Fabrication experience with mixed nitride fuels

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6536755

Prunier, C; Bardelle, P ^[1]; Stratton, R W; Ledergerber, G ^[2]; Richter, K

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1. CEA/CEN, Cadarache (France)
2. Paul Scherrer Institute, Villigen (Switzerland)

A solid solution of uranium mononitride and plutonium mononitride (U, Pu, N) is a strong candidate fuel material for advanced liquid-metal-cooled fast breeder reactors. For this reason, a research program, the aim of which is to compare the performance of nitride, carbide, and conventional oxide fuel, has been carried out under the leadership of the French Commissariat a l'Energie Atomique (CEA) over the last 5 yr. Within this program, the various stages of a nuclear fuel route for nitrides have been examined: (1) fabrication of pellets using facilities for the preparation of oxide fuel using a dry route and a sol-gel process; (2) evaluation of in-pile performance up to high burnups; and reprocessing of the irradiated nitride fuel by the PUREX process.

• OSTI ID: 6536755
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
ACTINIDE COMPOUNDS
BREEDER REACTORS
BURNUP
CARBIDES
CARBON COMPOUNDS
CEA
DISPERSIONS
EPITHERMAL REACTORS
EXTRACTION
FABRICATION
FAST REACTORS
FBR TYPE REACTORS
FRENCH ORGANIZATIONS
FUEL ELEMENTS
FUEL PELLETS
FUELS
GELATION
IRRADIATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALLURGY
MIXED NITRIDE FUELS
MIXTURES
NATIONAL ORGANIZATIONS
NITRIDES
NITROGEN COMPOUNDS
PELLETS
PERFORMANCE
PLUTONIUM COMPOUNDS
PLUTONIUM NITRIDES
PNICTIDES
POWDER METALLURGY
PUREX PROCESS
REACTOR COMPONENTS
REACTORS
REDUCTIVE EXTRACTION
REPROCESSING
RESEARCH PROGRAMS
SEPARATION PROCESSES
SOL-GEL PROCESS
SOLID FUELS
SOLID SOLUTIONS
SOLUTIONS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM NITRIDES