Accounting for a Vitrified Plutonium Waste Form in the Yucca Mountain Repository Total System Performance Assessment (Tspa)

Marra, J.C.

doi:10.2172/901094

Cited by 1 publication

(1 citation statement)

References 11 publications

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“…LABS glasses were considered in the late 1980's as a host matrix to transport actinides from Savannah River to Oak Ridge facilities and later evaluated by DOE as a possible waste form for recovered weapons plutonium. The performance of LABS glasses as high-level radioactive waste forms has been evaluated (Marra and Ebert, 2003;Marra et al, 2006;Ebert, 2006). In the event that the fission products in the ER salt can be completely converted from chlorides to oxides, this oxide waste stream could be immobilized into a LABS glass at very high waste loadings (>60 mass%).…”

Section: Lanthanide Borosilicate Glassmentioning

confidence: 99%

Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel

Frank

Park

Cho

et al. 2014

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This report summarizes the treatment and waste form options for waste streams resulting from the electrochemical pyroprocessing of used oxide nuclear fuel. The waste treatment options presented reflect many years of research conducted both in the United States (U.S.) and South Korea (Republic of Korea -ROK). Both nations are evaluating similar advanced fuel cycles involving the treatment used nuclear fuel (UNF) for recycle, isolation of fission products for disposal, and collection of the transuranic elements (TRU) from the used fuel for transmutation in a 'burner' type fast reactor. South Korea and the U.S. have developed different management strategies for waste streams generated from the pyroprocessing of UNF. The U.S. approach involves immobilizing spent electrolytic salt containing oxidized fission products into a ceramic waste form (CWF) and both the contaminated cladding hulls and metallic fission products into a metal waste form (MWF). Both of these waste forms were developed as part of the Experimental Breeder-II (EBR-II) sodium-bonded metallic fuel treatment program. The ROK approach emphasizes product recycle and waste form volume minimization by segregating fission products recovered from process streams for immobilization in separate waste forms. This includes head-end thermal treatment of the UNF to collect volatile and semi-volatile fission products, cladding recycle, and fission product concentration or separation from LiCl or LiCl-KCl salt streams. This allows for salt recycle and for higher fission-product loading in the final waste form. A novel aspect of the ROK waste-steam management process is dechlorination of the salt waste stream performed either prior to or during waste form fabrication for a substantial reduction in waste volume.

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Section: Lanthanide Borosilicate Glassmentioning

confidence: 99%