TY - JOUR
T1 - Penetration of deuterium into neutron-irradiated tungsten under plasma exposure
AU - Yajima, Miyuki
AU - Hatano, Yuji
AU - Alimov, Vladimir Kh
AU - Toyama, Takeshi
AU - Kuwabara, Tatsuya
AU - Schwarz-Selinger, Thomas
AU - Oya, Yasuhisa
AU - Spitsyn, Alexander V.
AU - Ohno, Noriyasu
N1 - Funding Information:
Original content from this work may be used under the terms of the . Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI. Japan-Russia Research Cooperative Program between JSPS and RFBR JPJSBP120204808 RFBR#20-58-50005 Japan Society for the Promotion of Science Kakenhi JP18H03688 GIMRT Program of the Institute for Materials Research, Tohoku University 202012-IRKMA-0509 202012-IRKMA-0510 yes � 2021 The Author(s). Published by IOP Publishing Ltd Creative Commons Attribution 4.0 licence
Publisher Copyright:
© 2021 The Author(s). Published by IOP Publishing Ltd.
PY - 2021/12
Y1 - 2021/12
N2 - Hydrogen isotope trapping at lattice defects in neutron-irradiated tungsten (W), a leading candidate as plasma facing material, is an important problem determining tritium (T) inventory in a vacuum vessel of a future fusion reactor. In this study, W samples were irradiated with neutrons in the Belgium Reactor 2 at 563 K to 0.06 or 0.016 displacement per atom (dpa). After characterizing defects by positron lifetime measurements, deuterium (D) penetration under exposure to D plasma was examined at 563-773 K. Positron lifetime showed the presence of dislocations, monovacancies and relatively large vacancy clusters. These defects trapped D atoms with different values of binding energy. Dependence of D retention on plasma exposure temperature and damage level indicated that the concentrations of weak traps with smaller binding energy increased more significantly with damage level than those of strong traps.
AB - Hydrogen isotope trapping at lattice defects in neutron-irradiated tungsten (W), a leading candidate as plasma facing material, is an important problem determining tritium (T) inventory in a vacuum vessel of a future fusion reactor. In this study, W samples were irradiated with neutrons in the Belgium Reactor 2 at 563 K to 0.06 or 0.016 displacement per atom (dpa). After characterizing defects by positron lifetime measurements, deuterium (D) penetration under exposure to D plasma was examined at 563-773 K. Positron lifetime showed the presence of dislocations, monovacancies and relatively large vacancy clusters. These defects trapped D atoms with different values of binding energy. Dependence of D retention on plasma exposure temperature and damage level indicated that the concentrations of weak traps with smaller binding energy increased more significantly with damage level than those of strong traps.
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U2 - 10.1088/1402-4896/ac2c20
DO - 10.1088/1402-4896/ac2c20
M3 - Article
AN - SCOPUS:85118580736
SN - 0031-8949
VL - 96
JO - Physica Scripta
JF - Physica Scripta
IS - 12
M1 - 124042
ER -