Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800 °C

被引:4
|
作者
Miyazawa, Takeshi [1 ,4 ]
Kikuchi, Yuta [1 ]
Ando, Masami [2 ]
Yu, Ju-Hyeon [2 ]
Yabuuchi, Kiyohiro [3 ]
Nozawa, Takashi [2 ]
Tanigawa, Hiroyasu [2 ]
Nogami, Shuhei [1 ]
Hasegawa, Akira [1 ]
机构
[1] Tohoku Univ, Sendai 9808579, Japan
[2] Natl Inst Quantum Sci & Technol, Rokkasho 0393212, Japan
[3] Kyoto Univ, Uji 6110011, Japan
[4] Japan Atom Energy Agcy, Oarai, Ibaraki 3111393, Japan
基金
日本学术振兴会;
关键词
Refractory metals; Binary alloys; Radiation damage; Ion irradiation; Transmission electron microscopy; NEUTRON-IRRADIATION; RADIATION-DAMAGE; MOLECULAR-DYNAMICS; W-RE; TRANSMUTATION; TEMPERATURE; BEHAVIOR; RHENIUM; METALS;
D O I
10.1016/j.jnucmat.2023.154239
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
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 W 6 + ) irradiations at 800 degrees 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.
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页数:11
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