钨
材料科学
辐照
氘
氚
核反应分析
放射化学
中子通量
单晶
热脱附光谱法
通量
中子
分析化学(期刊)
解吸
Crystal(编程语言)
离子
原子物理学
核物理学
化学
结晶学
物理
吸附
有机化学
冶金
程序设计语言
色谱法
计算机科学
作者
M. Shimada,Yasuhisa Oya,W.R. Wampler,Yuji Yamauchi,Chase N. Taylor,Lauren M. Garrison,D. Buchenauer,Yuji Hatano
标识
DOI:10.1016/j.fusengdes.2018.04.094
摘要
Six single crystal tungsten specimens were neutron irradiated to a dose of 0.1 displacements per atom (dpa) at three different irradiation temperatures (633 K, 963 K, and 1073 K) at the High Flux Isotope Reactor in Oak Ridge National Laboratory under the US-Japan PHENIX project. A pair of neutron-irradiated tungsten specimens was exposed to deuterium (D) plasma to D ion fluence of 5.0 × 1025 m−2 at three different exposure temperatures (673 K, 873 K, and 973 K) at the Tritium Plasma Experiment in Idaho National Laboratory. A combination of thermal desorption spectroscopy, nuclear reaction analysis, and rate-diffusion modeling code (Tritium Migration Analysis Program, TMAP) were used to understand D behavior in neutron-irradiated tungsten. A broad D desorption spectrum from the plasma-exposure temperature up to 1173 K was observed. Total D retention up to 1.9 × 1021 m−2 and near-surface D concentrations up to 1.7 × 10−3 D/W were experimentally measured from the 0.1 dpa neutron-irradiated single crystal tungsten. Trap density up to 2.0 × 10−3 Trap/W and detrapping energy ranging from 1.80 to 2.60 eV were obtained from the TMAP modeling.
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