TY - CHAP
T1 - Effect of Damage Introduction and He Existence on D Retention in Tungsten by High Flux D Plasma Exposure
AU - Oya, Yasuhisa
AU - Azuma, Keisuke
AU - Togari, Akihiro
AU - Nakata, Moeko
AU - Zhou, Qilai
AU - Zhao, Mingzhong
AU - Kuwabara, Tatsuya
AU - Ohno, Noriyasu
AU - Yajima, Miyuki
AU - Hatano, Yuji
AU - Toyama, Takeshi
N1 - Funding Information:
Acknowledgements. This work was performed under the Inter-University Cooperative Research Program of the Institute for Materials Research, Tohoku University (Proposal No. 18M0023) and with the support and under the auspices of the NIFS Collaboration Research program (NIFS17KNWF003). This study was also supported by KAKENHI, 18H03688.
PY - 2019
Y1 - 2019
N2 - Both of radiation-induced damages and helium (He) existence effects on deuterium (D) retention in tungsten (W) by D plasma exposure were evaluated using high flux divertor plasma exposure device, called Compact Divertor Plasma Simulator (CDPS). The results were compared with 3 keV D 2 + implanted W with low flux and fluence. The thermal desorption spectra were consisted of three desorption stages at 400, 600, 780 K. Comparing to the undamaged W, the D desorption stages were shifted towards higher temperature side and the values of D retention increased. It can be said that the formation of stable trapping sites by damage introduction enhances the D trapping in the damaged W. For He + irradiation, D desorption at lower temperature was enhanced, due to the formation of dense dislocation loops. In case of sequential Fe 2+ and He + implantation, D desorption at higher temperature was reduced, comparing to that for only Fe 2+ damaged W. These facts show that the accumulation of He near surface region reduces D diffusion toward bulk, leading to the reduction of D trapping by voids.
AB - Both of radiation-induced damages and helium (He) existence effects on deuterium (D) retention in tungsten (W) by D plasma exposure were evaluated using high flux divertor plasma exposure device, called Compact Divertor Plasma Simulator (CDPS). The results were compared with 3 keV D 2 + implanted W with low flux and fluence. The thermal desorption spectra were consisted of three desorption stages at 400, 600, 780 K. Comparing to the undamaged W, the D desorption stages were shifted towards higher temperature side and the values of D retention increased. It can be said that the formation of stable trapping sites by damage introduction enhances the D trapping in the damaged W. For He + irradiation, D desorption at lower temperature was enhanced, due to the formation of dense dislocation loops. In case of sequential Fe 2+ and He + implantation, D desorption at higher temperature was reduced, comparing to that for only Fe 2+ damaged W. These facts show that the accumulation of He near surface region reduces D diffusion toward bulk, leading to the reduction of D trapping by voids.
KW - He bubble formation
KW - Hydrogen isotopes
KW - Irradiation damages
UR - http://www.scopus.com/inward/record.url?scp=85063140150&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85063140150&partnerID=8YFLogxK
U2 - 10.1007/978-3-319-99834-3_12
DO - 10.1007/978-3-319-99834-3_12
M3 - Chapter
AN - SCOPUS:85063140150
T3 - Lecture Notes in Networks and Systems
SP - 89
EP - 96
BT - Lecture Notes in Networks and Systems
PB - Springer
ER -