Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions

Sizyuk, Tatyana; Abrams, Tyler

doi:10.1016/j.jnucmat.2022.154095

Dynamics of deuterium retention and desorption from plasma-facing materials in fusion reactor-relevant conditions

Journal Article · Thu Oct 20 00:00:00 EDT 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.154095· OSTI ID:1905307

^[1]; Abrams, Tyler ^[2]

Argonne National Lab. (ANL), Lemont, IL (United States)
General Atomics, San Diego, CA (United States)

Hydrogen isotopes retention and desorption during and after discharges in fusion devices are still not well understood due to the complex device conditions and limitations of in-situ diagnostics and measurements. Here, we simulated well-diagnosed recent experiments at the DIII-D facility to benchmark our ITMC-DYN integrated package of modeling deuterium diffusion, retention, and desorption during and after D discharge irradiation. Modeling results were compared with detail experimental data of D desorption fluxes for various irradiation conditions. We predicted the temporal evolution of free and trapped D distribution in tungsten (W) plasma-facing material (PFM). Effects of key parameters namely diffusion coefficient, recombination rate, trapping energies against different defect types, were examined in these simulations. Existing experimental data of these parameters in literature varies significantly which makes it harder to identify key mechanisms and physics responsible for hydrogen isotope retention and desorption. The purpose of this work is to accurately simulate recent well-diagnosed reactor experiments given the uncertainties in such parameters and identify mechanisms responsible for the retention and desorption. We implemented the best identified diffusion, recombination, and trapping parameters in ITMC-DYN package that integrate both various collisional and thermal processes. We predicted, for example, that sample cooling between discharges in DIII-D operations can significantly affect the spatial distribution of trapped D in W under reactor irradiation conditions. Correct prediction of desorption spectra from samples irradiated during 10 DIII-D discharges showed that up to 35% of D can be retained in high binding energy defects such as vacancy clusters or voids.

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Laboratory (ANL)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-06CH11357; FC02-04ER54698

OSTI ID:: 1905307

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 572; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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