Behavior of mixed-oxide fuel pins during an overpower transient

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6681429

Tsai, H; Neimark, L A ^[1]; Asaga, T; Shikakura, S ^[2]

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1. Argonne National Lab., IL (United States)
2. Power Reactor and Nuclear Fuels Development Corp., Ibaraki-ken (Japan)

For reliable operation of a fast breeder reactor fueled with mixed oxide (MOX) the fuel must be resistant to breaching in slow-ramp, operational overpower transients. To demonstrate this resistance in a range of pin designs and operating conditions, extended overpower transient tests are being conducted in the Experimental Breeder Reactor II (EBR-II) under a collaborative arrangement between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan. The results of the first three tests, designated TOPI-IA, -1B, and -1C, have been reported; the results of the fourth test, TOPI-1D, are the subject of this paper.

• OSTI ID: 6681429
• Report Number(s): CONF-921102-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FBR TYPE REACTORS
FUEL PINS
PERFORMANCE TESTING
EBR-2 REACTOR
INTERNATIONAL COOPERATION
JAPAN
MIXED OXIDE FUELS
TRANSIENT OVERPOWER ACCIDENTS
US DOE
ACCIDENTS
ASIA
BREEDER REACTORS
COOPERATION
DEVELOPED COUNTRIES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FUEL ELEMENTS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TESTING
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding