Effect of oxygen content on tensile properties of low oxygen zircaloy-2.
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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NAGAI Masayuki
Nippon Nuclear Fuel Development Co., Ltd.
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IMAHASHI Hiromichi
Nippon Nuclear Fuel Development Co., Ltd.
関連論文
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- 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.
- Stress corrosion cracking of zircaloy-2 by metal iodides.
- Reduction of plastic anisotropy of zircaloy cladding by neutron irradiation. (II). Numerical simulations of yield loci.:Numerical Simulations of Yield Loci
- Effect of iodine on fatigue properties of zircaloy-2 fuel cladding under cyclic tensile stress.