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Reduced blister quantity in damaged tungsten exposed to deuterium plasma
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作者 Xiu-Li Zhu Long Cheng +6 位作者 ShiWei Wang Yue Yuan Guang-Hong Lu Ying Zhang Er-Yang Lu Xing-Zhong Cao jian-jun huang 《Science China(Physics,Mechanics & Astronomy)》 SCIE EI CAS CSCD 2019年第5期125-128,共4页
Tungsten (W) is a promising candidate for plasma-facing materials (PFMs) in fusion reactors owing to its excellent thermal conductivity, sputtering resistance, and low hydrogen isotope solubility [1]. W PFMs encounter... Tungsten (W) is a promising candidate for plasma-facing materials (PFMs) in fusion reactors owing to its excellent thermal conductivity, sputtering resistance, and low hydrogen isotope solubility [1]. W PFMs encounter the challenges of triple irradiations generated by high-heat loads;high-flux particles, including helium/deuterium (D)/tritium (T);and high-energy neutrons. 展开更多
关键词 damaged TUNGSTEN DEUTERIUM PLASMA
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