Deuterium irradiation resistance and relevant mechanism in W–ZrC/Sc2O3 composites prepared by spark plasma sintering

Gang Yao; Hong Yu Chen; Ming Qi Fu; Lai Ma Luo; Xiang Zan; Qiu Xu; Kazutoshi Tokunaga; Xiao Yong Zhu; Yu Cheng Wu

doi:10.1016/j.pnucene.2019.103215

Deuterium irradiation resistance and relevant mechanism in W–ZrC/Sc₂O₃ composites prepared by spark plasma sintering

Gang Yao, Hong Yu Chen, Ming Qi Fu, Lai Ma Luo, Xiang Zan, Qiu Xu, Kazutoshi Tokunaga, Xiao Yong Zhu, Yu Cheng Wu

Division of Nuclear Fusion Dynamics

Research output: Contribution to journal › Article › peer-review

2 Citations (Scopus)

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	https://doi.org/10.1016/j.pnucene.2019.103215
Publication status	Published - Feb 2020

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering
Safety, Risk, Reliability and Quality
Energy Engineering and Power Technology
Waste Management and Disposal

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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 › peer-review

@article{d23fcb205595488ca0fffa752facbfe1,

title = "Deuterium irradiation resistance and relevant mechanism in W–ZrC/Sc2O3 composites prepared by spark plasma sintering",

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.",

author = "Gang Yao and Chen, {Hong Yu} and Fu, {Ming Qi} and Luo, {Lai Ma} and Xiang Zan and Qiu Xu and Kazutoshi Tokunaga and Zhu, {Xiao Yong} and Wu, {Yu Cheng}",

note = "Funding Information: This work was supported by the National Key Research and Development Program of China (No.2017YFE0302600), the State Key Laboratory of Powder Metallurgy, the Foundation of Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province (15CZS08031), and the 111 Project (B18018). Funding Information: This work was supported by the National Key Research and Development Program of China (No. 2017YFE0302600 ), the State Key Laboratory of Powder Metallurgy , the Foundation of Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province ( 15CZS08031 ), and the 111 Project ( B18018 ). Appendix A ",

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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

N1 - Funding Information: This work was supported by the National Key Research and Development Program of China (No.2017YFE0302600), the State Key Laboratory of Powder Metallurgy, the Foundation of Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province (15CZS08031), and the 111 Project (B18018). Funding Information: This work was supported by the National Key Research and Development Program of China (No. 2017YFE0302600 ), the State Key Laboratory of Powder Metallurgy , the Foundation of Laboratory of Nonferrous Metal Material and Processing Engineering of Anhui Province ( 15CZS08031 ), and the 111 Project ( B18018 ). Appendix A

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.

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