Studies on Tritium Interactions with Plasma Facing Material at the Tritium Process Laboratory Of Jaeri
作者： T. Hayashi , S. O’hira , H. Nakamura , T. Tadokoro , W. M. Shu
DOI: 10.1007/978-94-011-4331-8_25
关键词: Tritium 、 Carbon fiber composite 、 Radiochemistry 、 Nuclear engineering 、 Fusion power 、 Scientific method 、 Plasma-facing material 、 Coolant 、 Environmental science 、 Hydrogen isotope
摘要: From a view point of safety evaluation fusion reactors, estimation permeation amounts tritium to coolant through plasma facing components (PFC) is one the critical issues. Moreover, inventory in materials important subject not only for safety, but also accountability reactors [1].
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