Status on Nuclear Waste Separation and Transmutation Technologies in JNC

Conference · Wed Sep 15 00:00:00 EDT 1999

OSTI ID:23142076

Ozawa, Masaki ^[1]; Wakabayashi, Toshio ^[2]

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1. Japan Nuclear Cycle Development Institute, Ooarai, Naritamachi 4002, ibaraki (Japan)
2. Japan Nuclear Cycle Development Institute, Tokai-mura,4-33, ibaraki (Japan)

Separation and transmutation of long-lived TRU and FPs are recognized as two of the key concepts in JNC's newly developing nuclear strategy in the coming FBR fuel cycle, which are to be economically more compatible and set a new ecological global standard. Total separation of TRU in the spent fuel is under consideration by a combination of PUREX and TRUEX methods with their well-improved flowsheet using several kind of salt-free reagents and techniques. Electrolytic extraction (electro-reduction) of fission rare metals covering LLFPs and electrolytic decomposition (electro-oxidation) of spent solvent are both Promising for the ultimate recycling or reduction of radioactive wastes. Pd{sub adatom} and Ag{sup 2+} are utilized as promoter and mediator, respectively, in these electro-redox schemes. Concerning MA transmutation, it was found that the mixed hybrid MA-loading method, where Np nuclide is dispersed uniformly in the core and target subassemblies containing Am, Cm, and rare earth nuclides are loaded into the radial blanket region, has a great potential to achieve effective transmutation of MA without serious drawbacks in terms of core performance. Fission cross section ratios of minor actinide nuclides ({sup 237}Np, {sup 241}Am, {sup 243}Am, {sup 242m}Am, etc.) in the fast and epithermal neutron energy region have been measured to evaluate the accuracy of MA nuclear data. As for fabrication and investigation of irradiation behavior of MOX containing MA, a systematic program has been planned.

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23142076
• Resource Relation: Conference: Global'99: International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia, Las Vegas, NV (United States), 29 Aug - 3 Sep 1999; Other Information: Country of input: France; 11 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDES
AMERICIUM 241
AMERICIUM 242
AMERICIUM 243
CROSS SECTIONS
EPITHERMAL NEUTRONS
FLOWSHEETS
FUEL CYCLE
IRRADIATION
NEPTUNIUM 237
OXIDATION
PERFORMANCE
RADIOACTIVE WASTES
RARE EARTHS
RECYCLING
SOLVENTS
SPENT FUELS
TRANSMUTATION