Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation

Abrams, T.; Jaworski, M. A.; Chen, M.; Carter, E. A.; Kaita, R.; Stotler, D. P.; De Temmerman, G.; Morgan, T. W.; van den Berg, M. A.; van der Meiden, H. J.

doi:10.1088/0029-5515/56/1/016022

Title: Suppressed gross erosion of high-temperature lithium via rapid deuterium implantation

Journal Article · Thu Dec 17 00:00:00 EST 2015 · Nuclear Fusion

DOI:https://doi.org/10.1088/0029-5515/56/1/016022· OSTI ID:1256597

Abrams, T. ^[1]; Jaworski, M. A. ^[1]; Chen, M. ^[2]; Carter, E. A. ^[2];

^[1];

^[1]; De Temmerman, G. ^[3]; Morgan, T. W. ^[3]; van den Berg, M. A. ^[3]; van der Meiden, H. J. ^[3]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Princeton Univ., Princeton, NJ (United States)
FOM Institute DIFFER - Dutch Institute For Fundamental Energy Research, Nieuwegein (The Netherlands)

Lithium-coated high-Z substrates are planned for use in the NSTX-U divertor and are a candidate plasma facing component (PFC) for reactors, but it remains necessary to characterize the gross Li erosion rate under high plasma fluxes (>1023 m-2 s-1), typical for the divertor region. In this work, a realistic model for the compositional evolution of a Li/D layer is developed that incorporates first principles molecular dynamics (MD) simulations of D diffusion in liquid Li. Predictions of Li erosion from a mixed Li/D material are also developed that include formation of lithium deuteride (LiD). The erosion rate of Li from LiD is predicted to be significantly lower than from pure Li. This prediction is tested in the Magnum-PSI linear plasma device at ion fluxes of 1023–1024 m-2 s-1 and Li surface temperatures ≤800 °C. Li/LiD coatings ranging in thickness from 0.2 to 500 μm are studied. The dynamic D/Li concentrations are inferred via diffusion simulations. The pure Li erosion rate remains greater than Langmuir Law evaporation, as expected. For mixed-material Li/LiD surfaces, the erosion rates are reduced, in good agreement with modelling in almost all cases. These results imply that the temperature limit for a Li-coated PFC may be significantly higher than previously imagined.

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Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States); Princeton Univ., NJ (United States)

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

Grant/Contract Number:: AC02-09CH11466; SC0008598

OSTI ID:: 1256597

Alternate ID(s):: OSTI ID: 1238844; OSTI ID: 1390517

Report Number(s):: PPPL-5114

Journal Information:: Nuclear Fusion, Vol. 56, Issue 1; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 19 works

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