Behavior of mixed-oxide fuel elements during an overpower transient
Conference
·
OSTI ID:6866984
- Argonne National Lab., IL (United States). Materials and Components Technology Div.
- Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan
For reliable operation of a fast breeder reactor, the fuel elements must be resistant to breaching in slow-ramp, operational overpower transients. To determine this resistance capability of mixed-oxide fuel elements, extended overpower transient tests over a range of element design and operating conditions are being conducted in the Experimental Breeder Reactor-II (EBR-II). These tests are a part of a collaborative Operational Reliability Testing (ORT) program between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan. The Phase 1 portion of the program was successfully completed in 1990; the Phase 2 program is currently in progress. Four extended overpower transient tests were conducted in the Phase-1 ORT program. The results of the first three tests, TOPI-1A, -1B and -1C, using existing preirradiated mixed-oxide fuel elements from the US breeder development program. have been reported. The results of the fourth test, TOPI-1D, using fuel elements specifically designed and fabricated for the ORT program, are the subject of this paper.
- Research Organization:
- Argonne National Lab., IL (United States). Materials and Components Technology Div.
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6866984
- Report Number(s):
- ANL/MCT/CP-76422; CONF-921102--37; ON: DE93004181
- Country of Publication:
- United States
- Language:
- English
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Behavior of mixed-oxide fuel elements during an overpower transient
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
BREEDER REACTORS
EBR-2 REACTOR
EPITHERMAL REACTORS
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EXPERIMENTAL REACTORS
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FAST REACTORS
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LMFBR TYPE REACTORS
MIXED OXIDE FUELS
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POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RUPTURES
SAFETY
SODIUM COOLED REACTORS
SOLID FUELS
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210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
EBR-2 REACTOR
EPITHERMAL REACTORS
EXCURSIONS
EXPERIMENTAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUELS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
PERFORMANCE
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RUPTURES
SAFETY
SODIUM COOLED REACTORS
SOLID FUELS
TESTING
TRANSIENTS