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

宮澤 健; 菊池 裕太*; 安堂 正己*; Yu, J.-H.*; 藪内 聖皓*; 野澤 貴史*; 谷川 博康*; 野上 修平*; 長谷川 晃*

Journal of Nuclear Materials, 575, p.154239_1 - 154239_11, 2023/03

https://doi.org/10.1016/j.jnucmat.2023.154239

This study examined the effects of alloying elements such as Re and Ta on the microstructural evolution of recrystallized W under proton and self-ion irradiations at 800C. Although the number density of voids increased with increasing proton-induced damage level, the void density in W-Re and W-Ta alloys were lower than that of pure W. Herein, the addition of Re and Ta to W suppresses the void formation process. In the proton-irradiated W-3%Re, 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 have already evolved into the tangled dislocations. Solute Re may inhibit the mobility of small dislocation loops and SIA clusters. In W-3%Ta 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 to 0.2 dpa, not only dislocation loops but also voids and rafts were observed in pure W to 0.2 dpa. The solute Re would suppress the raft formation and then the void formation under self-ion irradiation.

耐熱合金と炭火ホウ素との両立性(4) OGL-1照射下両立性試験報告(81LM-21J)

馬場 信一; 猿田 徹; 大岡 紀一; 田中 勲; 青山 功

JAERI-M 85-088, 39 Pages, 1985/07

JAERI-M-85-088.pdf:2.94MB

本報告は、日本原子力研究所が開発研究を進めている高温ガス実験炉の制御棒用被覆管材料と中性子吸収体との照射下両立性試験に関するものである。この試験の主な目的は、照射下で被覆管材料(ハステロイXR合金)と中性子吸収体(BC/C)との反応侵食挙動を調べること、および高融点金属箔(Nb、Mo、W、Re)の反応障壁効果を確認することである。照射は材料試験炉のOGL-1において熱中性子(E 0.11aJ)が410m、高速中性子(E 0.16pJ)は6.410、雰囲気のへリウムガス温度が平均855C、またヘリウムガス中の不純物濃度が4.0vpm以下、気体状核分裂生成物濃度が400kBg/m以下の試験条件で5Msの時間にわたり行われた。照射後試験の結果、ハステロイXR合金の反応侵食形態は局部的な領域に楕円形状の反応生成物が見られたが、これは炉外試験の結果と同様であった。本試験の中性子照射量では顕著な照射効果は表われなかったが、試料部の発熱による合金の反応侵食深さの加速化が観察された。