Synergistic effects of surface erosion on tritium inventory and permeation in metallic plasma facing armours
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference13 articles.
1. The interaction of tritium with graphite and its impact on tokamak operations
2. Trapping of deuterium at damage in graphite
3. Retention and thermal release of deuterium implanted in beryllium
4. Hydrogen transport behavior of beryllium
5. Evidences of Hydrogen Trapping in Tungsten and Implications for Plasma-Facing Components
Cited by 4 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. Deuterium retention in recrystallized tungsten irradiated with simultaneous deuterium–neon ion beams;Nuclear Materials and Energy;2017-08
2. The influence of neon or argon impurities on deuterium permeation in tungsten;Journal of Nuclear Materials;2015-08
3. Tritium saturation in plasma-facing materials surfaces;Journal of Nuclear Materials;1998-10
4. The influence of key operation parameters and material properties on the quantification of tritium inventory and permeation in the plasma facing components of ITER;Journal of Nuclear Materials;1997-02
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