【摘 要】
：
Tungsten(W),which possesses higher energy threshold for sputtering,low ability to hydride formation and low hydrogen solubility level,has been selected as the most likely candidate of plasma facing ma
【机 构】
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Graduate School of Science and Technology,Shizuoka University,Japan
【出 处】
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第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)
论文部分内容阅读
Tungsten(W),which possesses higher energy threshold for sputtering,low ability to hydride formation and low hydrogen solubility level,has been selected as the most likely candidate of plasma facing materials(PFMs)for future fusion reactors.However,our recent studies showed that the surface of PFMs after plasma exposure was quite different from that before experiment; leading to the hydrogen isotope behavior should be also changed.This paper compares the retention enhancement behavior of hydrogen isotope in W exposed to Large Helical Device(LHD)plasma in 2014 campaign.The W specimens were placed in the four unique positions,namely PI(typical PWI area),DP(deposition dominated area),HL(higher heat load area)and ER(erosion dominated area)in LHD at NIFS and exposed to H and He plasma.Thereafter,additional D2+implantation was performed and the D retention behavior was evaluated by TDS.
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