Abstract
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.
| Original language | English |
|---|---|
| Article number | 103215 |
| Journal | Progress in Nuclear Energy |
| Volume | 120 |
| DOIs | |
| Publication status | Published - Feb 2020 |
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All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Safety, Risk, Reliability and Quality
- Energy Engineering and Power Technology
- Waste Management and Disposal
Cite this
Deuterium irradiation resistance and relevant mechanism in W–ZrC/Sc2O3 composites prepared by spark plasma sintering. / Yao, Gang; Chen, Hong Yu; Fu, Ming Qi; Luo, Lai Ma; Zan, Xiang; Xu, Qiu; Tokunaga, Kazutoshi; Zhu, Xiao Yong; Wu, Yu Cheng.
In: Progress in Nuclear Energy, Vol. 120, 103215, 02.2020.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Deuterium irradiation resistance and relevant mechanism in W–ZrC/Sc2O3 composites prepared by spark plasma sintering
AU - Yao, Gang
AU - Chen, Hong Yu
AU - Fu, Ming Qi
AU - Luo, Lai Ma
AU - Zan, Xiang
AU - Xu, Qiu
AU - Tokunaga, Kazutoshi
AU - Zhu, Xiao Yong
AU - Wu, Yu Cheng
PY - 2020/2
Y1 - 2020/2
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85075190532&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85075190532&partnerID=8YFLogxK
U2 - 10.1016/j.pnucene.2019.103215
DO - 10.1016/j.pnucene.2019.103215
M3 - Article
AN - SCOPUS:85075190532
VL - 120
JO - Progress in Nuclear Energy
JF - Progress in Nuclear Energy
SN - 0149-1970
M1 - 103215
ER -