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Irradiation hardening induced by blistering in tungsten due to low-energy high flux hydrogen plasma exposure

机译:由于低能量高通量氢等离子体暴露,通过钨利用诱导辐照硬化

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In this work, the microstructure evolution in the near-surface of tungsten under hydrogen (H) plasma exposure conditions was observed by means of scanning electron microscopy (SEM), plasma focused ion beam (FIB) and transmission electron microscopy (TEM) techniques. Blisters, with existing dislocations distributed around obviously, were observed beneath the tungsten surface when the exposure temperature was 573 K, which was rarely reported in previous studies. However, H bombardment at 1273 K did not lead to the formation of blister-like microstructures. Correspondingly, irradiation hardening occurred after low temperature exposure, but not after high temperature exposure, according to the Berkovich nano-indentation experiments. In order to characterize the indentation size effect and irradiation hardening behavior of plasma-exposed materials, a mechanistic model was proposed for the hardness-depth relationship. A good agreement between the experimental indentation data and theoretical results revealed that plasma-induced dislocations play a dominant role in determining the increase of hardness for H plasma-exposed tungsten. (C) 2019 Published by Elsevier B.V.
机译:在这项工作中,通过扫描电子显微镜(SEM),等离子体聚焦离子束(FIB)和透射电子显微镜(TEM)技术,观察到氢气(H)血浆暴露条件下氢气(H)血浆暴露条件下的近表面的微观结构演变。当渗透温度为573k时,在钨表面下观察到围绕显然分布的现有脱位的水泡在钨表面下方观察到,在此之前的研究中很少报道。然而,在1273K的H轰炸不会导致泡罩状微观结构的形成。根据Berkovich纳米缩进实验,相应地,在低温暴露后发生辐射硬化,但在高温暴露后不会发生辐照硬化。为了表征等离子体暴露材料的压痕尺寸效应和照射硬化行为,提出了一种机械模型,用于硬度深度关系。实验性缩进数据与理论结果之间的良好一致性揭示了血浆诱导的脱位在确定H等离子体暴露钨的硬度的增加时起显性作用。 (c)2019年由elestvier b.v发布。

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