The effect of irradiation on the fatigue and flow behavior of TZM alloy
暂无分享,去创建一个
[1] J. Moteff,et al. Substructure of type 316 stainless steel deformed in slow tension at temperatures between 21° and 816°C , 1973 .
[2] R. Schoone,et al. Automatic Unit for Thinning Transmission Electron Microscopy Specimens of Metals , 1966 .
[3] R. Stegman,et al. Environmental Acceleration of Fatigue-Crack Growth in a High-Strength Steel , 1972 .
[4] G. M. Sinclair,et al. Parameter Representation of Low-Temperature Yield Behavior of Body-Centered Cubic Transition Metals , 1966 .
[5] J. Steichen. Tensile properties of neutron irradiated TZM and tungsten , 1976 .
[6] R. Stegman,et al. Flexural Fatigue Machine for High Temperature Operation at Resonance in Vacuum , 1966 .
[7] J. Cahoon. An improved equation relating hardness to ultimate strength , 1972 .
[8] F. Smidt. Correlation of microstructure and strength during stage III annealing of irradiated vanadium , 1971 .
[9] J. Moteff,et al. Voids in neutron irradiated and annealed niobium and niobium-1% zirconium alloy , 1974 .
[10] J. Moteff,et al. Annealing of defect clusters in irradiated tungsten , 1971 .
[11] Richard Chait,et al. Factors influencing the strength differential of high strength steels , 1972 .
[12] C. Liu,et al. Internal oxidation and mechanical properties of TZM-Mo alloy , 1974, Metallurgical and Materials Transactions B.
[13] L. James,et al. Fatigue-crack propagation behavior of type 304 stainless steel in a liquid sodium environment , 1975 .