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; Yucheng Wu

doi:https://doi.org/10.1016/j.net.2020.05.022

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자료유형: 학술저널

저자정보: Xiao-Yu Ding (Zhejiang University of Technology) Qiu Xu (Kyoto University) Xiao-yong Zhu (Hefei University of Technology) Lai-Ma Luo (Hefei University of Technology) Jian-Jun Huang (Shenzhen University) Bin Yu (Shenzhen University) Xiang Gao (Chinese Academy of Sciences) Jian-Gang Li (Chinese Academy of Sciences) Yucheng Wu (Hefei University of Technology)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제12호

발행연도: 2020.12

수록면: 2,860 - 2,866 (7page)

DOI: https://doi.org/10.1016/j.net.2020.05.022

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Oxide dispersion-strengthened materials W-1wt%Pr2O3 and W-1wt%La2O3 were synthesized by wetchemical 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/m2under 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. At1.0 1020 Heþ/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. Theeffects of pre-irradiation with 1.0 1021 Heþ/m2 on trapping of injected deuterium in doped W wasstudied by thermal desorption spectrometry (TDS) technique using quadrupole mass spectrometer. Compared with the samples without Heþ pre-irradiation, deuterium (D) retention of doped W materialsincreased after Heþ irradiation, whose retention was unsaturated at the damage level of 1.0 1022D2þ/m2.The present results implied that irradiation effect of Heþ ions must be taken into account to evaluate thedeuterium retention in fusion material applications

#Oxide dispersion-strengthened #Pre-irradiation #Microstructure evolution #Heþ ions #Deuterium retention

참고문헌 (17)

참고문헌 신청

A. Xu / 2017 / Ion-irradiation induced clustering in W-Re-Ta, W-Re and W-Ta alloys: an atom probe tomography and nanoindentation study / Acta Mater 124:71~78

X. X. Hu / 2016 / Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation / J. Nucl. Mater 470:278~289

S. J. Zinkle / 2014 / Designing radiation resistance in materials for fusion energy / Annu. Rev. Mater. Res 44(1):241~267

T. Toyama / 2018 / Deuterium trapping at vacancy clusters in electron/neutron-irradiated tungsten studied by positron annihilation spectroscopy / J. Nucl. Mater 499:464~470

O. El-Atwani / 2018 / Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: microstructure, effect of dpa rate, temperature, and grain size / Acta Mater 149:206~219

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