Progress of nitride fuel cycle research for transmutation of minor actinides

Conference · Sun Jul 01 00:00:00 EDT 2007

OSTI ID:20979658

Arai, Yasuo; Akabori, Mitsuo; Minato, Kazuo ^[1]

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1. Japan Atomic Energy Agency - JAEA, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195 (Japan)

Recent progress of nitride fuel cycle research for transmutation of MA is summarized. Preparation of MA-bearing nitride pellets, such as (Np,Am)N, (Am,Pu)N and (Np,Pu,Am,Cm)N, was carried out. Irradiation behavior of U-free nitride fuel was investigated by the irradiation test of (Pu,Zr)N and PuN+TiN fuels, in which ZrN and TiN were added as a possible diluent material. Further, pyrochemical process of spent nitride fuel was developed by electrorefining in a molten chloride salt and subsequent re-nitridation of actinides in liquid Cd cathode electro-deposits. Nitride fuel cycle for transmutation of MA has been demonstrated in a laboratory scale by the experimental study with MA and Pu. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 20979658
• Resource Relation: Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 18 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AMERICIUM NITRIDES
CHLORIDES
ELECTROREFINING
FUEL CYCLE
MOLTEN SALTS
NEPTUNIUM NITRIDES
NITRIDATION
NUCLEAR FUELS
PLUTONIUM NITRIDES
PYROCHEMICAL REPROCESSING
TITANIUM NITRIDES
TRANSMUTATION
ZIRCONIUM NITRIDES