Influence of Precipitated Hydride on the Fracture Behavior of Zircaloy Fuel Cladding Tube
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概要
- 論文の詳細を見る
In order to clarify the influence of precipitated hydride on the fracture behavior of Zircaloy cladding tubes, the stress-strain distribution of the cladding was estimated by finite element method (FEM) analysis. The mechanical properties of α-phase of zirconium and zirconium hydride required for the analysis were examined by means of an ultrasonic pulse-echo method and a tensile test. It was found from the analysis that the non-hydrided cladding has the highest equivalent plastic strain at the inner surface of the cladding, suggesting that the fracture initiated at the inner surface of the cladding. Since the hydride accumulated layer located in the outer surface of the hydrided cladding fails at a lower internal pressure, the crack appears to initiate at the outer surface of the cladding. The fracture behavior estimated from the stress states of the hydrided cladding was in good agreement with the experimental results obtained by pulse irradiation tests of the Nuclear Safety Research Reactor (NSRR) and high-pressurization-rate burst tests in the Japan Atomic Energy Research Institute (JAERI).
- 社団法人 日本原子力学会の論文
- 2000-08-25
著者
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Nagase F
Japan Atomic Energy Res. Inst. Ibaraki
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Nagase Fumihisa
Department Of Reactor Safty Research Japan Atomic Energy Research Institute
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Uetsuka Hiroshi
Department Of Reactor Safety Research Japan Atomic Energy Research Institute
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Uetsuka Hiroshi
Department Of Reactor Safty Research Japan Atomic Energy Research Institute
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YAMANAKA Shinsuke
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
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KURODA Masatoshi
Department of Nuclear Engineering, Graduate School of Engineering, Osaka University
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Yamanaka Shinsuke
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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Yoshioka Kunihiko
Department Of Urology Tohoku University School Of Medicine
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ANADA Hiroyuki
Sumitomo Metal Industries, Ltd.
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Kuroda Masatoshi
Department Of Mechanical System Engineering Graduate School Of Science And Technology Kumamoto Unive
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Kuroda Masatoshi
Department Of Nuclear Engineering Graduate School Of Engineering Osaka University
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UETSUKA Hiroshi
Department of Fuel Safety Research, Japan Atomic Energy Research Institute
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