Measurements of friction coefficient and strain concetration of barriered fuel claddings under mechanical interaction with pellets.
スポンサーリンク
概要
著者
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Nakatsuka Masafumi
Nippon Nuclear Fuel Development Co. Ltd.
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KOIZUMI Kazuo
Tokyo Electric Power Co., Inc.
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HAYASHI Yo
Toshiba Corp.
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KAWAHARA Akira
Hitachi, Ltd.
関連論文
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- Development of the Ultra-microhardness Technique for Post Irradiation Examination of Fuel Cladding Tubes
- Stress Reorientation of Hydrides in Recrystallized Zircaloy-2 Sheet
- Measurements of friction coefficient and strain concetration of barriered fuel claddings under mechanical interaction with pellets.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (I). Yield loci obtained from knoop hardness.:Yield Loci Obtained from Knoop Hardness
- Effect of oxygen content on tensile properties of low oxygen zircaloy-2.
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- Effect of iodine on fatigue properties of zircaloy-2 fuel cladding under cyclic tensile stress.