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Nuclear related materials mechanical properties and microstructure analysis

Author: WangGang
Tutor: ShenYinZhong
School: Shanghai Jiaotong University
Course: Nuclear Energy Science and Engineering
Keywords: Austenitic stainless steel Serrated flow stress Dynamic strain aging Activation energy Tungsten alloy Microstructure
CLC: TL341
Type: Master's thesis
Year: 2012
Downloads: 100
Quote: 0
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Abstract


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CLC: > Industrial Technology > Nuclear technology > Engineering of Nuclear Reactors > Reactor materials and their properties > Structural materials
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