Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation

Xiao-Yu Ding; Qiu Xu; Xiao-yong Zhu; Lai-Ma Luo; Jian-Jun Huang; Bin Yu; Xiang Gao; Jian-Gang Li; Yu-Cheng Wu

Nuclear Engineering and Technology (Dec 2020)

Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation

Xiao-Yu Ding,
Qiu Xu,
Xiao-yong Zhu,
Lai-Ma Luo,
Jian-Jun Huang,
Bin Yu,
Xiang Gao,
Jian-Gang Li,
Yu-Cheng Wu

Affiliations

Xiao-Yu Ding: Institute of Laser Advanced Manufacturing, Zhejiang University of Technology, Hangzhou, 310014, China; Key Laboratory of Optoelectronic Devices and Systems of Ministry of Education and Guangdong Province, College of Optoelectronic Engineering, Shenzhen University, Shenzhen, 518060, China; Institute of Laser, Advanced Manufacturing, Zhejiang University of Technology, Hangzhou, 310014, China
Qiu Xu: Institute for Integrated Radiation and Nuclear Science, Kyoto University, Osaka-fu, 590-0494, Japan
Xiao-yong Zhu: School of Materials Science and Engineering, Hefei University of Technology, Hefei, 230009, China; Key Laboratory of Advanced Functional Materials and Devices of Anhui Province, Hefei, 230009, China; National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei, 230009, China
Lai-Ma Luo: School of Materials Science and Engineering, Hefei University of Technology, Hefei, 230009, China; Key Laboratory of Advanced Functional Materials and Devices of Anhui Province, Hefei, 230009, China; National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei, 230009, China
Jian-Jun Huang: Key Laboratory of Optoelectronic Devices and Systems of Ministry of Education and Guangdong Province, College of Optoelectronic Engineering, Shenzhen University, Shenzhen, 518060, China
Bin Yu: Key Laboratory of Optoelectronic Devices and Systems of Ministry of Education and Guangdong Province, College of Optoelectronic Engineering, Shenzhen University, Shenzhen, 518060, China
Xiang Gao: Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, China
Jian-Gang Li: Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, China
Yu-Cheng Wu: School of Materials Science and Engineering, Hefei University of Technology, Hefei, 230009, China; Key Laboratory of Advanced Functional Materials and Devices of Anhui Province, Hefei, 230009, China; National-Local Joint Engineering Research Centre of Nonferrous Metals and Processing Technology, Hefei, 230009, China; Corresponding author. School of Materials Science and Engineering, Hefei University of Technology, Hefei, 230009, China.

Journal volume & issue: Vol. 52, no. 12
pp. 2860 – 2866

Abstract

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Oxide dispersion-strengthened materials W-1wt%Pr2O3 and W-1wt%La2O3 were synthesized by wet chemical method and spark plasma sintering. The field emission scanning electron microscopy (FE-SEM) analysis, XRD and Vickers microhardness measurements were conducted to characterize the samples. The irradiations were carried out with a 5 keV helium ion beam to fluences up to 5.0 × 1021 ions/m2 under 600 °C using the low-energy ion irradiation system. Transmission electron microscopy (TEM) study was performed to investigate the microstructural evolution in W-1wt%Pr2O3 and W-1wt%La2O3. At 1.0 × 1020 He+/m2, the average loops size of the W-1wt%Pr2O3 was 4.3 nm, much lower than W-1wt%La2O3 of 8.5 nm. However, helium bubbles were not observed throughout in both doped W materials. The effects of pre-irradiation with 1.0 × 1021 He+/m2 on trapping of injected deuterium in doped W was studied by thermal desorption spectrometry (TDS) technique using quadrupole mass spectrometer. Compared with the samples without He+ pre-irradiation, deuterium (D) retention of doped W materials increased after He+ irradiation, whose retention was unsaturated at the damage level of 1.0 × 1022D2+/m2. The present results implied that irradiation effect of He+ ions must be taken into account to evaluate the deuterium retention in fusion material applications.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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