Helium implantation effects on low activation 9Cr martensitic steels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference13 articles.
1. Effects of irradiation on low activation ferritic alloys
2. Effect of specimen size on the ductile-brittle transition behavior and the fracture sequence of 9Cr-W steels
3. Phase stability of reduced activation ferritic steel: 8%Cr-2%W-0.2%V-0.04%Ta-Fe
4. The development of low-activation martensitic 9 and 11%Cr,W,V stainless steels for fusion reactor applications
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1. Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review;Journal of Physics: Energy;2022-07-01
2. Effects of displacement damage and helium production rates on the nucleation and growth of helium bubbles – Positron annihilation spectroscopy aspects;Journal of Nuclear Materials;2018-02
3. Vacancy-type defects and hardness of helium implanted CLAM steel studied by positron-annihilation spectroscopy and nano-indentation technique;Fusion Engineering and Design;2012-08
4. Effects of helium on ductile-brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature;Journal of Nuclear Materials;2009-04
5. Fatigue Properties of Helium Injected F82H-IEA Heat Material;MATERIALS TRANSACTIONS;2009
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