Penetration of deuterium into neutron-irradiated tungsten under plasma exposure

Penetration of deuterium into neutron-irradiated tungsten under plasma exposure
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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
Ohno Noriyasu
中科院分区:
物理与天体物理3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

文献摘要

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中子辐照钨(W)晶格缺陷处的氢同位素俘获是决定未来核聚变反应堆真空容器中氚(T)库存的一个重要问题。在这项研究中,W样品在比利时2号反应堆中用563 K的中子照射到0.06或0.016位移/原子(dpa)。在用正电子寿命测量来表征缺陷后,在563-773 K下测试了暴露于D等离子体下的氘(D)穿透。正电子寿命表现为位错、单空位和相对较大的空位团。这些缺陷捕获了具有不同结合能值的D原子。D保留与等离子体暴露温度和损伤程度的关系表明,与强阱相比,结合能较小的弱阱浓度随损伤程度的增加更为显著。
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.