Numerical analysis of deuterium migration behaviors in tungsten damaged by fast neutron by means of gas absorption method

Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at 918 K and 0.74 dpa at 1079 K) and 6.4 MeV Fe2+ (0.3 dpa at R.T.) were investigated to evaluate the tritium retention property of fusion reactor divertors. A deuterium gas absorption method was carried...

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Bibliographic Details
Published in:Fusion engineering and design 2021-07, Vol.168 (C), p.112635, Article 112635
Main Authors: Kobayashi, Makoto I, Shimada, Masashi, Taylor, Chase N, Nobuta, Yuji, Hatano, Yuji, Oya, Yasuhisa
Format: Article
Language:English
Subjects:
Absorption
Damage
Desorption
Deuterium
Divertor
Divertors (fusion reactors)
Fast neutrons
Gas absorption
High temperature
Hydrogen isotopes
Neutron
Neutron irradiation
Neutrons
Numerical analysis
Retention
Spectrum analysis
TDS
Thermal desorption spectroscopy
Trapping
Tritium
Tungsten
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Summary:Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at 918 K and 0.74 dpa at 1079 K) and 6.4 MeV Fe2+ (0.3 dpa at R.T.) were investigated to evaluate the tritium retention property of fusion reactor divertors. A deuterium gas absorption method was carried out to avoid additional damage that may be induced by plasma exposure, then, deuterium retention and desorption behaviors were investigated quantitatively by means of thermal desorption spectroscopy and the following simulation code. The deuterium desorption spectra for tungsten samples were analyzed by the numerical code which includes the elementary steps of hydrogen isotope migration processes including diffusion, trapping, detrapping, and surface recombination. The evaluated deuterium detrapping energy from the irradiation defects in neutron irradiated tungsten sample was larger than that in 6.4 MeV Fe2+ irradiated tungsten. It was suggested that the dominant deuterium trapping site in the neutron irradiated tungsten would be voids which was formed by the accumulation of vacancies during neutron irradiation under high temperature and long duration.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2021.112635