RMI Nuclear Justice Documents

in Tables 2

Radionuclide concentrations used for input data are listed

‘ky

Fthrough 7;

a 2 1/d intake is assumed for each source of water.

137g, 90g, 23942405

241

u, and
Am,
r
3
F calculated fo
Fradionuc li des in the environment of each atoll.
137
“a
The
doses

Cs

F tnternational

are

Commission

calculated

on

using

Radiological

The doses are

the four most significant
the

methods

Protection

outlined

(rerp)}7~19

by

the

and

the

The
B National Council on Radiation Protection and Measurements (NCRP ), 20
H model consists of two exponential components with half-lives of 2 and 110 d,
Dwith

10% of

the

compartment and 90% to the
4137
The gut-transfer coefficient for
Cs is assumed to be l.

it compartment.
The

90¢,

intake

doses

going

are

to

the

2-d

calculated

in

B’< Bennett is used to correlate the 90 Sr
bone. 21-23

Rin mineral
a

Second,

two

steps.

First,

concentrations

the dosimetric

in

model

the

the

diet

developed

by

110-d

model
with

of
that

Spiers

is

Bs

FP used to calculate the bone-marrow dose rate from the concentration in mineral
A bone.24
a

For the

F the

gut

transuranics Pu and Am,

transfer:

1

m organs are bone and

X

10~¢

for

liver with

i bone and 40 y in liver.

Pu

the most recent

and

5

x

i104

ICRP values are used for

for

Am. +7

100-y biological half-lives

The

critical

for Pu and Am in

Of the Pu and Am transferred to blood, 45% is assumed

: to reach bone and liver.
More detailed discussions of

the dose calculation methodology

for each

E radionuclide can be found in Ref. 25.
e

Both

the maximum annual-dose

Bi are calculated.

d the dose
au whole-body

in
s

For bone marrow
and
Sr

the

external

in bone

via

that

for

the

30- and

50-y

year after consumption begins when

ingestion dose and
it

is

when

the

gamma

dose

is

ingestion and

steady-state conditions and
year

and

integral

doses

The maximum annual-dose rate for the whole body is defined as

rate

137,

rates

1376,

for

both

the external gamma dose

bone-marrow
a maximum.
the

the

1376.

Because

resultant

and

of

buildup

ingestion dose

accumulation

of

to a maximum dose

at

the continuously decreasing dose after
ingestion

and

external

the

is a maximum.

905,

the

sum of

gamma,

the

the

first

maximum

annual-dose rate in bone marrow can occur in a different year than the maximum

annual-dose rate for the whole body.
ty

.

The maximum annual~dose rates for each of the atolls for intake of both

cistern water and groundwater are

listed

in

‘lable

8.

The

30- and

integral doses are listed in Tables 9 and 10, respectively.
Table
the individual radionuclide contribution to the 30-y integral dose.

ll

50-y
lists

!

\

i

'

§