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

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5.88<br />

probability that the drill (0.5 m in diameter) will strike a waste canister is 0.005 per<br />

drilling event, because <strong>of</strong> the relative cross sectional areas involved.<br />

For dose calculations it is assumed that during drilling one-fourth <strong>of</strong> the waste in one<br />

canister is circulated to the surface with the drilling mud, and the radioactive material is<br />

uniformly distributed over 0.5 ha in the top 5 cm <strong>of</strong> the surface soil.<br />

Table 5.5.10 lists the expected releases to air from contaminated surface soil. These<br />

values are based upon 1) a resuspension factor <strong>of</strong> 0.011/yr 2) the assumption that one-fourth<br />

<strong>of</strong> the radioactive material in the top 5 cm is available for resuspension and 3) that 0.10<br />

<strong>of</strong> the material resuspended is respirable. The maximum individual is exposed, on the aver-<br />

age, to the contaminated soil for 12 hr/day. Based on the releases given in Table 5.5.10<br />

and methods <strong>of</strong> dose calculations presented in Appendix D, first-year doses and 70-yr doses<br />

to the maximum individual who will reside and grow crops for his consumption on the con-<br />

TABLE 5.5.10. Respirable Radionuclides Released to the<br />

Atmosphere from Salt Repository Breach by<br />

Drilling 1000 Yrs After Repository Closure, Ci<br />

Radionuclide Spent Fuel HLW<br />

14C(*) 1.7 x 10- 4 1.1 x 10o 6<br />

- 5<br />

- 4<br />

126Sb 1.2 x 10 1.1 x 10<br />

1 2 6 Sn 1.2 x 10- 5 1.1 x 10- 4<br />

1291(*) 8.6 x 10- 6 7.4 x 10- 7<br />

2 3 9 Np 3.4 x 10- 4 9.0 x 10- 3<br />

2 4 0 Pu 1.1 x 10- 2<br />

4.4 x 10- 4<br />

2 4 1 Am 2.2 x 10- 2 3.2 x 10- 2<br />

239u 7.3 x 10- 2 6.3 x 10- 4<br />

(*) The bulk <strong>of</strong> the C and I is volatized during<br />

dissolution <strong>of</strong> the spent fuel and stored in<br />

separate containers and locations different<br />

than those used for HLW in the repository.<br />

For these two nuclides, 100% <strong>of</strong> the material<br />

resuspended is assumed respirable.<br />

taminated land were calculated. The first-year whole-body doses amounted to 13 rem for<br />

drilling through a spent fuel canister and 19 rem for drilling through a HLW waste can-<br />

ister. The 70-yr whole body doses were 9.4 x 102 and 1.4 x 103 rem, respectively.<br />

The predominant mode <strong>of</strong> exposure is direct radiation(a) from contaminated soil and<br />

as a consequence, dose to the various organs is substantially the same the first year.<br />

During the 70-yr dose period the dose via the ingestion pathway increases substantially,<br />

particularly in terms <strong>of</strong> dose to bone. The 70 year accumulated doses as calculated might<br />

result in a small increase in risk <strong>of</strong> life shortening, contracting lukemia, etc.<br />

(a) 2 4 1 Am is the principal contributor to the direct radiation dose. The dose from<br />

breach <strong>of</strong> a HLW canister was reported in the draft Statement, and in supporting<br />

documents, as about 100 times higher than here because an incorrect 2 4 1 Am inventory<br />

was used.

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