Synergy of plastic deformation and gas retention in tungsten

Terentyev, D.; Temmerman, G. De; Minov, Boris; Zayachuk, Y.; Lambrinou, Konstantina; Morgan, T.W.; Dubinko, A.; Bystrov, K.; Oost, G. Van

doi:10.1088/0029-5515/55/1/013007

Cited by 27 publications

(8 citation statements)

References 21 publications

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“…Thermal drifts were below 0.05 nm s −1 . The black spectrum reveals two peaks, one around 510 K and one around 760 K, consistent with previous studies on deuterium retention in tungsten [19,58,59]. The trapping density and trapping energy are estimated by matching the TMAP7 simulation to the experimental data.…”

Section: Spherical Nanoindentationsupporting

confidence: 85%

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Morgan

Terentyev

et al. 2020

Nucl. Fusion

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Section: Spherical Nanoindentationsupporting

confidence: 85%

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Morgan

Terentyev

et al. 2020

Nucl. Fusion

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“…This work is a continuation of our recent study addressing the role played by heavy plastic deformation on D retention and surface microstructure evolution [13][14][15]. Those works have demonstrated that plastically induced dislocation network enhances deuterium retention and amplifies the release stage around 450-600 K. Here, we provide the microstructural characterizatization of nano-and micro-scale defects that appeared as a result of plasma exposure.…”

Section: Introductionmentioning

confidence: 71%

Microstructural modifications in tungsten induced by high flux plasma exposure: TEM examination

et al. 2016

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We have performed microstructural characterization using transmission electron microscopy (TEM) techniques to reveal nanometric features in the sub-surface region of tungsten samples exposed to high flux, low energy deuterium plasma. TEM examination revealed formation of a dense dislocation network and dislocation tangles, overall resulting in a strong increase in the dislocation density by at least one order of magnitude as compared to the initial one. Plasmainduced dislocation microstructure vanishes beyond a depth of about 10 μm from the top of the exposed surface where the dislocation density and its morphology becomes comparable to the reference microstructure. Interstitial edge dislocation loops with Burgers vector a 0 /2〈111〉 and a 0 〈100〉 were regularly observed within 6 μm of the sub-surface region of the exposed samples, but absent in the reference material. The presence of these loops points to a co-existence of nanometric D bubbles, growing by loop punching mechanism, and sub-micron deuterium flakes, resulting in the formation of surface blisters, also observed here by scanning electron microscopy.S Online supplementary data available from stacks.iop.org/PSTOP/T167/014030/mmedia

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“…Our earlier works have shown that the initial dislocation density plays a very important role in the trapping and release of hydrogen and helium in W studied under ITER-relevant plasma exposure conditions [27][28][29][30] . The initial dislocation network creates additional trapping sites and promotes strong trapping, which should be seen as a negative impact.…”

Section: Introductionmentioning

confidence: 98%

Effect of statistically stored dislocations in tungsten on the irradiation induced nano-hardening analyzed by different methods

Bonny

Khvan

Bakaeva

et al. 2021

Journal of Nuclear Materials

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Tungsten self-ion irradiation was performed at 800 °C up to 0.01-1 dpa on two different W grades with essentially different dislocation density. Nanoindentation was applied to characterize the radiation hardening in two W grades with different microstructure. Different methods to analyze the indentation curves were applied to extract the bulk equivalent radiation hardening. It was shown that depending on the applied method, different outcomes may occur. The most satisfactory procedure was established and a consistent set of parameters was found. The bulk equivalent radiation hardening was found to saturate above 0.1 dpa. The characteristic distance between irradiation induced defects acting as dislocation pinning points was found to decrease up to 0.1 dpa, and then saturate/increase with irradiation dose. No essential difference in radiation hardening was observed between the studied W grades with essentially different initial dislocation density.

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Synergy of plastic deformation and gas retention in tungsten

Cited by 27 publications

References 21 publications

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Microstructural modifications in tungsten induced by high flux plasma exposure: TEM examination

Effect of statistically stored dislocations in tungsten on the irradiation induced nano-hardening analyzed by different methods

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