Fuel pellet fissile content variation in as-sintered fast reactor fuel

Conference · Thu May 24 00:00:00 EDT 1984

OSTI ID:6231485

Powers, H G; Dutt, D S

Previous studies have shown that a substantial reduction in the manufacturing costs of liquid metal fast breeder reactor fuel can be achived by a relaxation in the mixed uranium/plutonium oxide fuel pellet tolerance specification consistent with demonstrated process capabilities for as-sintered fuel. A number of studies were required to confirm that the proposed relaxations would not be detrimental to reactor core performance. One such study, which compared the expected variability of local fuel pellet fissile content with that allowed based upon reactor performance criteria, is reported herein.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6231485
• Report Number(s): HEDL-SA-3146-FP; CONF-841105-39; ON: DE85003009
• Resource Relation: Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Washington, DC, USA, 11 Nov 1984
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PELLETS
FISSILE MATERIALS
QUALITY ASSURANCE
LMFBR TYPE REACTORS
GRAPHS
MATHEMATICAL MODELS
REACTOR FUELING
SINTERED MATERIALS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSIONABLE MATERIALS
LIQUID METAL COOLED REACTORS
MATERIALS
PELLETS
REACTORS
210500* - Power Reactors
Breeding