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Behavior of mixed-oxide fuel elements during an overpower transient

Conference ·
OSTI ID:10110244
;  [1]; ;  [2]
  1. Argonne National Lab., IL (United States). Materials and Components Technology Div.
  2. Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan
+ Show Author Affiliations
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:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
10110244
Report Number(s):
ANL/MCT/CP--76422; CONF-921102--37; ON: DE93004181
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
EBR-2 REACTOR
EXCURSIONS
FUEL ELEMENTS
LMFBR TYPE REACTORS
MIXED OXIDE FUELS
PERFORMANCE
POWER REACTORS
BREEDING
REACTOR SAFETY
RUPTURES
TESTING
TRANSIENTS