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COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

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This recycling system can be operated flexibly by combining LWR and FBR cycles. Its main<br />

features are the electrolytic transfer of uranium and plutonium to solid and liquid double cathodes and<br />

recovery of transuranium elements from the salt by reductive extraction or electrorefining. Oxide fuels<br />

are first reduced to metals with lithium or calcium. Expected advantages are improved proliferation<br />

resistance, simplified criticality control and economically compact equipment. The disadvantage is lack<br />

of industrial experience with a high-temperature process using corrosive materials.<br />

Figure II.10 Actinide recycling system based on a pyrochemical processing of HLW and<br />

FR metal-fuel FR-irradiation<br />

1.2.2.1 Pyrochemical reprocessing of metal and oxide fuels<br />

The basic pyrochemical process developed at ANL [43] consists of anodic dissolution of spent<br />

fuel, partial recovery of uranium on a solid cathode, and electrolysis of plutonium with the remaining<br />

uranium into a liquid cadmium cathode, with an electrolyte of LiCl-KCl above 500°C [44]. The flow<br />

diagram for metal fuel is shown in Figure II.11. An anodic dissolution test on EBR-II fuel showed that<br />

most of the alloy was dissolved into the salt while a little cladding material remained as residue [45].<br />

Recovery of uranium on the solid cathode has been thoroughly demonstrated with 10 kg deposited in a<br />

dendritic formation [46]. The condition of effective deposition on the solid cathode was investigated by<br />

changing the ratio of surface area of cathode to anode at CRIEPI [44].<br />

Oxide fuels to be treated by this process must first be reduced to metal. ANL experimentally<br />

evaluated several methods, such as salt transport, the Zn-Mg process, Mg extraction and lithium<br />

reduction. The lithium process has the advantages of a lower operating temperature, less corrosive<br />

environment and small amounts of salt waste. Single element tests with uranium, plutonium and other<br />

elements, demonstrate the reduction to metallic form in LiCl or LiCl-KCl above 500 o C, resulting in the<br />

formation of lithium oxide which will be electrolytically decomposed for recycling.<br />

Multi-element tests of the whole process, preferably with real fuels, are going on to find out<br />

the technical feasibility of lithium reduction, proceeding to find the best operating conditions for pilotand<br />

larger-scale trials at CRIEPI.<br />

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