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

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Draft Appendix L<br />

Issue<br />

280<br />

MULT.IBARRIERS FOR DISPOSAL<br />

In Appendix L (the draft statement) the statement that devitrified glass is stronger<br />

than ordinary glass and will resist further fracturing is not as important as the potential<br />

greater leaching from devitrified glass. (113-EPA)<br />

Response<br />

DOE believes the relative importance <strong>of</strong> these two factors depends on the circumstances<br />

being considered. For instance, the importance <strong>of</strong> fracturing behavior probably predominates<br />

in a transportation accident while leaching behavior will be more important after emplace-<br />

ment in the repository. The essential information that appeared in Appendix L <strong>of</strong> the draft<br />

Statement has been incorporated into Chapter 4 <strong>of</strong> the final Statement. Additional details<br />

can be found in DOE/ET-0028.<br />

Draft Appendix P<br />

Issue<br />

Ringwood and co-workers have identified a suite <strong>of</strong> minerals for use in waste disposal.<br />

Their work should be referenced and seriously considered. (113-EPA)<br />

Response<br />

R'ingwood's work is referred to in final Section 4.3.2.<br />

Draft Appendix 0<br />

Issue<br />

This is a rather interesting appendix although the development <strong>of</strong> the field does not<br />

appear to be sufficiently advanced for any convincing environmental impact analysis. There<br />

seems to be a contradiction between Tables 0.4 and 0.5. In Table 0.4 a 1 meter barrier is<br />

reported to retain strontium-90 and cesium-137 for about 30 years, or about one-half life<br />

for these nuclides. In Table 0.5 a 1 meter barrier is said to retain them for 30 half<br />

lives.<br />

The possible competition for ion exchange sites on added minerals (or natural minerals<br />

for that matter) should be noted. Canister materials are elements <strong>of</strong> the transition series,<br />

notably iron, nickel, chromium, or titanium. In Sweden, lead and copper have been suggested<br />

for canisters. The ion exchange capacity <strong>of</strong> any added materials must be enough to handle<br />

the nonradioelements as well as the radioelements. (113-EPA)

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