A Domestic Program for Liquid Metal PFC Research in Fusion

Andruczyk, D.; Maingi, R.; Kessel, Chuck; Curreli, D.; Kolemen, E.; Canik, J.; Pint, B.; Youchison, D.; Smolentsev, S.

doi:10.1007/s10894-020-00259-0

A Domestic Program for Liquid Metal PFC Research in Fusion

Journal Article · Sat Oct 03 00:00:00 EDT 2020 · Journal of Fusion Energy

DOI:https://doi.org/10.1007/s10894-020-00259-0· OSTI ID:1821857

^[1]; Maingi, R. ^[2]; Kessel, Chuck ^[3]; Curreli, D. ^[1]; Kolemen, E. ^[2]; Canik, J. ^[3]; Pint, B. ^[3]; Youchison, D. ^[3]; Smolentsev, S. ^[4]

Univ. of Illinois at Urbana-Champaign, IL (United States)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of California, Los Angeles, CA (United States)

While high-Z solid plasma-facing components (PFCs) are the leading candidates for reactors, it is unclear that they can survive the intense plasma material interaction (PMI). Liquid metals (LM) PFCs offer potential solutions since they are not susceptible to the same type of damage, and can be “self-healing”. Following the Fusion Energy System Study on Liquid Metal Plasma Facing Components study that recently was completed by Kessel et al. (Fusion Sci Technnol 75:886, 2019) a domestic LM PFC design program has been initiated to develop reactor-relevant LM PFC concepts. This program seeks to evaluate LM PFC concepts for a Fusion Nuclear Science Facility (FNSF) or a Compact Pilot Plant via engineering design calculations, modeling of PMI and PFC components and laboratory experiments. The latter involves experiments in dedicated test stands and confinement devices and seeks to identify and answer open questions in LM PFC design. The new national LM PFC program is first investigating lithium as the plasma facing material for a flowing divertor PFC concept. Several flow speeds will be evaluated, ranging from ~ cm/s to m/s. The surface temperature will initially be held below the strongly evaporative limit in the first design; higher temperatures with strong evaporation will be considered in future concepts. Other topics of interest include: understanding of the hydrogen and helium interaction with the liquid lithium; single effect experiments on wetting, compatibility and embrittlement; and prototypical experiments for control and characterization of flowing LM. A path to plasma and future tokamak exposure of these concepts will be developed.

View Accepted Manuscript (DOE)

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

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

Grant/Contract Number:: AC02-09CH11466; AC05-00OR22725; SC0020642

OSTI ID:: 1821857

Journal Information:: Journal of Fusion Energy, Journal Name: Journal of Fusion Energy Journal Issue: 6 Vol. 39; ISSN 0164-0313

Publisher:: SpringerCopyright Statement

Country of Publication:: United States

Language:: English

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