Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800 °C
Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800 °C
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DOI：
10.1016/j.jnucmat.2023.154239
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发表时间：
2023-03
影响因子：
3.1
通讯作者：
T. Miyazawa;Y. Kikuchi;M. Ando;Ju-Hyeon Yu;K. Yabuuchi;T. Nozawa;H. Tanigawa;S. Nogami;A. Hasegawa
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文献类型：
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作者：
T. Miyazawa;Y. Kikuchi;M. Ando;Ju-Hyeon Yu;K. Yabuuchi;T. Nozawa;H. Tanigawa;S. Nogami;A. Hasegawa
研究了Re和Ta等合金元素在800 °C质子（1 MeV H+）和自离子（18 MeV W 6+）辐照下对再结晶W微观结构演变的影响。尽管空穴密度随质子损伤水平的增加而增加，但W-Re（R）和W-Ta（R）合金中的空穴密度低于纯W（R）合金。在此，向W中添加Re和Ta抑制了空隙形成过程。在质子辐照的W-3%Re（R）合金中，在0.05dpa时观察到大量位错环，这是形核阶段。演化过程的特点是通过团簇和点缺陷的吸收循环增长高达0.2 dpa。然后位错环合并并变大，并且位错线在1dpa时变得缠结。在0.05dpa时，纯W（R）中的位错环已经演化为缠结位错。溶质Re可抑制小位错环和SIA团簇的移动性。在0.05和0.2dpa辐照的W-3%Ta（R）中，观察到拉长位错环的合并过程。溶质Ta对SIA团簇的迁移有抑制作用。自离子辐照W-3%Re（R）至0.2dpa时，没有观察到空位和筏，而纯W（R）至0.2dpa时，不仅观察到位错环，还观察到空位和筏。溶质Re可以抑制小位错环和SIA团簇的迁移，从而抑制自离子辐照下筏的形成，进而抑制空穴的形成。本文应用弥散势垒模型研究了W-3%Re（R）在产生位错线前的辐照硬化。质子辐照W-3%Re（R）合金在0.2dpa以下的硬化主要是由于TEM可见的空洞和位错环。
This study examined the effects of alloying elements such as Re and Ta on the microstructural evolution of recrystallized W under proton (1 MeV H+) and self-ion (18 MeV W6+) irradiations at 800 °C. Although the number density of voids increased with increasing proton-induced damage level, the void density in W-Re (R) and W-Ta (R) alloys were lower than that of pure W (R). Herein, the addition of Re and Ta to W suppresses the void formation process. In the proton-irradiated W-3%Re (R), a lot of dislocation loops were observed at 0.05 dpa which is the stage of nucleation. The evolution process up to 0.2 dpa was characterized by loop growth via the absorption of clusters and point defects. The dislocation loops then coalesce and grow large, and the dislocation lines become tangled at 1 dpa. At 0.05 dpa, the dislocation loops in pure W (R) have already evolved into the tangled dislocations. Solute Re may inhibit the mobility of small dislocation loops and SIA clusters. In W-3%Ta (R) irradiated at 0.05 and 0.2 dpa, the coalescence process of the elongated dislocation loops was observed. Solute Ta may inhibit the mobility of SIA clusters. Although no voids and rafts were observed in self-ion irradiated W-3%Re (R) to 0.2 dpa, not only dislocation loops but also voids and rafts were observed in pure W (R) to 0.2 dpa. Solute Re may inhibit the mobility of small dislocation loops and SIA clusters, so that solute Re would suppress the raft formation and then the void formation under self-ion irradiation. The dispersed barrier model was applied to the irradiation hardening of the proton-irradiated W-3%Re (R) up to 0.2 dpa before developing dislocation lines. The hardening in the proton-irradiated W-3%Re (R) up to 0.2 dpa is mainly due to TEM-visible voids and dislocation loops.