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

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4.32<br />

Center has been set up to provide techniques for comparing important waste form materials<br />

characteristics on a common basis (Nelson et al. 1980). The first issue <strong>of</strong> the Nuclear<br />

<strong>Waste</strong> Materials Handbook will be published in approximately two years. It will contain<br />

materials data, not only for candidate waste forms, but also for other waste package com-<br />

ponents.<br />

Since the most likely mechanism for release <strong>of</strong> radionuclides to the biosphere is reac-<br />

tion with and transport by ground water, resistance to leaching <strong>of</strong> radionuclides by ground<br />

water is the performance characteristic <strong>of</strong> major interest. Leach resistance can be highly<br />

dependent upon the physical, chemical, mechanical, and radiation stability <strong>of</strong> the waste<br />

form. The stability <strong>of</strong> a waste form depends upon its response to radiation, temperature,<br />

and the chemical environment (Mendel et al. 1975). The factors influencing long-term sta-<br />

bility are: 1) transmutation by radioactive decay, which may alter the chemical structure<br />

<strong>of</strong> the waste form; 2) recoil from alpha decay, which may break chemical bonds and alter the<br />

physical structure <strong>of</strong> the waste form; 3) heat generated by radioactive decay, which may<br />

cause the waste form to change to a more thermodynamically stable state and which may accel-<br />

erate potential chemical reactions, including leaching; and 4) the chemical environment,<br />

i.e., water plus dissolved ions, which ultimately determines the rate <strong>of</strong> release <strong>of</strong> radioactive<br />

materials into the repository.<br />

4.3.3 TRU <strong>Waste</strong> Treatment in the Reprocessing Cycle<br />

When spent fuel is reprocessed for uranium and plutonium recycle, the non-high-level<br />

and nongaseous wastes that result from these operations and from the mixed oxide fuel fabri-<br />

cation must also be treated and packaged. This section addresses the treatment <strong>of</strong> these<br />

solid and liquid TRU wastes. Treatment and packaging processes for such wastes are<br />

described in detail in DOE-ET-0028 (Section 4.0), where wastes are discussed in four cate-<br />

gories: 1) fuel residue (the fuel hulls and assembly hardware), 2) failed equipment and<br />

noncombustible waste, 3) compactable and combustible waste, and 4) wet and particulte solid<br />

wastes. Brief descriptions <strong>of</strong> the treatment processes for these wastes are given in the<br />

following sections; the referenced document may be consulted for details. Both TRU and<br />

non-TRU wastes <strong>of</strong> the latter three categories result from operation <strong>of</strong> fuel reprocessing<br />

plants (FRPs). Only the treatment <strong>of</strong> the TRU wastes is considered in this Statement; the<br />

treatment <strong>of</strong> the non-TRU portions would be similar, however.<br />

4.3.3.1 Fuel Residue Treatment<br />

Packaging without compaction is the example fuel residue treatment process used in this<br />

Statement. Mechanical compaction <strong>of</strong> hulls and melting <strong>of</strong> hulls are also described to illus-<br />

trate other alternatives. The fuel residue packages have surface dose rates well above<br />

0.2 R/hr. Remote handling <strong>of</strong> these wastes is thus required.<br />

Fuel Residue Packaging Without Compaction (Example Method)<br />

Packaging without compaction is a treatment concept in which the nonsegregated fuel<br />

residue is monitored for undissolved fuel, dried, and sealed without compaction in stainless

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