Surface morphology and deuterium retention in tungsten and tungsten–rhenium alloy exposed to low-energy, high flux D plasma

Alimov, V.Kh.; Hatano, Yuji; Sugiyama, K.; Balden, M.; Oyaidzu, M.; Akamaru, Satoshi; Tada, Kohei; Kurishita, Hiroaki; Hayashi, T.; Matsuyama, Masao

doi:10.1016/j.jnucmat.2014.07.064

Cited by 25 publications

(13 citation statements)

References 28 publications

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“…According to the TDS measurements immediately performed after the plasma exposure, an increase in the exposure temperature from 573 to 773 K led to a decrease in the amount of released deuterium from 3.9 × 10 20 to 4.7 × 10 18 D m −2 (table 2). This decrease in the amount of deuterium correlated well with previously published data on the retention of deuterium in undamaged tungsten samples exposed to low-energy (76 eV), high-flux (about 5 × 10 21 m −2 s −1 ) deuterium plasma [30,31]. The accumulation of deuterium in undamaged polycrystalline hot-rolled tungsten exposed to deuterium plasma with ion energies well below the displacement threshold can be explained by the mechanisms of fracture and/or plastic deformation due to deuterium supersaturation [32].…”

Section: Resultssupporting

confidence: 90%

Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing

et al. 2020

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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 × 1021 to 9.4 × 1021 m−2 s−1) deuterium plasma at temperatures ranging from 573 to 773 K to an ion fluence of 1.1 × 1025 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.

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Section: Resultssupporting

confidence: 90%

Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing

et al. 2020

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“…Recently, a few experimental works have been performed to investigate the influence of solute atoms on the hydrogen retention in tungsten. These experiments clearly showed that the solute atoms can significantly change the hydrogen retention in tungsten [22][23][24][25][26][27][28]. Therefore, the study of solutehydrogen (solute-H) interaction has an important role in the reliable predication of hydrogen recycling and retention in tungsten, particularly in its alloy.…”

Section: First-principles Calculations Of Transition Metal Solute Int...mentioning

confidence: 96%

First-principles calculations of transition metal solute interactions with hydrogen in tungsten

Kong

Liu

et al. 2015

Nucl. Fusion

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We have performed systematic first-principles calculations to predict the interaction between transition metal (TM) solutes and hydrogen in the interstitial site as well as the vacancy in tungsten. We showed that the site preference of the hydrogen atom is significantly influenced by the solute atoms, which can be traced to the charge density perturbation in the vicinity of the solute atom. The solute-H interactions are mostly attractive except for Re, which can be well understood in terms of the competition between the chemical and elastic interactions. The chemical interaction dominates the solute-H interaction for the TM solutes with a large atomic volume and small electronegativity compared to tungsten, while the elastic interaction is primarily responsible for the solute-H interaction for the TM solutes with a small atomic volume and large electronegativity relative to tungsten. The presence of a hydrogen atom near the solute atom has a negative effect on the binding of other hydrogen atoms. The large positive binding energies among the solute, vacancy and hydrogen suggest that they would easily form a defect cluster in tungsten, where the solute-vacancy and vacancy-H interaction contribute greatly while the solute-H interaction contributes a little. Our result provides a sound theoretical explanation for recent experimental phenomena of hydrogen retention in the tungsten alloy and further recommends a suitable W–Re–Ta ternary alloy for possible plasma-facing materials (PFMs) including the consideration of the hydrogen retention.

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“…Further, the vacancy clusters could also act as nucleation sites for the Re/Os clusters, and mediate the diffusion of them, leading to the growth of Re/Os-rich clusters [22]. It is found that Re also has an effect on deuterium (D) in W [26][27][28]. The retention of D is much lower in W-Re than that in W [28], which may be attributed to that Re blocks the nucleation of vacancies by forming a Re-vacancy (Re-V) complex or enhances the recombination between vacancy and self-interstitial atoms (SIAs).…”

Section: Behaviors Of Transmutation Elements Re and Os And Their Effe...mentioning

confidence: 99%

Behaviors of transmutation elements Re and Os and their effects on energetics and clustering of vacancy and self-interstitial atoms in W

Zhou

Jin

et al. 2017

Nucl. Fusion

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We investigate the behaviors of rhenium (Re) and osmium (Os) and their interactions with point defects in tungsten (W) using a first-principles method. We show that Re atoms are energetically favorable to disperse separately in bulk W due to the Re-Re repulsive interaction. Despite the attractive interaction between Os atoms, there is still a large activation energy barrier of 1.10 eV at the critical number of 10 for the formation of Os clusters in bulk W based on the results of the total nucleation free energy change. Interestingly, the presence of vacancy can significantly reduce the total nucleation free energy change of Re/Os clusters, suggesting that vacancy can facilitate the nucleation of Re/Os in W. Re/Os in turn has an effect on the stability of the vacancy clusters (V n ) in W, especially for small vacancy clusters. A single Re/Os atom can raise the total binding energies of V 2 and V 3 obviously, thus enhancing their formation. Further, we demonstrate that there is a strong attractive interaction between Re/Os and self-interstitial atoms (SIAs). Re/Os could increase the diffusion barrier of SIAs and decrease their rotation barrier, while the interstitial-mediated path may be the optimal diffusion path of Re/Os in W. Consequently, the synergistic effect between Re/Os and point defects plays a key role in Re/Os precipitation and the evolution of defects in irradiated W.

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Surface morphology and deuterium retention in tungsten and tungsten–rhenium alloy exposed to low-energy, high flux D plasma

Cited by 25 publications

References 28 publications

Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing

Deuterium release from deuterium plasma-exposed neutron-irradiated and non-neutron-irradiated tungsten samples during annealing

First-principles calculations of transition metal solute interactions with hydrogen in tungsten

Behaviors of transmutation elements Re and Os and their effects on energetics and clustering of vacancy and self-interstitial atoms in W

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