Open AccessDeuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing
Author(s) -
V.Kh. Alimov,
Yuji Hatano,
T. Kuwabara,
Takeshi Toyama,
Youji Someya,
А. В. Спицын
Publication year - 2020
Publication title -
nuclear fusion
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.774
H-Index - 120
eISSN - 1741-4326
pISSN - 0029-5515
DOI - 10.1088/1741-4326/aba337
Subject(s) - deuterium , tungsten , materials science , irradiation , radiochemistry , annealing (glass) , neutron , analytical chemistry (journal) , fluence , chemistry , atomic physics , nuclear physics , physics , chromatography , metallurgy
We examine the effect of neutron irradiation on the release of deuterium from tungsten at 573 K to understand the efficiency of tritium removal by baking out at moderate temperatures. Tungsten samples, undamaged and neutron-irradiated to a damage level of approximately 0.016 displacements per atom, are exposed to low-energy (108 eV), high-flux (3.0 × 10 21 to 9.4 × 10 21 m −2 s −1 ) deuterium plasma at temperatures ranging from 573 to 773 K to an ion fluence of 1.1 × 10 25 m −2 . At each exposure temperature, two undamaged and two neutron-irradiated tungsten samples are exposed to plasma. The deuterium content in the tungsten samples is measured by thermal desorption spectrometry soon after the plasma exposure and after post-plasma annealing at 573 K for 30 h. It is found that: (i) the deuterium retention in the neutron-irradiated tungsten samples is significantly higher than that in the undamaged tungsten samples; (ii) annealing at 573 K of undamaged tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to an almost complete (60%–99%) release of deuterium from the samples; (iii) annealing at 573 K of neutron-irradiated tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to a significant (8%–20%) release of deuterium from the samples.