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Management of Commercially Generated Radioactive Waste - U.S. ...

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5.84<br />

Dilution Dilution<br />

Element Factor Element Factor<br />

H 2 Cs 100<br />

C 2 Sm 100<br />

Co 100 Eu 100<br />

Ni 100 U 100<br />

Sr 100 Np 100<br />

Nb, Zr 100 Pu 100<br />

Sb 2 Am 100<br />

Sn 2 Cm 100<br />

I 2<br />

Saltwater bioaccumulation factors were used to estimate the concentration <strong>of</strong> radionu-<br />

clides in the edible portion <strong>of</strong> marine foods (Soldat, Robinson and Baker 1974). The 70-yr<br />

dose to the maximum individual from ingestion <strong>of</strong> mollusks (at a rate <strong>of</strong> 10 kg/yr) for<br />

repository breaches at 1,000, 100,000 and 1,000,000 years after repository closure were<br />

calculated. The largest <strong>of</strong> these, 7.2 x 10-2 rem to the whole-body, would add about 1% to<br />

the dose the individual would have received from naturally occurring sources for the same<br />

period and would not add significantly to the maximum individual's 70-year dose commitment.<br />

The second scenario developed for the repository fracture and flooding assumes that<br />

radionuclides are leached from the waste and carried beyond the boundaries <strong>of</strong> the host rock<br />

and are then transported via moving (100 m/yr) ground water through the ground before enter-<br />

ing the biosphere (the R river).<br />

In this scenario a migration path length <strong>of</strong> 10 km was investigated, using sorption<br />

equibrium constants (Kd values) measured or estimated under conditions at the Hanford Site,<br />

Richland, Washington. While these parameters are believed to be representative <strong>of</strong> average<br />

conditions to be expected at candidate sites, all factors could vary by several orders <strong>of</strong><br />

magnitude.<br />

Based on inventories <strong>of</strong> radionuclides in repositories and the models and dose calcula-<br />

tion methods according to Lester et al. (1975) and Burkholder et al. (1975), doses were cal-<br />

culated for the maximum individual.(a) Total body doses are presented in Table 5.5.9 as a<br />

function <strong>of</strong> time since disposal and for leach rates ranging from 0.1% to 0.01% <strong>of</strong> inventory<br />

per year.(b)<br />

The doses given in Table 5.5.9 were calculated to result from leaching <strong>of</strong> all wastes<br />

from a 50,000 MTHM example repository in salt. These doses would be about 2.5 times higher<br />

for the repositories in granite or basalt and about 1.3 times higher should the event occur<br />

in a shale repository due to larger amounts <strong>of</strong> waste contained in those repositories. In<br />

(a) A computer model called GETOUT for hydrologic transport (Lester et al. 1978) was used<br />

in conjunction with a dose to biota model (Burkholder et al. 1975) as adjusted for parameters<br />

developed for the midwest reference environment.<br />

(b) Several commenters on the draft concluded that total release <strong>of</strong> inventory in one year<br />

as presented in the draft Statement was out <strong>of</strong> the question. As a onsequence the 100%<br />

removal per year case is omitted. The leach rates <strong>of</strong> 1 x 10-5 g/cm -day used in the<br />

fracturing and stream flooding scenario amounts to about 1% <strong>of</strong> inventory removed per<br />

year, using assumptions that maximize the area available to contact water.

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