Deuterium retention in tungsten from exposure to plasma
Deuterium retention in tungsten from exposure to plasma
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DOI：
10.1088/0031-8949/2009/t138/014037
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发表时间：
2009-12
期刊：
影响因子：
2.9
通讯作者：
W. Wampler;R. Doerner
中科院分区：
文献类型：
--
作者：
W. Wampler;R. Doerner
描述了在高达1022 D原子cm-2的注量下暴露于等离子体中的钨中氘的保留特性的实验。位移损伤的氘保留的影响进行了研究的损伤水平高达0.6位移每原子（dpa）由12 MeV的硅离子辐照产生的。在受损和未受损材料中均观察到与沉淀和起泡相关的近表面保留。还观察到位移损伤处的陷获。这些实验确定了相对于dpa产生的陷阱的数量，以及在暴露于等离子体期间它们被填充的速率。这些结果表明，由于在较低温度（500 °C）下氚渗透到陷阱的深度较浅，因此由于中子损坏处的俘获而导致的ITER偏滤器中氚存量的增加应该相对较小。
Experiments are described which characterize retention of deuterium in tungsten resulting from exposure to plasma at fluences up to 1022 D atoms cm−2. The influence of displacement damage on deuterium retention is investigated for damage levels up to 0.6 displacements per atom (dpa) produced by 12 MeV silicon ion irradiation. Near-surface retention associated with precipitation and blistering was seen in both damaged and undamaged material. Trapping at displacement damage was also observed. These experiments determined the number of traps produced versus dpa, and the rate at which they are filled during exposure to plasma. These results indicate that the increase in tritium inventory in the ITER divertor due to trapping at neutron damage should be relatively small due to the shallow depth of penetration of tritium to traps at lower temperatures (500 °C).