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The FuTure oF nuclear Fuel cycle - MIT Energy Initiative

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is that it will be many decades before the U.S. adopts a closed fuel <strong>cycle</strong>, and thus the possibility<br />

exists that a geological repository for disposal of wastes will be sited before implementation<br />

of any closed fuel <strong>cycle</strong>. This creates the option of collocation and integration of reprocessing<br />

and fuel fabrication, with the repository facilities, which could result in potentially major<br />

reductions in closed fuel <strong>cycle</strong> costs and risks. It enables technical options for termination of<br />

safeguards on wastes containing fissile materials. Collocation and integration of back-end fuel<br />

<strong>cycle</strong> facilities may also aid the siting of future repositories. A reprocessing-fabrication facility<br />

would provide many more direct and indirect jobs than would a geological repository. It is not<br />

known if the benefits of collocating and integrating backend facilities are sufficiently large to<br />

drive fuel <strong>cycle</strong> choices.<br />

In the 1950s it was thought that the cost of the closed fuel <strong>cycle</strong> would be low. This was partly<br />

based on the experience of reprocessing defense SNF at the Hanford site with onsite disposal<br />

of wastes. However, the improper disposal of those wastes resulted in high-cost remedial action<br />

programs. By the 1960s it was understood that geological disposal should be used for the<br />

ultimate disposal of many wastes. In the 1960s and early 1970s, the U.S. government encouraged<br />

private construction of reprocessing and fuel fabrication facilities. Because no geological<br />

repository existed, there was no option for collocation of reprocessing, fabrication, and repository<br />

facilities. Reprocessing, fabrication, and repository facilities would be separately located.<br />

Separate siting of closed fuel <strong>cycle</strong> reprocessing and fabrication facilities necessitates storage<br />

and transport of wastes to the geological repository. In turn, these requirements favor<br />

reprocessing and fabrication processes being chosen to minimize waste volumes. However,<br />

by the 1980s it was recognized that the costs of geological repositories for the disposal of<br />

low-heat wastes (clad and hardware, transuranics, low-level, failed equipment, etc.) would<br />

be inexpensive but that the costs of disposal of high-heat wastes (spent <strong>nuclear</strong> fuel and<br />

high-level waste) would be significant. Most of the wastes from reprocessing and fuel fabrication<br />

plants are low-heat wastes. If the reprocessing and fabrication plants were collocated<br />

and integrated with the repository [1], the restrictions on waste volumes for low-heat<br />

wastes would be dramatically relaxed with several impacts.<br />

p Cost. Relaxation of waste volume constraints enables the use of lower cost processes in<br />

reprocessing (such as the chemical decladding of SNF that was done at Hanford) and<br />

fabrication plants. <strong>The</strong> recognition that collocation of backend facilities could result in<br />

significant cost savings resulted in German plans [2] in the 1970s to collocate and integrate<br />

all fuel <strong>cycle</strong> facilities at Gorleben—their proposed repository site. Because of the<br />

German decision to use a once-through fuel <strong>cycle</strong>, that option was never implemented.<br />

p Risk. Facility collocation eliminates some shipping and storage requirements (except<br />

storage of HLW before disposal). Facility integration has the potential to significantly<br />

reduce the process complexity by reducing the requirements to minimize waste volumes<br />

with resultant reductions in potential accident risks.<br />

p Repository performance. <strong>The</strong> relaxation of waste volume constraints allows lower waste<br />

loadings in final waste forms. This, in turn, (1) enables the use of waste forms with potentially<br />

superior performance but that for technical reasons have low waste loadings, (2)<br />

reduces radiation damage to the waste form over time and (3) allows isotopic dilution of<br />

solubility-limited radionuclides to boost performance.<br />

204 <strong>MIT</strong> STudy on <strong>The</strong> <strong>FuTure</strong> <strong>oF</strong> <strong>nuclear</strong> <strong>Fuel</strong> <strong>cycle</strong>

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