Temperature characterization of PNC ferritic/martensitic steel fuel cladding after a high-temperature excursion
In an extended overpower transient test (TOPI-1E) in Experimental Breeder Reactor II jointly sponsored by the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan and the U.S. Department of Energy, a mixed-oxide fuel element (UW11048) with advanced PNC high-strength ferritic/martensitic steel (PNC-FMS) experienced cladding breach at an overpower of {approx}75%. The breach was limited to a {approx}30-mm-long region near the top of the fuel column. Because the test element was contained in a flow tube, the resultant fission gas and molten fuel release from the breach apparently caused partial voiding of the sodium, leading to further localized cladding overtemperature before the reactor was scrammed. Some of the expelled molten fuel solidified against the outer surface of the cladding and subsequently caused the melting of a sector of the cladding. The purpose of this study is to characterize the affected cladding by means of metallography and microhardness determination, thereby bracketing the cladding temperatures and providing insights into the events that occurred to the breached fuel element.
- OSTI ID:
- 89087
- Report Number(s):
- CONF-941102-; ISSN 0003-018X; TRN: 95:004215-0157
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 71; Conference: Winter meeting of the American Nuclear Society (ANS), Washington, DC (United States), 13-18 Nov 1994; Other Information: PBD: 1994
- Country of Publication:
- United States
- Language:
- English
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