TY - JOUR
T1 - Synergistic effects of high energy helium irradiation and damage introduction at high temperature on hydrogen isotope retention in plasma facing materials
AU - Sun, F.
AU - Nakata, M.
AU - Lee, S. E.
AU - Zhao, M.
AU - Wada, T.
AU - Yamazaki, S.
AU - Koike, A.
AU - Kondo, S.
AU - Hinoki, T.
AU - Hara, M.
AU - Oya, Y.
N1 - Funding Information:
This study was supported by the Joint Usage/Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University ( ZE31A-30 ); and National Institue for Fusion Science-University of Toyama Bilateral Collaboration Project ( NIFS19KUHR054 ).
Publisher Copyright:
© 2020 Elsevier B.V.
PY - 2020/5
Y1 - 2020/5
N2 - In this study, energetic helium (He) ion irradiation was performed to obtain bulk He distribution in tungsten (W) materials, concurrent with damage introduction at high temperature. Then, deuterium (D) implantation and thermal desorption spectrometry were performed to evaluate D retention. At the same time, the surface tritium (T) concentration and depth distribution were evaluated by imaging plate (IP) and β-ray induced X-ray spectroscopy (BIXS) measurements after mixed D-T gas exposure. Numerical simulations were applied to evaluate changes in binding energies, diffusion depths, and trapping sites under different irradiation conditions. The results showed that weak trapping sites with higher concentration, such as vacancies, were produced during only energetic He+ irradiation events, leading to enhancement of D retention. Fe3+-He+ simultaneous irradiation promoted the formation of HexVy complexes, which reduced the concentration of vacancy trapping sites and changed the stress field around defects, leading to the suppression of D trapping behavior. From the reduced effects of D retention caused by HexVy complexes at higher temperatures, the results suggested that defect recovery was the dominant mechanism. With increasing damage level at higher temperatures, more weak trapping sites, such as dislocations and vacancies sites, were produced, leading to a more dominant influence on D retention than HexVy complex effects. It was also found that HexVy complexes prevented D diffusion to the bulk and that simulation results showed that the damage level had little impact on D diffusion depth.
AB - In this study, energetic helium (He) ion irradiation was performed to obtain bulk He distribution in tungsten (W) materials, concurrent with damage introduction at high temperature. Then, deuterium (D) implantation and thermal desorption spectrometry were performed to evaluate D retention. At the same time, the surface tritium (T) concentration and depth distribution were evaluated by imaging plate (IP) and β-ray induced X-ray spectroscopy (BIXS) measurements after mixed D-T gas exposure. Numerical simulations were applied to evaluate changes in binding energies, diffusion depths, and trapping sites under different irradiation conditions. The results showed that weak trapping sites with higher concentration, such as vacancies, were produced during only energetic He+ irradiation events, leading to enhancement of D retention. Fe3+-He+ simultaneous irradiation promoted the formation of HexVy complexes, which reduced the concentration of vacancy trapping sites and changed the stress field around defects, leading to the suppression of D trapping behavior. From the reduced effects of D retention caused by HexVy complexes at higher temperatures, the results suggested that defect recovery was the dominant mechanism. With increasing damage level at higher temperatures, more weak trapping sites, such as dislocations and vacancies sites, were produced, leading to a more dominant influence on D retention than HexVy complex effects. It was also found that HexVy complexes prevented D diffusion to the bulk and that simulation results showed that the damage level had little impact on D diffusion depth.
KW - Fusion
KW - Helium
KW - Hydrogen isotope
KW - Irradiation damages
KW - Simulation
KW - Tungsten
UR - http://www.scopus.com/inward/record.url?scp=85081955745&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85081955745&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2020.152122
DO - 10.1016/j.jnucmat.2020.152122
M3 - Article
AN - SCOPUS:85081955745
SN - 0022-3115
VL - 533
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 152122
ER -