Summary of panel discussion on austenitic stainless steels as fusion reactor structural materials
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Cited by 5 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Swelling of cold-worked austenitic stainless steels irradiated in HFIR under spectrally tailored conditions;Journal of Nuclear Materials;2002-12
2. Tensile properties and damage microstructures in ORR/HFIR-irradiated austenitic stainless steels;Journal of Nuclear Materials;2000-12
3. Overview of microstructural evolution in neutron-irradiated austenitic stainless steels;Journal of Nuclear Materials;1993-10
4. Technical Issues in Fusion Reactors — A Review;Fusion Technology;1989-11
5. Swelling behavior of austenitic stainless steels in a spectrally tailored reactor experiment: Implications for near-term fusion machines;Journal of Nuclear Materials;1988-07
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