Effect of Cooling History on Cladding Ductility under LOCA Conditions
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概要
- 論文の詳細を見る
In a Loss-of-Coolant Accident of LWRs, heated and oxidized fuel cladding is slowly cooled and then quenched by re-flooding water. Effects of cooling rate during the slow-cooling process and quench temperature were investigated on post-quench ductility of the oxidized cladding. Unirradiated Zircaloy-4 cladding specimens were oxidized in steam at 1,373 or 1,473 K, cooled at a rate from 2 to 7 K/s, and finally quenched from temperatures ranging 1,073 to 1,373 K. Post-quench ductility was evaluated by ring-compression test, and microscopic properties were examined by metallurgical examination, hardness test, and oxygen analysis. Morphology of oxygen-rich α phase in the metallic prior-β phase layer changed depending on the cooling history. Area fraction of α phase region in the cross section obviously increased and post-quench ductility reduced with decrease in the quenching temperature. Since α phase region with low ductility can be preferential path for crack propagation, increase in area fraction of α phase region possibly decreases resistance for fracture, which results in ductility reduction. On the other hand, the area fraction was nearly constant irrespective of the rate of the slow cooling, and consequently, effect of the cooling rate on the post-quench ductility was negligible.
- 社団法人 日本原子力学会の論文
- 2006-08-25
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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UDAGAWA Yutaka
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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