Behavior of High Burn-up Fuel Cladding under LOCA Conditions
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概要
- 論文の詳細を見る
LOCA-simulated experiments were performed with MDA, ZIRLOTM, M5®, NDA, and Zircaloy-2 cladding specimens with local burn-ups ranging from 66 to 76 MWd/kg. Short test rods fabricated with the cladding specimens were heated, isothermally oxidized at 1,459 to 1,480 K in steam flow, and finally quenched in flooding water. Rod rupture and subsequent double-sided oxidation of the cladding were also simulated in the experiments. Neither split-fracture nor fragmentation occurred during the quench in the cladding specimens which were oxidized to about 18–27% of the metallic thickness. Accordingly, the fracture boundary, a most important safety issue, is not reduced significantly by the high burn-up and use of the new alloys within the examined scope, although it may be somewhat reduced with pre-hydriding during the reactor operation as observed in unirradiated specimens.
- 2009-07-01
著者
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NAGASE Fumihisa
Japan Atomic Energy Agency
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FUKETA Toyoshi
Japan Atomic Energy Agency
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CHUTO Toshinori
Japan Atomic Energy Agency
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Fuketa T
Japan Atomic Energy Agency
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NAGASE Fumihisa
Nuclear Safety Research Center, Japan Atomic Energy Agency
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Nagase Fumihisa
Nuclear Safety Research Center Japan Atomic Energy Agency
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