FFTF criteria for run-to-cladding-breach experiments

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6581604

Van Keuren, J C; Heard, F J; Stepnewski, D D

The Fast Flux Test Facility (FFTF) is a liquid-metal-cooled fast reactor, which is designed to test a variety of different structural and fuel materials. A safety analysis is performed for each experiment that is irradiated in FFTF. The FFTF final safety analysis report (FSAR) assumed that all driver fuel assemblies would maintain cladding integrity during normal operations and all design transients. Maintenance of cladding integrity retains three barriers to any fission gas release to the public and also prevents any potential contact between the fuel and coolant. Experiments are, in general, expected to meet the same criterion. Selected experiments can, however, be classified as run-to-cladding-breach experiments (RTCB). The purpose of this paper is to describe alternative acceptance criteria for RTCB experiments that they feel provide protection equivalent to the maintenance of cladding integrity.

• Research Organization: Westinghouse Hanford Co., Richland, WA
• OSTI ID: 6581604
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

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EPITHERMAL REACTORS
FAST REACTORS
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FISSION PRODUCT RELEASE
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
FUEL INTEGRITY
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LIQUID METAL COOLED REACTORS
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REACTIVITY
REACTOR ACCIDENTS
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RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
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TEST REACTORS
TRANSIENTS