Lv32
340 积分 2024-11-08 加入
Analysis of Cavitation Damage of HR3C Steel Tube Joints after Internal Pressure Creep Tests
1个月前
已完结
Coupled cluster and dislocation dynamics modeling of microstructure evolution in irradiated materials
1个月前
已完结
Engineering formulation of the irradiation growth behavior of zirconium-based alloys for light water reactors
1个月前
已关闭
Modeling of irradiation growth of Zr single crystals with diffusion anisotropy
1个月前
已完结
Review of the Radiation Effect on the Cladding of Zirconium Alloy in Nuclear Reactors
1个月前
已完结
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