Reliability of fast reactor mixed-oxide fuel during operational transients

Conference · Mon Jul 01 04:00:00 EDT 1991

OSTI ID:5134575

Boltax, A; Neimark, L A; Tsai, Hanchung ^[1]; Katsuragawa, M; Shikakura, S ^[2]

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1. Argonne National Lab., IL (United States)
2. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 figs., 4 tabs.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5134575
• Report Number(s): ANL/CP-73613; CONF-911001--18; ON: DE91018633
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALLOYS
BREEDER REACTORS
BURNUP
COOPERATION
COORDINATED RESEARCH PROGRAMS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXCURSIONS
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FUEL CANS
FUEL ELEMENTS
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MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
PNC
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
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RUPTURES
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TRANSIENTS
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