Behavior of mixed-oxide fuel pins during an overpower transient
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6681429
- Argonne National Lab., IL (United States)
- 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--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
Similar Records
Behavior of mixed-oxide fuel elements during an overpower transient
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Sat Oct 31 23:00:00 EST 1992
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Behavior of mixed-oxide fuel elements during an overpower transient
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Thu Jan 31 23:00:00 EST 1991
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ASIA
BREEDER REACTORS
COOPERATION
DEVELOPED COUNTRIES
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
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INTERNATIONAL COOPERATION
JAPAN
LIQUID METAL COOLED REACTORS
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MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
PERFORMANCE TESTING
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
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RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
US DOE
US ORGANIZATIONS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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BREEDER REACTORS
COOPERATION
DEVELOPED COUNTRIES
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL PINS
FUELS
INTERNATIONAL COOPERATION
JAPAN
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
PERFORMANCE TESTING
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
TESTING
TRANSIENT OVERPOWER ACCIDENTS
US DOE
US ORGANIZATIONS