106 1 x 109

3 x 106 4x109 2x 106


METABOLIC DATA FOR CURIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for curium. Reliance must therefore be placed on animal data, which has recently been reviewed by a Task Group and presented in ICRP Publication 48.3 Only information directly applicable to the calculation of secondary limits for curium is presented here; further information can be found in ICRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

Very limited information is available concerning the absorption of curium from the gastrointestinal tract. The data reviewed by the Task Group (see Table 4.8 of ZCRP Publication 48) suggest an f, value in the range 6 x 10e5 to 3 x 10m4. This is reasonably consistent with theji value of 5 x 10e4 used in ZCRP Publication 30.’ However, the Task Group considered it prudent to assume that the absorption might be enhanced, in a manner similar to that indicated for plutonium. Thus, the samefr value as recommended for plutonium, i.e. 10a3, was considered appropriate for curium.


As with americium, curium compounds, including the oxide, are more quickly lost from the lungs than are the corresponding compounds of plutonium. The limited data suggest that all compounds of curium should be assigned to inhalation Class W.

Inhalation class s,

D - W 10-j Y -


The behaviour of curium in experimental animals is similar to that of americium. Thus, the Task Group concluded that it was reasonable to retain the assumption made in ICRP Publication 30 that curium behaves like plutonium with regard to initial partition between liver and skeleton.

In this report it is assumed that of curium entering the transfer compartment, 0.45 is translocated to bone and 0.45 to liver. The fraction of curium translocated to the gonads is assumed to be 3.5 x 10m4 for the testes and 1.1 x 10d4 for the ovaries. The remainder ofcurium entering the transfer compartment is assumed to be excreted. Curium deposited in gonadal tissue is assumed to be permanently retained there, whereas curium deposited in the liver is assumed to be retained with a half-time of 20 years and curium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group for plutonium.

JAICFCP 19:4-B

12


REPORT OF COMMITTEE 2

Chelated forms of curium are not considered in this report. It is known that they are more biologically mobile than are other compounds of curium.‘*


The distribution of curium in the skeleton of the rat is indistinguishable from that of americium.” The element is deposited mainly on the endosteal surfaces of mineral bone and is only slowly redistributed throughout its volume by processes such as resorption and burial.3 Thus, for the purposes of dosimetry, all isotopes of curium considered in this report are assumed to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

LlMITS FOR INTAKES OF RADIONUCLIDES BY WORKERS

Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of curium

Inhalation

Radionuclide

Oral

j,=10-’

Class W

f,=lO_3

AL1 DAC ALI

DAC AL1

DAC ALI

DAC ALI

DAC AL1

DAC ALI

DAC AL1

DAC AL1

DAC AL1

DAC AL1

DAC AL1

DAC

6x 10s

2 x lo6 (3 x 106) Bone surf.

4 x 10’

1 x 106 (2 x 106) Bone surf.

4x104 (7 x 104) Bone surf.


3x104 (5 x 104) Bone surf.


3x104 (5 x 104) Bone surf.

7% lo3 (1 x 104) Bone surf.

2x109


4x 10’ 2x lo4 2 x 104


9 1 x 106


400 1 x 104


4

(Z, Bone surf.

0.1

(Z) Bone surf.

0.2

(Z) Bone surf.

0.09

(Z) Bone surf.

0.09

(Z) Bone surf.

0.1

(%) Bone surf.

0.03 6x10s

(1 x 109) Bone surf. 3 x 10s

r::, Bone surf. 5 x 10-s

13


METABOLIC DATA FOR BERKELIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for berkelium. Reliance must therefore be placed on animal data, which has recently been reviewed by a Task Group and presented in ICRP Publication 4a3; and on analogies to the metabolism of other transplutonic elements. Only information directly applicable to the calculation of secondary limits is presented here; further information can be found in ICRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

The fractional gastrointestinal absorption of intragastrically administered 24*BkC1 in the rat13 has been estimated as about 10e4. By analogy with americium, thefi value is taken to be lo- 3 for all compounds of berkelium.


There is a limited amount of data available on the inhalationI and intratracheal administration of berkelium,13 but these data are insufficient for the assignment of an inhalation class to berkelium. By analogy with americium, all compounds of berkelium are assigned to inhalation Class W.

Inhalation class f,

D - W 1o-3 Y -


Although not extensively studied, the actinides of higher atomic number, californium, berkelium and einsteinium, seem clearly to favour skeletal, as opposed to hepat’ic deposition. Basing its estimate entirely on comparative animal data, the ICRP Task Group recommends that an initial skeletal deposition of 65% and deposition of 25% in liver would be reasonable for these elements.

In this report it is assumed that of the berkelium entering the transfer compartment, 0.65 is translocated to bone and 0.25 to liver. The fraction of berkelium translocated to the gonads is assumed to be 3.5 x 10S4 for the testes and 1.1 x low4 for the ovaries. The remainder of berkelium entering the transfer compartment is assumed to be excreted. Berkelium deposited in gonadal tissues is assumed to be permanently retained there, whereas berkelium deposited in the liver is assumed to be retained with a half-time of 20 years and berkelium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group for plutonium.


Chelated forms of berkelium are not considered in this report. They may have greater biological mobility than other compounds of berkelium.



By analogy with other actinides, all isotopes of berkelium considered in this report are assumed, for the purposes of dosimetry, to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of berkelium

Inhalation

Radionuclide

Oral

f,=10_3

Class W

f,=10_3

ALI DAC AL1 DAC AL1

t49Bk DAC ALI

250Bk DAC AL1

DAC

8x 10’

1 x 10”


7x lo6 (2 x 10’) Bone surf.

3 x to*

5x 10’ 2 x lo4 1 x 10s 5 x lo4

(Z, Bone surf.

0.06 6x 10“


30 1 x 10’

(3 x 10’) Bone surf. 5x lo3

:


METABOLIC DATA FOR CALIFORNIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for californium. Reliance must therefore be placed on animal data, which has recently been reviewed by a Task Group and presented in ZCRP Publication 48.3 Only information directly applicable to the calculation of secondary limits for californium is presented here; further information can be found in ZCRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

Very limited information is available concerning the absorption of californium from the gastrointestinal tract. The data reviewed by the Task Group (see Table 4.8 of ZCRP Publication 48) suggest anfi value in the range 3 x 10m5 to 4 x 10m3. This range is consistent with the fi value of 5 x 10e4 used in ZCRP Publication 30.’ However, the Task Group considered it prudent to assume that the absorption might be enhanced in a manner similar to that indicated for plutonium. Thus, the samefi value as that recommended for plutonium, i.e. 10e3, seemed appropriate for californium.


Studies in rats have shown that the clearance of “‘Cf can be described by a three-exponential function with component half-times of 0.5 days (46%), 9.7 days (27%) and 440,days (1%). A slower clearance was observed in dogs; clearance half-times of the intermediate and long-term components were estimated to be 13 days (23%) and 820 days (20%). In an accidental inhalation exposure of a worker, l4 the clearance from the lungs showed half-times of 25 days (17%) and 1210 days (83%). The limited data for compounds of californium are in broad agreement with the definition of a Class W compound.

Inhalation class J-1

D -

W lo-’ Y -


Although not extensively studied, the actinides of higher atomic number, californium, berkelium and einsteinium, seem clearly to favour the skeleton, as opposed to the liver, as a site of deposition. Basing its conclusions entirely on comparative animal data, the Task Group indicated an initial skeletal deposition of 65% and a liver deposition of 25% would be reasonable for these elements.

In this report it is assumed that of the californium entering the transfer compartment, 0.65 is translocated to bone and 0.25 to liver. The fraction of californium translocated to the gonads is assumed to be 3.5 x 10T4 for the testes and 1.1 x 10m4 for the ovaries. The remainder of the californium entering the transfer compartment is assumed to be excreted. Californium deposited in gonadal tissue is assumed to be permanently retained there, whereas californium


deposited in the liver is assumed to be retained with a half-time of 20 years and californium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group as appropriate for plutonium.


Chelated forms of californium are not considered in this report. It is known that they are more biologically mobile than are other compounds of californium.r5


Californium deposits mainly upon the endosteal surfaces of mineral bone and is only slowly redistributed throughout its volume by processes such as resorption and burial.” For this reason all isotopes of californium considered in this report are assumed, for the purposes of dosimetry, to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of californium

Inhalation

Oral Class W Class Y

Radionuclide f,=10_3 f, = 10-j j,=10-3

244Cf AL1

249Cf

252Cf

2s3Cf

2J4Cf

DAC ALI DAC AL1

DAC ALI

DAC ALI

DAC AL1

DAC AL1

DAC AL1

DAC AL1 DAC

9 x 10s (1 x 109) ST Wall

1 x IO’

3 x los (6 x 10’) Bone surf.



2x 10’ (4 x 104) Bone surf.

9x lo* (2 x 105) Bone surf.

7x 106 (1 x 10’) Bone surf.

8x104

2 x 10’

9 x 103 4 x 105

100 2x 103 (4 x 10’) Bone surf.

1

$, Bone surf.

0.06

r::, Bone surf.

0.1

(:!, Bone surf.

0.06

(1 ~O?oo,, Bone surf.

0.3 lx lo4

30 30 800 600 0.3 0.3

2 x 10’

9 x IO3 3x lo5

100 4x 103

2

(Z, Bone surf.

0.2 1 x 103

0.4

(E, Bone surf.

0.2 1 x lo3

0.5 6x IO4


METABOLIC DATA FOR EINSTEINIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for einsteinium. Reliance must therefore be placed on animal data, which has recently been reviewed by a Task Group and presented in ICRP Publication 03; and analogies with other transplutonic elements. Only information directly applicable to the calculation of secondary limits for einsteinium is presented here; further information can be found in ZCRP Publication 48.

2. Metabolic Model

(a) Uptake to blood

Experiments on rats’ 3 indicate that einsteinium and americium are both absorbed from the gastrointestinal tract to a similar extent. Therefore, by analogy with americium, thefi value is taken here to be 10e3 for all compounds of einsteinium.


Retention data from inhalation studies on rats i6 have been described by a two-compartment exponential function with component half-times of 1 day (65%) and 10 days (35%). Thus, from these data, and by analogy with the more extensively studied element americium, all compounds of einsteinium are assigned to inhalation Class W.

Inhalation class .fi

D -

W 1o-3 Y


Although not extensively studied, the actinides of higher atomic number, californium, berkelium, and einsteinium, seem clearly to favour skeletal as opposed to hepatic deposition. Basing its estimates entirely on comparative animal data, the Task Group indicated that an initial skeletal deposition of 65% and a liver deposition of 25% would be reasonable for these elements.

In this report it is assumed that of einsteinium entering the transfer compartment, 0.65 is translocated to bone and 0.25 to liver. The fraction of einsteinium translocated to the gonads is assumed to be 3.5 x 10m4 for the testes and 1.1 x 10e4 for the ovaries. The remainder of einsteinium entering the transfer compartment is assumed to be excreted. Einsteinium deposited in gonadal tissues is assumed to be permanently retained there, whereas einsteinium deposited in the liver is assumed to be retained with a half-time of 20 years and einsteinium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group as appropriate for plutonium.


Chelated forms of einsteinium are not considered in this report. It is known that their biological behaviour differs considerably from that of other compounds of einsteinium.”



19

Autoradiographic studies l6 have shown that the distribution of einsteinium in rat bone resembles the distribution of plutonium. Thus, by analogy with the other actinides, all isotopes of einsteinium considered in this report are assumed, for the purposes of dosimetry, to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of einsteinium

Inhalation

Oral Class W

Radionuclide j-,=10-’ ,f, =10-”

lsoEs ALI

DAC “‘Es ALI

DAC 253E~ ALI

DAC 2S4rnJTs ALI

DAC -Es ALI

2x 109

3x loa

6x 106

1 x 10’ (1 x 10’) LLI Wall


2x 10’ (4 x IO’) Bone surf. 8 x 10’ 3 x 10’

(4 x 10’) Bone surf. 1 x lo4 5x104

20 4 x 105

200 3 x 103


1 DAC


METABOLIC DATA FOR FERMIUM

1. Metabolism

No data are given in ICRP Publication 23 lo for fermium. Reliance must therefore be placed on analogy with the other actinides.

2. Metabolic Model

(a) Uptake to blood

There are no data available on the uptake of fermium from the gastrointestinal tract. By analogy with americium, thefi value is taken here to be low3 for all compounds of fermium.


By analogy with americium and curium, all compounds of fermium are assigned to inhalation Class W.

Inhalation class fl

D w 10-’ Y


In ZCRP Publication 301 the metabolic model used for plutonium was used for other actinides. However, the information recently reviewed by the Task Group and presented in ICRP Publication 483 suggests that the actinides of higher atomic number seem clearly to favour skeletal, as opposed to hepatic deposition. Basing its estimates entirely on comparative animal data, the Task Group indicated that an initial skeletal deposition of 65% and a liver deposition of 25% would be reasonable for these elements.

In this report it is assumed that of fermium entering the transfer compartment, 0.65 is translocated to bone and 0.25 to liver. The fraction of fermium translocated to the gonads is assumed to be 3.5 x low4 for the testes and 1.1 x 10e4 for the ovaries. The remainder of fermium entering the transfer compartment is assumed to be excreted. Fermium deposited in gonadal tissue is assumed to be permanently retained there, whereas fermium deposited in the liver is assumed to be retained with a half-time of 20 years and fermium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group as appropriate for plutonium.


Chelated forms of fermium are not considered in this report. They may have greater biological mobility than other compounds of fermium.



21

By analogy with other actinides, and because no isotope of fermium has a radioactive half-life much greater than 100 days, all isotopes of the element considered in this report are assumed to be uniformly distributed over bone surfaces at all times following their deposition in the skeleton.

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of fermium

Inhalation

Radionuclide

Oral

f,=10_3

Class W

f,=lO_’

252Fm AL1 DAC

253Fm ALI DAC

zs“Fm ALI DAC

255Fm ALI DAC

“‘Frn ALI

DAC

2x 10’

4x 10’

1 x 10s

2 x 10’

7x 105 (1 x 106) Bone surf.

5 x lo5 200

4 x lo5 100

3x lo6 1 x lo3 8 x 10’

300 7x lo3


3


METABOLIC DATA FOR MENDELEVIUM

1. Metabolism

No data are given in ICRP Publication 231° for mendelevium. Reliance must therefore be placed on analogy with the other actinides.

2. Metabolic Model

(a) Uptake to blood

There are no data available on the uptake of mendelevium from the gastrointestinal tract. By analogy with americium, the fi value is taken here to be 10e3 for all compounds of mendelevium.


By analogy with americium and curium, all compounds of mendelevium are assigned to inhalation Class W.

Inhalation class fi

D - W 1o-3 Y -


In ZCRP Publication 30,’ the metabolic model used for plutonium was used for other actinides. However, the information recently reviewed by the Task Group and presented in ZCRP Publication 48j suggests that the actinides of higher atomic number seem to favour skeletal, as opposed to hepatic deposition. Basing its estimate entirely on comparative animal data, the Task Group indicates that an initial skeletal deposition of 65% and liver deposition of 25% would be reasonable for these elements.

In this report it is assumed that, of mendelevium entering the transfer compartment, 0.65 is translocated to bone and 0.25 to liver. The fraction of mendelevium translocated to the gonads is assumed to be 3.5 x 10m4 for the testes and 1.1 x 10m4 for the ovaries. The remainder of mendelevium entering the transfer compartment is assumed to be excreted. Mendelevium deposited in gonadal tissue is assumed to be permanently retained there, whereas mendelevium deposited in the liver is assumed to be retained with a half-time of 20 years and mendelevium deposited in the skeleton is assumed to be retained with a half-time of 50 years. These values correspond to the values recommended by the Task Group as appropriate for plutonium.


Chelated forms of mendelevium are not considered in this report. They may have greater biological mobility than other compounds of mendelevium.



23

By analogy with other actinides, and because no isotope of mendelevium has a radioactive half-life much greater than 100 days, all isotopes of the element considered in this report are assumed to be uniformly distributed over bone surfaces at ail times following their deposition in the skeleton.

Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of mendelevium

Inhalation

Oral Class W

f,=10-3 f,=lO_3

=‘Md

‘j8Md

ALI

DAC ALI

DAC

3x10s

9 x 105 (2 x 106) Bone surf.

3 x IO6 (3 x 106) Bone surf. 1 x lo3 9x lo3


4


SECONDARY LIMITS FOR ADDITIONAL RADIONUCLIDES

Secondary limits are presented here for a number of isotopes other than those of transplutonic elements. The radionuclides addressed here were not included in ICRP Publication 30 because the nuclear decay data were judged to be insufficient at that time. However, by the time the Task Group on dose calculations began to complete ICRP Publication 38, adequate nuclear decay data were available and these nuclides were included in that publication. These data, in conjunction with the metabolic information for the appropriate element as presented in ZCRP Publication 30, were used to calculate the secondary limits. In addition to the nuclides tabulated below, secondary limits were presented for the first time for 246Pu and “‘Cm in the earlier section of this report. For information on the metabolic model and the assignment of chemical compounds to clearance classes, ICRP Publication 30 should be consulted.

Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for s2Sr

f, =0.3

Inhalation

Oral Class D Class Y

fi =O.Ol j-,=0.3 f, =O.Ol

AL1

DAC

1 x 10’ lx106 (9 x 106) LLI Wall

1 x 10’ 3 x lo6

6~10~ 1 x lo3

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for 95mTc

Oral Class D

j-,=0.8 f, =0.8

Class W

f, =0.8

AL1 1 x 10s 2x10s I x 10’ DAC 8x lo4 3 x lo4

Annual limits on intake, AL1 (Bq), and derived air concentrations, DAC (Bq/m”) (40 h/wk) for 95Tc

Inhalation

AL1 DAC

Oral

f, =0.8

4x 10s

Class D

f,=O.8

8 x 10” 3 x lo5

Class W

fi =0.8

1 x 10s 3 x lo5


Annual limits on intake, ALI (Bq), and derived air concentrations, DAC (Bq/m3) (40 h/wk) for isotopes of “%b

Inhalation

Oral Class D Class W

f, =O.l f* = 0.01 j, =O.l f, =O.Ol

25

AL1

DAC

3x109 3 x 109 (3 x 109) (3 x 109) ST Wall ST Wall

1 x 1O’O 1 x 10’0

4 x lo6 5 x 106


REFERENCES 1. ICRP Publication 30 (1979). Part 1, Limits for intakes of radionuclides by workers. Annals ofthe ICRP 2 No. 3/4,

Pergamon Press, Oxford. 2. ICRP Publication 19 (1972). The metabolism of compounds of plutonium and other actinides, Pergamon Press,

Oxford. 3. ICRP Publication 48 (1986). The metabolism of plutonium and related elements. Annals ofthe ICRP 16 No. 2/3,

Pergamon Press, Oxford. 4. ICRP Publication 38 (1983). Radionuclide transformations. Energy and intensity ofemissions. Annals ofthe ICRP

11-13. Pergamon Press, Oxford. 5. Ballou, J.E.,Bair, W. J.,Case, A.C.andThompson,R. C. (1962).Studies withneptuniumin therat.Health Phys.8,

685688. 6. Sullivan, M. F. (1980). Absorption of actinide elements from the gastrointestinal tract of rats, guinea pigs and dogs.

Health Phys. 38, 158-171. 7. Sullivan, M. F., Miller, B. M. and Ryan, J. L. (1983). The effect of mass on the gastrointestinal absorption of

plutonium and neptunium. Radiat. Res. 94, 199-209. 8. Metivier, H., Masse, R. and Lafuma, J. (1983). Effect of mass on the intestinal absorption of neptunium from the

baboon and rat. Radioprotection 8, 13-17. 9. Nenot, J. C., Masse, R., Morin, M. and Lafuma, J. (1972). An experimental comparative study of the behaviour of

23’Np, 23sAm and ‘%rn in bone. Health Phys. 22, 657-666. 10. ICRP Publication 23 (1975). Report of the Task Group on Reference Man. Pergamon Press, Oxford. 11. Richmond, C. R. and Thomas, R. L. (1975). Plutonium and other actinide elements in gonadal tissue of man and

animals. Health Phys. 29, 241-250. 12. Durbin, P. W. (1973). Metabolism and biological effects of the transplutonium elements. In: Uranium, Plutonium,

Transplutonium Elements, pp. 739-896. (Eds. Hodge, H. C., Stannard, J. N. and Hursh, J. B.). Springer Verlag, Berlin.

13. Hungate, F. P., Ballou, J. E., Mahlum, D. D., Kashima, M., Smith, V. H., Sanders, C. L., Baxter, D. W., Sikov, M. R. and Thompson, R. C. (1972). Preliminary data on zs3Es and 24gBk metabolism in rats. Health Phvs. 22. 653-656. -

14. Rundo, J. and Seldet, J. (1973). Retention and elimination of berkelium-249 and californium-249 following acute accidental inhalation. In: Proc. 3rd Znd. Cong. Radiat. Prot. Assoc. CONF 730901, Vol. 2, pp. 731-735 (Ed. W. S. Snyder).

15. Parker, fi. G., Low-Beer, A. de G. and Isaac, E. L. (1962). Comparison of retention and organ distribution of 241Am and 2s2Cf in mice: The effect of in-viuo DTPA chelation. Health Phys. 8, 679-684.

16. Ballou, J. E., Dagle, G. E., Gies, R. A. and Smith, L. G. (1979). Late effects ofinhaled 253Es(N03)3 in rats. Health Phys. 37,301-310.

17. Hayes, R. L., Rafter, J. J., Washburn, L. C. and Byrd, B. L. (1979). Affinity of ZS3Einsteinium for tumour tissue. Nature (New Biology) 246,23-25.

18. Watson, S. B. and Ford, M. R. (1980). A user’s manual to the ICRP code--A series of computer programs to perform dosimetric calculations for the ICRP Committee 2 Report, ORNL/TM-6980, Oak Ridge National Laboratory, Oak Ridge, TN.

APPENDIX A

SUPPLEMENTARY DOSIMETRIC INFORMATION

INTRODUCTION

In this Appendix dosimetric data relevant to the calculation of secondary limits for radionuclides considered in this report are tabulated. The content and format of the information parallels the presentation given in the Supplements to ZCRP Publication 30,’ and the tables were produced from the computer code’* used to calculate the secondary limits presented in ZCRP Publication 30. The supplementary information provides numerical data supporting the calculation of Annual Limit on Intake (ALI) and the Derived Air Concentration (DAC). For each radionuclide the following information is of interest:

1. number of nuclear transformations; 2. specific effective energy; 3. committed dose equivalent and committed effective dose equivalent per unit intake, the

ALI, and DAC.

To limit the size of the appendix, only data which differs from that contained in the Supplements to ICRP Publication 30 are presented. The reader wishing to investigate the calculations of the secondary limits presented here will need to consult the Supplements. The reader is also encouraged to consult the Supplement to Part 1 for further discussion of the quantities contained in the tabulations.

Number of Nuclear Transformations

Values are given for the number of transformations, U, occurring in source organs during the 50 years following the ingestion or inhalation of a unit activity of the specified isotope. Where appropriate, values of U are also given for radioactive daughters formed from transformations of the specified parent radionuclide taken into the body. Nuclear transformation data are presented only for those source organs contributing greater than 1% to the committed dose equivalent in the target organs. Revision of the metabolic model affects not only the numerical values, but also the selection of data for presentation.

Specific Effective Energy

Values of Specific Effective Energy (SEE) in selected target organs from nuclear transformations arising in selected source organs are given for the specified radionuclide and, where appropriate, for any radioactive daughters produced from transformations of the parent radionuclide taken into the body. Target organs are selected for inclusion in the table by the 10% rule, i.e. organs are excluded if their weighted committed dose equivalent is less than 10% of the maximum weighted committed dose. Source organs are retained in the tabulation only if they contribute greater than 1% to the committed dose equivalent of the target organs retained in the tabulation. Since the revised metabolic model alters the list of organs surviving the 1% and 10% values, in some instances it was necessary to include revised tabulations of the SEE values (for example, see 234Pu) Note that SEE data are tabulated here only if the data given in . the Supplements to Publication 30 are not sufficient to confirm the calculations presented here.

JAICRP 19:4-C 27


Committed Dose Equivalent per Unit Intake

The committed dose equivalent per unit intake for target organ T is computed as:

H 50,T = 1.6 X lo-” C C Us,jSEE(TtS)j, (1) s j

where the sum extends over all source organs S and all members j of the decay chain, when appropriate. Values of the committed dose equivalent are presented for each organ or tissue surviving application of the 10% rule to the intake of the specified radionuclide. The weighted committed dose equivalents, wTHSO,T, were tabulated in the Supplement to Part 2; however, since these values are readily obtained from the above definition, they are not tabulated here.

The committed effective dose equivalent per unit intake has been tabulated as the final entry of the committed dose equivalent tables.

Annual Limit on Intake and Derived Air Concentration

For completeness, the AL1 and DAC are tabulated for each radionuclide in this appendix. The numerical data are the same as those presented in the main text of this report.

NEPTUNIUM

232 N 93 P

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Np-232

SOURCES TARGETS ST SI ULI

GONADS CONTENT CONTENT CONTENT CORT BONE TRAB BONE

GONADS 1.3E-02 4.1E-06 4.OE-05 3.91-05 3.83-06 3.8E-06 R MARROW 1.4E-05 4.51-06 l.lE-05 9.4E-06 1.4E-05 S.OE-05 BONE SURF 4.1E-06 2.63-06 3.51-06 3.1E-06 1.5E-04 l.SE-04 ST WALL 3.2E-06 4.33-04 1.4E-05 l.SE-05 2.3E-06 2.3E-06 SI WALL 4.6E-05 l.OE-05 2.6E-04 6.5E-05 3.3E-06 3.3E-06 ULI WALL 4.43-05 1.3E-05 9.6E-05 4.3E-04 3.OE-06 3.OE-06 PANCREAS 3.OE-06 6.9E-05 8.21-06 8.43-06 3.91-06 3.9E-06

SPECIFIC EFFECTItiE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF U-232



GONADS 9.8E 00 S.SE-10 6.3E-08 E.OE-08 1.2E-09 1.2E-09 R MARROW l.lE-08 2.3E-09 1.3E-08 9.1E-09 1.8E-07 3.5E-02 BONE SURF 2.8E-09 l.SE-09 3.4E-09 2.41-09 2.2E-01 2.2E-01 ST WALL 7.3E-10 2.23-03 l.OE-08 1.4E-08 9.4E-10 9.4E-10 SI WALL 7.1E-08 3.9E-09 1.3E-03 1.4E-07 1.3E-09 1.3E-09 ULI WALL l.SE-07 8.4E-09 8.7E-07 2.4E-03 1.4E-09 1.4E-09 PANCREAS 3.9E-10 7.23-08 2.1E-09 2.23-09 2.OE-09 2.OE-09

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Th-228



GONADS l.OE 01 3.83-09 1.2E-07 1.3E-07 5.63-09 5.63-09 R MARROW 4.9E-08 1.3E-08 4.OE-08 3.3E-08 l.SE-07 3.6E-02 BONE SURF 1.3E-08 7.5E-09 l.lE-08 9.83-09 2.3E-01 2.3E-01 ST WALL 5.83-09 2.2E-03 3.23-08 3.5E-08 4.3E-09 4.33-09 SI WALL 1.3E-07 2.1E-08 1.4E-03 2.OE-07 5.9E-09 5.9E-09 ULI WALL 1.7E-07 3.OE-08 7.73-07 2.53-03 5.6E-09 5.615-09 PANCREAS 3.4E-09 1.7E-07 l.SE-08 1.7E-08 7.3E-09 7.31-09

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Ra-224



GONADS l.lE 01 1.6E-08 3.6E-07 l.lE-07 2.63-08 2.61-08 R MARROW 1.4E-07 4.53-08 l.lE-07 9.81-08 1.2E-07 3.8E-02 BONE SURF 4.1E-08 2.53-08 3.5E-08 3.1E-08 2.4E-01 2.4E-01 ST WALL 2.8E-08 2.3E-03 1.3E-07 1.3E-07 2.OE-08 ~.oE-08 SI WALL 4.23-07 9.21-08 1.4E-03 5.83-07 2.73-08 2.73-08 ULI WALL 4.OE-07 1.2E-07 8.4E-07 2.53-03 2.61-08 2.61-08 PANCREAS 1.8E-08 6.3E-07 7.2E-08 8.3E-08 3.71-08 3.73-08

29

30 REPORT OFCOMMI-ITEEZ

SPECIFIC EFFECTIVE ENERGY (HeV PER GRAM PER TRANSFORMATION) OF Rn-220



GONADS 1.2E 01 7.9E-10 1.2E-08 1.6E-08 1.4E-09 1.4E-09 R MARROW 4.1E-09 1.4E-09 3.3E-09 2.83-09 4.1E-09 4.2E-02 BONE SURF 1.2E-09 8.OE-10 l.OE-09 9.5E-10 2.6E-01 2.6E-01 ST WALL l.lE-09 2.5E-03 4.53-09 4.8E-09 7.7E-10 7.7E-10 SI WALL 1.6E-08 3.53-09 1.6E-03 2,1E-08 l.lE-09 l.lE-09 ULI WALL l.SE-08 4.38-09 3.OE-08 2.8E-03 9.4E-10 9.4E-10 PANCREAS 7.8E-10 2.3E-08 2.71-09 2.4E-09 1.2E-09 1.2E-09

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF PO-216



GONADS 1.3E 01 6.4E-11 S.SE-10 5.3E-10 5.7E-11 5.7E-11 R MARROW 1.7E-10 5.7E-11 1.4E-10 l.ZE-10 l.?E-10 4.51-02 BONE SURF S.lE-11 3.3E-11 4.4E-11 3.9E-11 2.8E-01 2.8E-01 ST WALL 4.5E-11 2.7E-03 1.9E-10 2.OE-10 3.2E-11 3.2E-11 SI WALL 6.4E-10 1.4E-10 1.7E-03 8.9E-10 4.7E-11 4.7E-11 ULI WALL 6.OE-10 1.7E-10 1.3E-09 3.OE-03 4.3E-11 4.3E-11 PANCREAS 4.5E-11 9.4E-10 1.2E-10 l.lE-10 S.SE-11 S.SE-11

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Pb-212



GONADS 1.6E-02 2.53-07 5.83-06 6.4E-06 4.OE-07 4.OE-07 R MARROW 2.6E-06 7.5E-07 2.OE-06 1.7E-06 2.23-06 6.1E-05 BONE SURF 7.33-07 4.3E-07 6.OE-07 5.43-07 3.3E-04 3.33-04 ST WALL 4.21-07 3.8E-04 2.OE-06 2.OE-06 3.OE-07 3.OE-07 SI WALL 6.61-06 1.4E-06 2.4E-04 9.3E-06 4.1E-07 4.1E-07 ULI WALL 6.23-06 1.9E-06 1.4E-05 4.2E-04 3.83-07 3.81-07 PANCREAS 2.53-07 l.OE-05 l.lE-06 1.2E-06 5.3E-07 5.33-07

SPECIFIC EFFECTIVE ENERGY (MeV

TARGETS

GONADS R MARROW BONE SURF ST WALL SI WALL ULI WALL PANCREAS

GONADS

4.1E 00 1.8E-06 5.43-07 5.3E-07 6.83-06 6.43-06 4.1E-07

ST CONTENT

6.1E-07 6.OE-07 3.61-07 1.8E-03 l.SE-06 2.OE-06 l.OE-05

PER GRAM PER TRANSFORMATION) OF Bi-212

SOURCES SI ULI

CONTENT CONTENT CORT BONE TRAB BONE

5.4E-06 5.51-06 5.9E-07 5.9E-07 l.SE-06 1.2E-06 1.9E-06 l.SE-02 4.73-07 4.23-07 9.1E-02 9.1E-02 2.1E-06 2.1E-06 3.5E-07 3.51-07 1.2E-03 9.43-06 4.9E-07 4.9E-07 1.4E-05 2.1E-03 4.5E-07 4.53-07 1.2E-06 1.2E-06 6.2E-07 6.23-07





31

GONADS 1.6E 01 0.0 0.0 0.0 0.0 0.0 R MARROW 0.0 0.0 0.0 0.0 0.0 5.9E-02 BONE SURF 0.0 0.0 0.0 0.0 3.7E-01 3.7E-01 ST WALL 0.0 3.53-03 0.0 0.0 0.0 0.0 SI WALL 0.0 0.0 2.2E-03 0.0 0.0 0.0 ULI WALL 0.0 0.0 0.0 3.9E-03 0.0 0.0 PANCREAS 0.0 0.0 0.0 0.0 0.0 0.0

NUMBER OF NUCLEAR TRANSFORMATIONS OVER 50 YEARS IN SOURCE ORGANS OR TISSUES PER UNIT INTAKE OF ACTIVITY

(TRANSFORHATIONS/Bq) OF NQ-232

ORGAN ORAL

fl-10-3

GONADS

ST CONTENT

SI CONTENT

LJLI CONTENT

N~-232 4.2E-06 U-232 5.31-05 Th-228 5.1E-05 Ra-224 5.1E-05 Rn-220 5.1E-05 PO-216 5.1E-05 a-212 5.1E-05 Bi-212 5.1E-05 PO-212 3.2E-05 N~-232 9.4E 02 U-232 l.OE-03 Th-228 4.3E-08 Ra-224 3.3E-10 Rn-220 3.3E-10 Po-216 3.3E-10 Pb-212 2.OE-11 81-212 8.1E-12 Po-212 5.23-12 NQ-232 3.1E 02 U-232 5.5E-03 Th-228 l.lE-06 Ra-22L 3.43-08 Rn-220 3.4E-08 Po-216 3.413-08 Pb-212 7.1E-09 Bi-212 5.23-09 Po-212 3.31-09 Np-232 2.6E 01 U-232 1.8E-02 Th-228 1.3E-05 Ra-224 1.3E-06 Rn-220 1.3E-06 PO-216 1.3E-06 Pb-212 6.21-07 Bi-212 5.63-07 Po-212 3.6E-07

INHALATION CLASS w

fl-10-3

7.OE-03 6.4E-03 6.2E-03 6.2E-03 6.2E-03 6.2E-03 6.2E-03 6.2E-03 3.9E-03 8.2~ 00 7.1E-04 9.81-06 8.8E-06 8.8E-06 8.8E-06 8.7E-06 8.7E-06 5.6E-06 2.7E 00 2.8E-03 4.OE-05 3.5E-05 3.51-05 3.5E-05 3.5E-05 3.51-05 2.2E-05 2.3E-01 9.3E-03 1.3E-04 1.2E-04 1.2E-04 1.2E-04 l.lE-04 l.lE-04 7.31-05

32 REPORT OF COMMIlTEE 2

NUCLEAR TRANSFORMATION DATA FOR Np-232, CONT'D

ORGAN INHALATION

ORAL CLASS W

fl-10-3 fl-10-3

CORT BONE Np-232 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 81-212 PO-212

TRAB BONE Np-232 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

1.9E-03 1.3E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 8.OE-02 7.73-04 1.3E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 1.2E-01 8.OE-02

3.1E 00 1.6E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 9.8E 00

1.3E 00 1.6E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 1.5E 01 9.8E 00

COMMITTED DOSE EQUIVALENT IN TARGET ORGANS OR TISSUES PER INTAKE OF UNIT ACTIVITY (Sv/Bq) OF Np-232

ORAL

fl-10-3

GONADS 3.33-12

R MARROW 6.3E-12

BONE SURF 6.3E-11 ST WALL 6.6E-11 SI WALL l.SE-11 ULI WALL 8.43-12 REMAINDER l.lE-11 UT-.06 EFFECTIVE 9.41-12

INHALATION cuss w

fl-10‘3

R MARROW 6.1E-10 (25,33,42) BONE SURF 7.63-09 (25,33,42) EFFECTIVE 3.OE-10

ANNUAL LIMITS ON INTAKE, AL1 (Bq), AND DERIVED AIR CONCENTRATIONS, DAC (Bq/m3), (40 Hr/Wk) FOR Np-232

ALI DAC INHALATION INHALATION

ORAL CLASS w CLASS w

fl-10-3 fl-10-3 fl-10-3

5.E 09 7.E 07 3.E 04 (2.E 08) BONE SURF


233 N 93 P


TARGETS LUNGS

GONADS 2.71-08 LUNGS 2.3E-05 BONE SURF 5.5E-07 ST WALL 6.2E-07 SI WALL 6.OE-08 ULI WALL 7.2E-08 PANCREAS 8.73-07

ST CONTENT

1,8E-07 5.9E-07 3.33-07 5.OE-05 9.OE-07 1.2E-06 6.26-06

SOURCES SI ULI

CONTENT CONTENT

3.73-06 4.1E-06 6.81-08 8.4E-08 4.61-07 4.1E-07 1.2E-06 1.3E-06 3.2E-05 6.OE-06 l.OE-05 5.OE-05 6.81-07 7.4E-07

LLI CONTENT

6.OE-06 2.43-08 6.1E-07 5.93-07 3.33-06 1.5E-06 2.5E-07

____ BONE _____ CORT TRAB

2.43-07 2.43-07 3.1E-07 3.1E-07 2.91-05 2.91-05 1.8E-07 1.8E-07 2.43-07 2.43-07 2.2E-07 2.2E-07 2.5E-07 2.51-07

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAH PER TRANSFORMATION) OF U-233

SOURCES TARGETS ST SI ULI LLI ____ BONE _____

LUNGS CONTENT CONTENT CONTENT CONTENT CORT TRAB

GONADS 1.9E-10 l.lE-09 5.1E-08 6.1E-08 1.3E-07 1.9E-09 1.9E-09 LUNGS 9.8E-02 4.8E-09 4.4E-10 5.2E-10 1.5E-10 2.53-09 2.5E-09 BONE SURF 5.OE-09 2.33-09 3.93-09 3.23-09 6.4E-09 2.OE-01 2.OE-01 ST WALL 5.53-09 1.9E-03 l.lE-08 1.4E-08 4.X-09 1.4E-09 1.4E-09 SI WALL 3.7E-10 6.33-09 l.ZE-03 l.OE-07 5.5E-08 1.9E-09 l.YE-09 ULI WALL 4.5E-10 l.OE-08 5.OE-07 2.21-03 3.3E-08 1.8E-09 1.8E-09 PANCREAS 5.93-09 6.9E-08 4.3E-09 4.73-09 1.5E-09 2.33-09 2.3E-09


SOURCES TARGETS ST SI ULI LLI -_-_ BONE _-___


GONADS 2.83-08 1.7E-07 4.OE-06 4.23-06 6.93-06 2.41-07 2.4E-07 LUNGS 9.93-02 6.OE-07 6.53-08 7.9E-08 2.3E-08 3.23-07 3.2E-07 BONE SURF 5.8E-07 3.3E-07 4.7B-07 4.2E-07 6.4E-07 2.OE-01 2.OE-01 ST WALL 6.43-07 2.28-03 1.3E-06 1.3E-06 5.9E-07 1.8E-07 1.8E-07 SI WALL 5.6E-08 Y.OE-07 1.4E-03 6.53-06 3.6E-06 2.4E-07 2.43-07 ULI WALL 6.7E-08 1.2E-06 1.3E-05 2.56-03 1.7E-06 2.2E-07 2.2E-07 PANCREAS 8.8E-07 6.6E-06 6.6E-07 7.43-07 2.31-07 2.7E-07 2.71-07

34 REPORT OF COMMYITEE 2


SOURCES TARGETS ST SI ULI LLI -___ BONB _____


GONADS 1.4E-09 1.5E-08 7.93-07 8.2E-07 1.8E-06 4.1E-08 4.1E-08 LUNGS l.lE-04 l.OE-07 3.OE-09 4.OE-09 6.9E-10 4.5&-08 4.58-08 BONE SURF 1.3E-07 S.OE-08 8.OE-08 7.23-08 1.6E-07 2.23-04 2.2E-04 ST WALL l.OE-07 2.213-04 1.9E-07 2.6E-07 7.6E-08 1.7E-08 1.7E-08 SI WALL 2.41-09 l.lE-07 1.4E-04 1.6E-06 8.33-07 2.83-08 2.8E-08 ULI WALL 3.4E-09 2.1E-07 3.33-06 2.5E-04 3.53-07 2.43-08 2.4E-08 PANCREAS 1.3E-07 1.5E-06 6.OE-08 6.3E-08 1.3E-08 2.8&-08 2.83-08

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF AC-225

SOURCES TARGETS ST SI ULI LLI -___ BONE __-__


GONADS 5.71-09 3.3E-08 7.5E-07 8.1E-07 1.3E-06 4.7E-08 4.715-08 LUNGS 1.2E-01 l.lE-07 1.3E-08 1.6E-08 4.63-09 6.1E-08 6.1E-08 BONE SURF l.OE-07 6.1E-08 8.7E-08 7.7E-08 1.2E-07 2.4E-01 2.4E-01 ST WALL 1.2E-07 2.43-03 2.4E-07 2.51-07 l.lE-07 3.41-08 3.41-08 SI WALL l.lE-08 1.7E-07 1.5E-03 1.2E-06 6.7E-07 4.73-08 4.7E-08 ULI WALL 1.4E-08 2.3E-07 2.53-06 2.61-03 3.2E-07 4.33-08 4.3E-08 PANCREAS 1.7E-07 1.2E-06 1.3E-07 1.4E-07 4.51-08 5.3E-08 5.33-08

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Fr-221



GONADS 1.3E-08 4.9E-08 1.2E-06 1.3E-06 2.2E-06 8.OE-08 8.OE-08 LUNGS 1.3E-01 1.9E-07 2.81-08 3.1E-08 9.63-09 l.lE-07 l.lE-07 BONE SURF 1.4E-07 8.4E-08 1.2E-07 l.OE-07 1.5E-07 2.6E-01 2.6E-01 ST WALL 2.1E-07 2.53-03 4.1E-07 4.2E-07 2.OE-07 6.43-08 6.4E-08 SI WALL 2.2E-08 2.9E-07 1.6E-03 1.9E-06 l.OE-06 8.5E-08 8.5E-08 ULI WALL 2.7E-08 3.9E-07 2.7E-06 2.83-03 4.83-07 8.2E-08 8.2E-08 PANCREAS 2.83-07 2.OE-06 2.3E-07 2.6E-07 7.8E-08 1.2E-07 1.2E-07

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF At-217



GONADS 1.6E-10 6.8E-10 l.OE-08 1.3E-08 l.EE-08 l.lE-09 l.lE-09 LUNGS 1.4E-01 2.OE-09 3.4E-10 3.6E-10 l.lE-10 l.lE-09 l.lE-09 BONE SURF 1.2E-09 6.9E-10 9.2E-10 8.4E-10 1.2E-09 2.9E-01 2.9E-01 ST WALL 2.OE-09 2.8E-03 3.71-09 3.91-09 1.9E-09 6.2E-10 6.2E-10 SI WALL 2.9E-10 2.83-09 1.8E-03 1.8E-08 9.7E-09 8.6E-10 8.6E-10 ULI WALL 3.8E-10 3.6E-09 2.5E-08 3.1E-03 4.5E-09 7.7E-10 7.7E-10 PANCREAS 2.9E-09 1.9E-08 2.2E-09 2.1E-09 7.9E-10 l.OE-09 l.OE-09

LIMITSFORlNTAKESOFRADlONUCLiDESBYWORKERS 35


(TRANSFORMATIONS/Bq) OF Np-233

INHAIATION ORGAN ORAL CLASS w

fl-10-3 fl-10-3

LUNGS

ST CONTENT

SI CONTENT

ULI CONTENT

LLI CONTENT

CORT BONE

TRAB BONE

Np-233 U-233 Th-229 Re-225 AC-225 Fr-221 At-217 Np-233 1.7E 03 U-233 8.33-07 Th-229 9.OE-15 Ra-225 1.7E-17 AC-225 5.OE-20 Fr-221 4.51-20 At-217 4.5E-20 Np-233 1.2E 03 U-233 5.7E-06 Th-229 2.13E-13 Ra-225 2.28-15 AC-225 2.6E-17 Fr-221 2.58-17 At-217 2.58-17 Np-233 2.4E 02 U-233 Z.OE-05 Th-229 3.7E-12 Re-225 9.9E-14 AC-225 3.7E-15 Fr-221 3.6&-15 At-217 3.61-15 Np-233 1.6E 01 U-233 3.7&-05 Th-229 1.7E-11 Ra-225 9.1E-13 A-z-225 6.6E-14 Fr-221 6.53-14 At-217 6.53-14 Np-233 2.2E-02 U-233 1.8E-04 Th-229 3.9E-07 Ra-225 3.9E-07 AC-225 3.93-07 Fr-221 3.91-07 At-217 3.93-07 ND-233 1.2E-02 U:233 1.8E-04 Th-229 3.9E-07 Ra-225 3.93-07 AC-225 3.9E-07 Fr-221 3.9E-07 At-217 3.9E-07

9.3E 02 4.5E-04 8.8E-09 6.9E-09 5.8E-09 5.8E-09 5.8E-09 3.5E 01 7.81-07 3.1E-12 2.3E-12 1.9E-12 1.9E-12 1.9E-12 2.5E 01 3.2E-06 1.2E-11 9.OE-12 7.51-12 ?.5E-12 7.53-12 5.1E 00 l.OE-05 4.2E-11 3.OE-11 2.5E-11 2.5E-11 2.5E-11 3.3E-01 1.9E-05 8.2E-11 5.6E-11 4.6E-11 4.6E-11 4.6E-11 1.4E 01 2.2E-02 4.73-05 4.71-05 4.7E-05 4.7E-05 4.73-05 7.4E 00 2.2E-02 4.7E-05 4.7E-05 4.7E-05 4.78-05 4.71-05



ORAL

fl-10-3

9.43-13

ST WALL 1.4E-11

SI WALL 6.51-12 ULI WALL 4.3E-12 REMAINDER l.EE-12 WT-.06 EFFECTIVE 1.8E-12

LUNGS 3.4E-12

( 0916984) BONE SURF 1.6E-12 (25,33,42) EFFECTIVE 4.5E-13

ANNUAL LIMITS ON INTAKE, AL1 CONCENTRATIONS, DAC (Bq/m3),

(Bq), AND DERIVED AIR (40 Hr/Wk) FOR Np-233

AL1 INHALATION

ORAL CLASS w

fl-10-3 fl-10-3

INHALATION CLASS w

fl-10-3

DAC INHALATION CLASS w

fl-10-3

3.E 10 l.E 11 5.E 07

SPECIFIC EFFECTIVE ENERGY (HeV PER GRAM PER TRANSFORMATION) OF Np-234

SOURCES TARGETS SI ULI LLI ____ BONE ____ TOTAL

GONADS LUNGS CONTENT CONTENT CONTENT LIVER CORT TRAB BODY

GONADS 8.OE-03 6.2E-07 2.8E-05 2.5E-05 5.7E-05 3.3E-06 3.1E-06 3.1E-06 7.8E-06 BREAST 6.81-06 4.6E-06 5.3E-06 5.1E-06 5.81-06 3.91-06 3.93-06 3.9E-06 5.8E-06 R HARROW l.OE-05 4.4E-06 8.6E-06 7.41-06 l.lE-05 3.8E-06 l.lE-05 3.OE-05 6.5E-06 LUNGS 5.81-07 l.lE-04 1.2E-06 1.5E-06 5.9E-07 8.6E-06 3.41-06 3.43-06 5.5E-06 SI WALL 3.8E-05 l.lE-06 1.8E-04 5.21-05 3.OE-05 5.6&-06 2.73-06 2.73-06 7.5~-06 ULI WALL 3.71-05 1.5E-06 7.9E-05 2.7E-04 1,5E-05 7.6B-06 2.6E-06 2.63-06 7.OE-06 LLI WALL 4.63-05 2.53-07 2.4E-05 l.OE-05 3.8E-04 1.3E-06 3.41-06 3.4E-06 7.6E-06

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF U-234

SOURCES TARGETS SI ULI LLI ---- BONE _-__ TOTAL

GONADS LUNGS CONTENT CONTENT CONTENT LIVER CORT TP.AB BODY

GONADS 8.8E 00 3.4E-11 4.8E-08 6.2E-08 1.4E-07 1.9E-10 7.5E-10 7.5E-10 1.4E-03 BREAST 1.6E-08 1.2E-08 4.81-09 2.9E-09 3.93-09 4.OE-09 2.1E-09 2.1E-09 1.4E-03 R MARROW 6.61-09 3.71-09 9.OE-09 6.OE-09 1.9E-08 2.31-09 1.5E-07 3.2E-02 1.4E-03 LUNGS 1.8E-11 9.7E-02 7.7E-11 9.8E-11 2.5E-11 8.4E-09 1.2E-09 1.2E-09 1.4E-03 SI WALL 5.4E-08 6.5E-11 1.2E-03 l.lE-07 5.8E-08 1.3E-09 8.2E-10 8.2E-10 1.4E-03 ULI WALL 1.2E-07 8.2E-11 7.21-07 2.2E-03 3.9E-08 2.3E-09 9.3E-10 9.3E-10 1.4E-03 LLI WALL 1.5E-07 1.8E-11 8.9E-08 l.OE-08 3.6E-03 7.3E-11 2.3E-09 2.31-09 1.4E-03

LIMlTSFORINTAKESOFRADIONUCLlDESBYWORKERS

NUMBER OF NUCLEAR TRANSFORHATIONS OVER 50 YEARS IN SOURCE ORGANS OR TISSUES PER UNIT INTAKE OF ACTIVITY

(TRANSFORNATIONS/Bq) OF Np-234

INHALATION ORGAN ORAL CLASS W

fl-lo-' fl-10-J

37

GONADS

LUNGS

SI CONTENT

ULI CONTENT

LLI CONTENT

LIVER

CORT BONE

TRAB BONE

OTHER TISSUE (63154g)

Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234 Np-234 U-234

6.OE-02 8.5E-06

1.4E 04 2.3E-05 4.2E 04 2.5E-04 6.7~ 04 9.81-04 7.6~ 01 5.4E-03 1.9E 02 Z.lE-02 1.9E 02 Z.lE-02 2.6~ 01 l.ZE-07

4.5E 00 l.OE-03 8.9E 04 4.68-02 5.2E 03 l.lE-04 1.5E 04 4.1E-04 2.5E 04 9.5E-04 5.8E 03 6.7E-01 1.4E 04 2.5E 00 1.4E 04 2.5E 00 2.OE 03 7.1E-05


ORAL

fl-10-3

GONADS 8.4E-10

SI WALL l.lE-09

ULI WALL 2.21-09

LLI WALL 4.2E-09

EFFECTIVE 6.5E-10

INHALATION CLASS w

fl-10-3

GONADS 3.5E-10 (63,13,24) BREAST 1.3E-10 (28,14,58) R HARROW 2.4E-10 (37,27,36) LUNGS 1.6E-09

( 1, 2897) SI WALL 4.3E-10 (63,12,25) ULI WALL 8.4E-10 (64,11,25) LLI WALL 1.6E-09 (66,11,23) EFFECTIVE S.OE-10

38 REPORT OF COMMI’ITEE 2

ANNUAL LIMITS ON INTAKE, ALI (Bq), AND DERIVED AIR CONCENTRATIONS, DAC (Bq/m3), (40 Hr/Wk) FOR Np-234

AL1 DAC INHALATION INHALATION


fl-10-3 fl-10-3 fl-10-3

8.~ 07 l.E 08 4.E 04

Specific effective energy data for Np-235 can be found on p. 719 of ICRP Publication 30; Supplement to Part 2.



INHALATION ORAL CLASS w

ORGAN fl-10-3 fl-10-3

LUNGS 9.1E 05 SI CONTENT 1.4E 04 7.2E 03 ULI CONTENT 4.7E 04 2.3E 04 LLI CONTENT 8.6E 04 4.3E 04 LIVER 7.OE 03 8.OE 05 CORT BONE 1.8E 04 2.1E 06 TRAB BONE 1.8E 04 2.1E 06


ORAL

fl-10-3

BONE SURF 1.5E-10

ULI WALL 2.2E-10

LLI WALL 6.3E-10

EFFECTIVE 5.5E-11

INHALATION CLASS w fl-10-3

R MARROW 1.7E-09 (27,35,38) LUNGS 2.31-09

(0, 0,100) BONE SURF 1.7E-08 (27,35,38) LIVER 1.2E-09 (27,35,38) EFFECTIVE l.lE-09

LIMITS FORINTAKESOFRADIONUCLIDESBYWORKERS 39

ANNUAL LIMITS ON INTAKE, AL1 (Bq), AND DERIVED AIR CONCENTRATIONS, DAC (Bq/m3), (40 Hr,'Wk) FOR Np-235


ORAL CLASS w CIASS w

fl-10-3 fl-10-3 fl-10-3

8.E 08 3.E 07 l.E 04 (9.E 08) (5.E 07) LLI WALL BONE SURF

“;;Np (T, = 1.15 x 105y)

Specific effective energy data for Np-236 and its daughter products can be found on pages 723-726 of ICRP Publication 30; Supplement to Part 2.

NUMBER OF NUCLEAR TP.ANSFORMATIONS OVER 50 YEARS IN SOURCE ORGANS OR TISSUES PER UNIT INTAKE OF $CTIVITY

(TRANSFORMATIONS/Bq) OF Np-236 (T,-1.15~10 y)

ORGAN -‘INHALATION

ORAL CLASS w

fl-10-3 f1-10-3

CORT BONE Np-236 U-236 Th-232 Ra-228 AC-228 Pu-236 U-232 lx-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

TRAB BONE Np-236 U-236 Th-232 Ra-228 AC-228 Pu-236 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

4.3E 05 2.5E-01 2.OE-10 1.2E-10 1.2E-10 3.4E 04 5.9E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 3.3E 03 4.3E 05 2.5E-01 2.OE-10 1.2E-10 1.2E-10 3.4E 04 5.9E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 5.2E 03 3.3E 03

5.1E 07 3.1E 01 2.4E-08 1.5E-08 1.5E-08 4.1E 06 7.1E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 4.OE 05 5.lE 07 3.1E 01 2.41-08 1.5E-08 1.5E-08 4.1E 06 7.1E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 6.3E 05 4.OE 05

COMMITTED DOSE EQUIVALENT PER INTAKE OF UNIT ACTIVITY

ORAL

fl-10-3

R MARROW 4.2E-07

BONE SURF 5.3&-06

EFFECTIVE 2.1E-07

IN TARGET ORGANS OR TISSUES (Sv/Bq) OF Np-236 (TV-1.15~10~ y)

INHALATION CLASS w

fl-10-3

R MARROW 5.1E-05 (25,33,42) BONE SURF 6.43-04 (25.33,42) EFFECTIVE 2.5E-05

40 REPORTOFCOMMITTEEZ

ANNUAL LIMITS ON INTAKE, AL1 (Bq), AND DERIVED AIR CONCENTRATIONS, DAC5(Bq/m3), (40 Hr/'Wk) FOR Np-236

(Th-1.15~10 y)

ALI DAC INHALATION INHALATION


fl-10-3 fl-10-3 fl-10‘3

9.E 04 8.E 02 3.E-01 (2.E 05) (2.E 03) BONE SURF BONE SURF

“92Np (T,,, = 22.5 h)


SOURCES TARGETS SI ULI LLI


GONADS 8.3E-03 2.OE-06 2.28-06 3.3E-06 1.4E-07 1.4E-07 R MARROW l.lE-06 8.33-07 7.1E-07 l.OE-06 l.lE-06 3.OE-05 BONE SURF 3.OE-07 2.43-07 2.21-07 3.23-07 1.8E-04 1.8E-04 SI WALL 2.33-06 1.2E-04 3.33-06 1.8E-06 1.3E-07 1.3E-07 ULI WALL 2.33-06 5.91-06 2.1E-04 8.4E-07 1.2E-07 1.2E-07 LLI WALL 3.OE-06 1.5E-06 6.1E-07 3.43-04 1.8E-07 1.8E-07




GONADS 8.3E 00 4.21-08 5.5E-08 1.3E-07 5.6E-10 5.6E-10 R KARROW 4.63-09 7.33-09 4.63-09 1.6E-08 1.3E-07 3.OE-02 BONE SURF 1.2E-09 1.8E-09 1.2E-09 4.1E-09 1.9E-01 1.9E-01 SI WALL 4.711-08 l.lE-03 9.8E-08 5.3E-08 6.2E-10 6.2E-10 ULI WALL l.lE-07 6.73-07 2.OE-03 3.6E-08 7.4E-10 7.4E-10 LLI WALL 1.4E-07 8.23-08 9.1E-09 3.43-03 2.OE-09 2.OE-09

SPECIFIC EFFECTIVE ENERGY (Me!! PER GRAM PER TRANSFORMATION) OF m-232



GONADS 7.4E 00 2.8E-08 3.61-08 7.63-08 5.7E-10 5.7E-10 R MARROW 5.9E-09 6.6E-09 4.63-09 l.lE-08 8.5E-08 2.73-02 BONE SURF 1.5E-09 1.7E-09 1.3E-09 3.OF.c09 1.7E-01 1.7E-01 SI WALL 3.OE-08 l.OE-03 5.91-08 3.2E-08 6.8E-10 6.8E-10 ULI WALL 6.51-08 4.2E-07 1.8E-03 2.2E-08 7.1E-10 7.1E-10 LLI WALL 8.1E-08 5.OE-08 6.1E-09 3.OE-03 1.5E-09 1.5E-09




GONADS 1.5E-03 3.83-14 5.6B-14 l.lE-13 5.91-17 5.93-17 R MARROW 3.1E-16 2.53-15 1.9E-15 5.OE-16 2.68-13 5.63-06 BONE SURF 7,5E-17 5.91-16 4.5E-16 1.2E-16 3.5E-05 3.5E-05 SI WALL 7.9E-15 2.1E-05 1.5E-14 6.73-15 4.23-16 4.2E-16 ULI WALL 2.53-14 1.2E-12 3.8B-05 2.83-14 5.81-16 5.83-16 LLI WALL 2.73-14 7.83-14 6.8E-15 6.31-05 1.8E-15 1.8E-15


SPECIFIC EFFECTIVE ENERGY (Met' PER GRAM PER TRANSFORMATION) OF AC-228



GONADS 4.63-02 3.OE-05 2.715-05 5.4E-05 3.OE-06 3.OE-06 R MARROW 9.63-06 7.9E-06 6.7E-06 9.8E-06 L.OE-05 1.7E-04 BONE SURF 2.93-06 2.53-06 2.3E-06 3.33-06 2.7E-04 3.OE-04 SI WALL 3.61-05 7.OE-04 5.OE-05 2.8E-05 2.63-06 2.6E-06 ULI WALL 3.4E-05 7.3E-05 1.2E-03 1.3E-05 2.43-06 2.4E-06 LLI WALL 4.3E-05 2.23-05 l.OE-05 1.9E-03 3.33-06 3.3E-06

41

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Pu-236



GONADS l.lE 01 6.2E-08 B.OE-08 2.OE-07 9.1E-10 9.1E-10 R MARROW 6.7E-09 l.OE-08 6.8E-09 2.6E-08 1.8E-07 3.8E-02 BONE SURF 1.6E-09 2.6E-09 1.7E-09 6.4E-09 2.4E-01 2.4E-01 SI WALL 7.43-08 1.5E-03 1.5E-07 8.1E-08 8.2E-10 8.2E-10 ULI WALL 1.6E-07 8.9E-07 2.6E-03 5.23-08 l.OE-09 l.OE-09 LLI WALL 2.1E-07 1.2E-07 1.4E-08 4.3E-03 2.83-09 2.8E-09




GONADS 9.8E 00 6.33-08 E.OE-08 1.8E-07 1.2E-09 1.2E-09 R MARROW l.lE-08 1.3E-08 9.1E-09 2.6E-08 1.8E-07 3.5E-02 BONE SURF 2.8E-09 3.41-09 2,4E-09 6.7E-09 2.2E-01 2.2E-01 SI WALL 7.1E-08 1.3E-03 1.4E-07 7.5B-08 1.3E-09 1.3E-09 ULI WALL 1.5E-07 8.7E-07 2.43-03 4.9E-08 1.4E-09 l..4E-09 LLI WALL 1.9E-07 l.lE-07 1.4E-08 4.OE-03 3.2E-09 3.23-09




GONADS l.OE 01 1.2E-07 1.3E-07 2.4E-07 5.6E-09 5.6E-09 R MARROW 4.93-08 4.OE-08 3.3E-08 5.51-08 1.5E-07 3.63-02 BONE SURF 1.3E-08 l.lE-08 9.8E-09 1.6E-08 2.3E-01 2.3E-01 SI WALL 1.3E-07 1.4E-03 2.OE-07 l.lE-07 5.9E-09 5.9E-09 ULI WALL 1.7E-07 7.73-07 2.5E-03 6.1E-08 5.63-09 5.63-09 LLI WALL 2.2E-07 1.2E-07 3.OE-08 4.1E-03 9.1E-09 9.1E-09

42 REPORTOFCOMMlTTEE2


TARGETS

GONADS R MARROW BONE SURF SI WALL ULI WALL LLI WALL

GONADS

l.lE 01 1.4E-07 4.1E-08 4.2E-07 4.OE-07 S.lE-07

SI CONTENT

3.63-07 l.lE-07 3.5E-08 1.4E-03 8.4E-07 2.51-07

SOURCES ULI

CONTENT

4.1E-07 9.83-08 3.1E-08 5.8E-07 2.5E-03 l.lE-07

LLI CONTENT

6.88-07 1.4E-07 4.5E-08 3.3E-07 l.SE-07 4.2E-03

CORT BONE

2.63-08 1.2E-07 2.4E-01 2.7E-08 2.6E-08 3.7E-08

TRAP. BONE

2.63-08 3.8E-02 2.4E-01 2.7E-08 2.63-08 3.7E-08

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Rn-220


GONADS CONTENT CONTENT CONTWT CORT BONE TRAB BONE

GONADS 1.2E 01 1.2E-08 1.6E-08 2.1E-08 1.4E-09 1.4E-09 R MARROW 4.1E-09 3.3E-09 2.83-09 4.1E-09 4.1E-09 4.2E-02 BONE SURF 1.2E-09 l.OE-09 9.5E-10 1.4E-09 2.6E-01 2.6E-01 SI WALL 1.6E-08 1.6E-03 2.1E-08 1.2E-08 l.lE-09 l.lE-09 ULI WALL 1.5E-08 3.OE-08 2.8E-03 5.5E-09 9.4E-10 9.4E-10 LLI WALL 1.9E-08 8.9E-09 4.OE-09 4.7&-03 1.3E-09 1.3E-09



GONADS CONTENT CONTENT CONTENT CORT BONE TBAB BONE

GONADS 1.3E 01 5.5E-10 5.3E-10 9.3E-10 5.7E-11 5.7E-11 R MARROW 1.7E-10 1.4E-10 1.2E-10 1.7E-10 1.7E-10 4.5E-02 BONE SURF S.lE-11 4.4E-11 3.9E-11 5.7E-11 2.8E-01 2.8E-01 SI WALL 6.4E-10 1.7E-03 8.9E-10 5.OE-10 4.7E-11 4.7E-11 ULI WALL 6.OE-10 1.3E-09 3.OE-03 2.3E-10 4.3E-11 4.3E-11 LLI WALL 7.6E-10 3.8E-10 l.EE-10 5.OE-03 5.8E-11 S.EE-11

SPECIFIC EFFECTIVE ENERGY (MeV PER GRAM PER TRANSFORMATION) OF Pb-212



GONADS 1.6E-02 5.83-06 6.4E-06 l.lE-05 4.OE-07 4.OE-07 R MARROW 2.63-06 2.OE-06 1.7E-06 2.5E-06 2.23-06 6.1E-05 BONE SURF 7.3E-07 6.OE-07 5.4E-07 E.OE-07 3.38-04 3.33-04 SI WALL 6.63-06 2.43-04 9.3E-06 5.2E-06 4.1E-07 4.1E-07 ULI WALL 6.2E-06 1.4E-05 4.23-04 2.33-06 3.83-07 3.8E-07 LLI WALL 8.OE-06 4.OE-06 1.7E-06 6.8E-04 5.63-07 5.6E-07

SPECIFIC EFFECTIVE ENERGY (HeV PER GRAM PER TRANSFORMATION) OF Bi-212


GONADS CONTENT CONTENT CONTENT CORT BONE TFZAB BONE

GONADS 4.1E 00 5.43-06 5.53-06 9.93-06 5.93-07 5.9E-07 RMARROW 1.8E-06 1.5E-06 1.2E-06 1.8E-06 1.9E-06 1.5E-02 BONE SURF 5.4E-07 4.73-07 4.23-07 6.1E-07 9.1E-02 9.1E-02 SI WALL 6.8E-06 1.2E-03 9.4E-06 5.31-06 4.93-07 4.913-07 ULI WALL 6.4E-06 1.4E.05 2.1E-03 2.53-06 4.51-07 4.5E-07

LLI WALL E.lE-06 .4.1E-06 l.EE-06 3.4E-03 6.1E-07 6.1E-07





43

GONADS 1.6E 01 0.0 0.0 0.0 0.0 0.0 R MARROW 0.0 0.0 0.0 0.0 0.0 5.93-02 BONE SURF 0.0 0.0 0.0 0.0 3.7E-01 3.7E-01 SI WALL 0.0 2.23-03 0.0 0.0 0.0 0.0 ULI WALL 0.0 0.0 3.93-03 0.0 0.0 0.0 LLI WALL 0.0 0.0 0.0 6.53-03 0.0 0.0


(TRANSFORXATIONS/Bq) OF Np-236 (T%-22.5 h)

INHALATION ORGAN ORAL cuss w

fl-10-3 fl-10-3

SI CONTENT 04 l.lE-07

3.98-06 6.6EelO 2.OE-11 2.OE-11 2.OE-11 4.1E-12 3.OE-12 1.9E-12 2.9E 04 l.OE-06 8.3E-20 l.SE-23 9.2E-24 7.7E 00 1.2E-04 6.8E-08 6.4E-09 6.43-09 6.4E-09 2.91-09 2.63-09 1.7E-09

9.8E-01 1.2E-06 l.SE-15 l.lE-15 l.lE-15 7.3E-01 2.7E-01 2.5E-01 2.5E-01 2.5E-01 2.5E-01 2.5E-01 2.5E-01 1.6E-01 3.3E 03 2.3&-07 S.lE-19 1.8E-20 l.EE-20 1.7E 00 l.lE-03 7.43-05 6.93-05 6.93-05 6.91-05 6.9E-05 6.9E-05 4.4E-05 7.6E 03 9.31-07 2.7E-18 6.OE-20 6.OE-20 6.9E 00 3.83-03 2.4E-04 2.3E-04 2.31-04 2.33-04 2.23-04 2.2E-04 1.4E-04

JAICRP 19:4-D

REPORTOFCOMMlTTEE2

NUCLEAR TRANSFORMATION DATA POR Np-236 (Tk-22.5 h), CONT'D

INHALATION ORGAN ORAL CLASS w

fl-10-3 fl-10-3

LLI CONTENT Np-236 U-236 Th-232 Ra-228 AC-228 Pu-236 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

CORT BONE Np-236 U-236 Th-232 Ra-228 AC-228 Pu-236 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

TRAB BONE Np-236 U-236 Th-232 Ra-228 AC-228 Pu-236 U-232 Th-228 Ra-224 Rn-220 PO-216 Pb-212 Bi-212 PO-212

3.1E 04 3.21-06 5.83-19 2.2E-22 1.73-22 2.4E 01 8.6B-04 9.8E-07 1.7E-07 1.7E-07 1.7E-07 l.OE-07 9.8E-08 6.33-08 3.1E 01 2.4E-05 2.73-14 1.9E-14 1.9E-14 2.OE 01 5.4E 00 5.OE 00 5.OE 00 5.OE 00 5.OE 00 5.OE 00 5.OE 00 3.2E 00 3.OE 01 2.43-05 2.73-14 1.9E-14 1.9E-14 2.OE 01 5.4E 00 5.OE 00 5.OE 00 f.OE 00 5.OE 00 5.OE 00 5.OE 00 3.2E 00

8.1E 03 2.OE-06 5.3E-18 l.lE-19 l.lE-19 1.5E 01 7.43-03 4.69-04 4.23-04 4.23-04 4.2E-04 4.2E-04 4.23-04 2.73-04 2.5E 03 2.93-03 3.23-12 2.3E-12 2.38-12 2.3E 03 6.5E 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 3.9E 02 2.5E 03 2.9E-03 3.23-12 2.33-12 2.33-12 2.3E 03 6.5E 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 6.OE 02 3.9E 02


COMHITTED DOSE EQUIVALENT IN TARGET ORGANS OR TISSUES PER INTAKE OF UNIT ACTIVITY (Sv,'Bq) OF Np-236 (Tk-22.5 h)

ORAL

fl-10-3

INHALATION CIASS W

fl-10-3

GONADS 6.4E-11

R MARROW 3.3E-10

BONE SURF 4.OE-09 SI WALL 2.6E-10 ULI WALL 9.aR-10 LLI WALL 1.7E-09 EFFECTIVE 3.5E-10

R MARROW 3.9R-08

(25, 33, 42) BONE SURF 4.8E-07

(25, 33, 42) EFFECTIVE 1.9E-08


(T$-22.5 h)


ORAL cuss w CLASS w

fl-10-3 fl-10-3 fl-10-3

l.E 08 l.E 06 4.E 02 (l.E 08) (3.E 06) BONE SURF BONE SURF

237~ 93 P




INHALATION ORGAN ORAL CLASS w

f1-10-3 fl-10-3

CORT BONE Np-237 4.3E 05 5.1E 07 Pa-233 4.3E 05 5.1E 07

TRAB BONE Np-237 4.3E 05 5.1E 07 Pa-233 4.3E 05 5.1E 07

46 REPORTOFCOMMI'ITEEZ

COHNITTED DOSE EQUIVALENT IN TARGET ORGANS OR TISSUES PER INTAKE OF UNIT ACTIVITY (Sv/Bq) OF Np-237

INHAIATION ORAL CIASS w fl-10-3 fl-10-3

R NARROW R NARROW 2.23-06 2.6E-04

(25, 33, 42) BONE SURF BONE SURF 2.7E-05 3.33-03

(25, 33, 42) EFFECTIVE EFFECTIVE 1.X-06 1.3E-04


AL1 DAC INHALATION INHAIATION

ORAL CLASS w CLASS w fl-10-3 fl-10-3 fl-10-3

2.E 04 2.E 02 6.E-02 (5.E 04) (4.E 02) BONE SURF BONE SURF

238 N 93 P


NUHBER OF NUCLEAR TRANSFORMATIONS OVER 50 YEARS ’ IN SOURCE ORGANS OR TISSUES PER UNIT INTAKE OF ACTIVITY

(TRANSFORHATIONS/Bq) OF Np-238

ORGAN

GONADS

SI CONTENT

ULI CONTENT

LLI CONTENT

CORT BONE

TRAB BONE

ORAL

fl-10-3

INHALATION CLASS w

fl-10-3

Np-238 2.81-02 Pu-238 9.53-03 Np-238 1.3E 04 Pu-238 6.1E-02 Np-238 3.7E 04 Pu-238 6.3E-01 Np-238 5.2E 04 Pu-238 2.3E 00 Np-238 8.4~ 01 Pu-238 2.4E 01 Np-238 8.3~ 01 Pu-238 2.4E 01

2.2E 00 l.lE 00 4.4E 03 1.9E-01 1.2E 04 7.7E-01 1.7E 04 1.8E 00 6.4~ 03 2.9E 03 6.4E 03 2.9E 03

LlMlTSFORlNTAKESOFRADlONUCLlDESBYWORKERS 47


ORAL

fl-10-3

GONADS 3.9E-10

SI WALL l.lE-09

ULI WALL 4.2E-09 LLI WALL 8.9E-09 EFFECTIVE 9.5E-10

INHALATION CLASS w

fl-10-3

R MARROW 1.7E-08

(25, 33, 42) BONE SURF 2.1E-07

(25, 33, 42) EFFECTIVE 8.3E-09




fl-10-3 fl-10-3 fl-10-3

5.E 07 2.E 06 l.E 03 (6.~ 06) BONE SURF

239~ 93 P


NUMBER

Documents

This document is copyright protectedJ. VENNART The Commission wishes to acknowledge its indebtedness to J. Vennart for his unselfish efforts in providing direction and leadership to