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
'
§