Penetration of deuterium into neutron-irradiated tungsten under plasma exposure
Penetration of deuterium into neutron-irradiated tungsten under plasma exposure
复制标题
等离子体暴露下氘渗透到中子辐照的钨中
DOI:
10.1088/1402-4896/ac2c20
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发表时间:
2021
期刊:
影响因子:
2.9
通讯作者:
Ohno Noriyasu
中科院分区:
文献类型:
--
作者:
Yajima Miyuki;Hatano Yuji;Alimov Vladimir Kh;Toyama Takeshi;Kuwabara Tatsuya;Schwarz-Selinger Thomas;Oya Yasuhisa;Spitsyn Alexander V;Ohno Noriyasu
Hydrogen isotope trapping at lattice defects in neutron-irradiated tungsten (W), a leading candidate as plasma facing material, is an important problem determining tritium (T) inventory in a vacuum vessel of a future fusion reactor. In this study, W samples were irradiated with neutrons in the Belgium Reactor 2 at 563 K to 0.06 or 0.016 displacement per atom (dpa). After characterizing defects by positron lifetime measurements, deuterium (D) penetration under exposure to D plasma was examined at 563–773 K. Positron lifetime showed the presence of dislocations, monovacancies and relatively large vacancy clusters. These defects trapped D atoms with different values of binding energy. Dependence of D retention on plasma exposure temperature and damage level indicated that the concentrations of weak traps with smaller binding energy increased more significantly with damage level than those of strong traps.