The Influence of Microstructure on Deuterium Retention in Polycrystalline Tungsten

Garrison, Lauren M.; Meyer, F. W.; Bannister, M. E.

doi:10.1080/15361055.2017.1352431

Cited by 3 publications

(1 citation statement)

References 19 publications

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“…Although W lacks the formation of stable hydrides, tritium fluxes as high as 10 24 m −2 s −1 are expected on the DEMO 5 divertor [1,2], potentially leading to severe surface blistering [3][4][5][6][7], cracking [8], hydrogen embrittlement [9,10], as well as creating safety and waste disposal concerns [11]. Retention of tritium (T), deuterium (D), or hydrogen (H) in as-fabricated W specimens is highly dependent on synthesis, thermal history, and intrinsic microstructure [12][13][14][15][16]. Understanding T/D/H retention in plasmafacing components is critical, as the viability of a D-T fusion energy source relies on the ability to breed sufficient T fuel for self-sustaining operation.…”

Section: Introductionmentioning

confidence: 99%

Understanding hydrogen retention in damaged tungsten using experimentally-guided models of complex multispecies evolution

Simmonds

Doerner

et al. 2020

Nucl. Fusion

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Fuel retention in plasma facing tungsten components is a critical phenomenon affecting the mechanical integrity and radiological safety of fusion reactors. It is known that hydrogen can become trapped in small defect clusters, internal surfaces, dislocations, and/or impurities, and so it is common practice to seed W subsurfaces with irradiation defects in an attempt to precondition the system to absorb hydrogen. The amount of H can later be tallied by performing careful thermal desorption tests where released temperature peaks are mapped to specific binding energies of hydrogen to defect clusters and/or microstructural features of the material. While this provides useful information about the potential trapping processes, modeling can play an important role in elucidating the detailed microscopic mechanisms that lead to hydrogen retention in damaged tungsten. In this paper, we develop a detailed kinetic model of hydrogen penetration and trapping inspired by recent experiments combining ion irradiation, hydrogen plasma exposure, and thermal desorption. We use the stochastic cluster dynamics method to solve the system of coupled partial differential equations representing the mean field description of the multispecies system. The model resolves the spatial distribution of defects and hydrogen clusters during the three processes carried out experimentally and is parameterized with information from atomistic calculations. We find that the calculated thermal desorption spectra are broadly characterized by three H emission regions: (i) a low temperature one where dislocations are the main contributors to the release peaks; (ii) an intermediate one governed by hydrogen release from small overpressurized clusters with multiple overlapping peaks, and (iii) a high temperature one defined by clean isolated emission peaks from large underpressurized bubbles. These three temperature intervals are seen to largely correlate with the depth at which the clusters are found. The relevance of the ‘super abundant’ vacancy mechanism is assessed, finding that its main role is to transfer more clusters from the intermediate to the high temperature regions as its relevance increases. We find this picture to be in very good agreement with the experiments, adding confidence to the predictive potential of the models and their useto understand irradiation damage and plasma exposure effects in plasma facing components.

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