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

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4.22<br />

methods described in Chapter 6 as alternatives to geologic disposal. However, two <strong>of</strong> these<br />

alternative disposal methods (rock melting and well injection) involve disposal <strong>of</strong> the high-<br />

level waste in liquid form; thus, a modified spent fuel treatment process is required.<br />

Application <strong>of</strong> these methods to disposal <strong>of</strong> dissolved spent fuel presents added nuclear<br />

criticality safety problems and feasability uncertainties resulting from the presence in the<br />

solution <strong>of</strong> all <strong>of</strong> the plutonium and the uranium.<br />

By eliminating the calcination and vitrification operations, the spent fuel treatment<br />

process described in Section 4.3.1.3 could provide a liquid waste stream for disposal.<br />

Additional storage would probably have to be provided for the dissolved spent fuel solution<br />

to allow proper operation <strong>of</strong> the disposal process, however. A flow diagram for such a pro-<br />

cess is shown in Figure 4.3.4.<br />

4.3.2 High-Level Liquid <strong>Waste</strong> Treatment<br />

High-level liquid wastes are defined as "those aqueous wastes resulting from the opera-<br />

tion <strong>of</strong> the first cycle solvent extraction system, or equivalent, and the concentrated<br />

wastes from subsequent extraction cycles, or equivalent, in a facility for reprocessing<br />

irradiated reactor fuels" (10 CFR 50). These wastes contain over 99% <strong>of</strong> the nonvolatile<br />

fission products and actinides, except U and Pu. If spent fuel is reprocessed, the U and<br />

Pu will normally be recycled. Only a small amount <strong>of</strong> U and Pu, perhaps 0.5%, resulting from<br />

waste losses during reprocessing will be in the HLW. Liquid high-level waste can be stored<br />

in tanks as an interim measure, but it must be solidified before transportation and<br />

disposal.<br />

Many HLW treatment processes are under development and DOE is committed to examining<br />

the relative merits <strong>of</strong> many <strong>of</strong> these processes. For this discussion the candidate processes<br />

have been divided into three categories: those that convert the HLW into glass (Sec-<br />

tion 4.3.2.2), into a crystalline solid (Section 4.3.2.3), or into a composite or multiphase<br />

solid form (Section 4.3.2.4). A further important distinction concerning the candidate HLW<br />

waste treatment processes should also be made. The processes fall into two broad classes:<br />

those that have been developed to the stage <strong>of</strong> practical engineering-scale implementation,<br />

and those for which there has been some characterization <strong>of</strong> waste form properties but little<br />

or no process development. Calcine, low-melting glass and cement can be placed in the first<br />

category. All <strong>of</strong> the rest <strong>of</strong> the waste forms to be described fall into the latter, rela-<br />

tively undeveloped category. Additional data on many <strong>of</strong> these processes may be found in<br />

ERDA-76-43.<br />

The processing descriptions given here assume that the HLW is not partitioned before<br />

treatment; however, because chemical partitioning has potential as a pretreatment for<br />

high-level liquid waste, partitioning techniques are also discussed in this section.<br />

Before proceeding with the more general discussion, brief descriptions will be given <strong>of</strong><br />

the two well developed high-level liquid waste treatment processes used in this Statement<br />

for evaluation <strong>of</strong> environmental impacts and costs. These processes are:

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