抄録
To study the D2 retention behavior of W–ZrC/Sc2O3 composites, mirror-polished samples prepared by spark plasma sintering (SPS) were exposed to different irradiation doses at room temperature (RT). TDS measurements were subsequently performed from RT to 900 K. Results revealed that Sc2O3 particles did not benefit the D2 + ion irradiation resistance, whereas W–1vol% ZrC/2 vol% Sc2O3 composites showed superior irradiation resistance over other samples. D2 implantation was also performed at 523 K with the irradiation dose of 1 × 1020 D2 +/m2 to study the influence of temperature on D2 retention during the capture process, which could apparently decrease D2 retention by low-energy traps. Only small dislocation loops or precipitates were observed in W–1vol% ZrC/2 vol% Sc2O3 sample after irradiation up to 1.0✕1021 D2 +/m2.
本文言語 | 英語 |
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論文番号 | 103215 |
ジャーナル | Progress in Nuclear Energy |
巻 | 120 |
DOI | |
出版ステータス | 出版済み - 2月 2020 |
!!!All Science Journal Classification (ASJC) codes
- 原子力エネルギーおよび原子力工学
- 安全性、リスク、信頼性、品質管理
- エネルギー工学および電力技術
- 廃棄物管理と処理