Effect of neutron energy and fluence on deuterium retention behaviour in neutron irradiated tungsten

Fujita, Hideyuki; Yuyama, Kenta; Li, Xiao-Chun; Hatano, Yuji; Toyama, Takeshi; Ohta, M.; Ochiai, Kentaro; Yoshida, N.; Chikada, Takumi; Oya, Yasuhisa

doi:10.1088/0031-8949/t167/1/014068

Cited by 32 publications

(8 citation statements)

References 12 publications

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“…TDS measurements immediately performed after the plasma exposure showed a significant increase in the retention of deuterium in the neutron-irradiated tungsten samples. This increase in deuterium retention is due to the generation of displacement-damaged defects over the entire thickness of the samples [8][9][10][11][12][13][14][15][16][17][18]. Positron lifetime measurements performed in the previous study [18] showed that the neutron irradiation at around 563 K resulted in the formation of vacancies and vacancy clusters as large as V 10 .…”

Section: Resultsmentioning

confidence: 93%

“…As a potential material for PFCs in future fusion reactors, tungsten will be subjected to intensive fluxes of energetic deuterium and tritium and 14 MeV neutrons. Neutron irradiation generates displacements in the tungsten bulk and thus creates defects at which hydrogen isotopes are trapped [8][9][10][11][12][13][14][15][16][17][18]. One of the possible tritium removal methods is to heat the PFCs after the deuterium-tritium operation using the decay heat generated by the radioisotopes that appear in the PFCs due to neutron irradiation.…”

Section: Introductionmentioning

confidence: 99%

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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: Resultsmentioning

confidence: 93%

Section: Introductionmentioning

confidence: 99%

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

et al. 2020

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“…Interest in tungsten (W) metal is seeing a resurgence owing to its high sputtering threshold [1], low tritium retention [2,3], and high temperature resistance [4], all of which make it extremely attractive as a plasma facing material in nuclear fusion reactors [5,6]. Additionally, tungsten forms the base of many technologies in a range of industrial fields, with tungsten oxides being widely used for their electronic, photoabsorption, optical, and catalytic properties [7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Lifetime effects and satellites in the photoelectron spectrum of tungsten metal

et al. 2022

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Tungsten (W) is an important and versatile transition metal and has a firm place at the heart of many technologies. A popular experimental technique for the characterization of tungsten and tungsten-based compounds is x-ray photoelectron spectroscopy (XPS), which enables the assessment of chemical states and electronic structure through the collection of core level and valence band spectra. However, in the case of tungsten metal, open questions remain regarding the origin, nature, and position of satellite features that are prominent in the photoelectron spectrum. These satellites are a fingerprint of the electronic structure of the material and have not been thoroughly investigated, at times leading to their misinterpretation. The present work combines high-resolution soft and hard x-ray photoelectron spectroscopy (SXPS and HAXPES) with reflected electron energy loss spectroscopy (REELS) and a multitiered ab initio theoretical approach, including density functional theory (DFT) and many-body perturbation theory (G0W0 and GW + C), to disentangle the complex set of experimentally observed satellite features attributed to the generation of plasmons and interband transitions. This combined experiment-theory strategy is able to uncover previously undocumented satellite features, improving our understanding of their direct relationship to tungsten's electronic structure. Furthermore, it lays the groundwork for future studies into tungsten-based mixed-metal systems and holds promise for the reassessment of the photoelectron spectra of other transition and post-transition metals, where similar questions regarding satellite features remain.

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“…It can be seen that there are two D desorption peaks around 600 K and 800 K, which are marked as peak 1 and peak 2 in the following discussion. According to references [31][32][33], peak 1 and peak 2 are correlated to the desorption of D trapped at dislocationtype defects and in vacancy-type defects, respectively. Comparing the D desorption peak in figures 5(a) and (b), it can be clearly found that the D desorption peak completely disappeared after He irradiation.…”

Section: Reduction Of D Penetration Into the Bulkmentioning

confidence: 99%

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

Zhou

Liu

et al. 2022

Nucl. Fusion

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Experiments concerning the effect of helium (He) plasma exposure on deuterium (D) plasma-driven permeation (PDP) through tungsten (W) foils in a linear plasma facility has been performed. 0.05 mm thick W foils were exposed to ~2×1020 m-2s-1 He plasma with various fluences at 883 K. After He irradiating, D permeation tests were performed for the samples and retention was also measured by high-resolution thermal desorption spectroscopy (TDS). It was observed that He pre-irradiation resulted in a significant reduction of D permeation and retention in W. Microstructure observation indicated that the surfaces of samples after He irradiation turned rough and He nanobubbles were formed near the surface. The defective structure including He nanobubbles very likely enhances D reemission and accordingly reduces the permeation and retention in He pre-irradiated W.

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Effect of neutron energy and fluence on deuterium retention behaviour in neutron irradiated tungsten

Cited by 32 publications

References 12 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

Lifetime effects and satellites in the photoelectron spectrum of tungsten metal

In situ measurements of low energy D plasma-driven permeation through He pre-damaged W

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