Upgrades toward high-heat flux, liquid lithium plasma-facing components in the NSTX-U

Jaworski, M. A.; Brooks, A.; Kaita, R.; Lopes-Cardozo, N.; Menard, J.; Ono, M.; Rindt, P.; Tresemer, K.

doi:10.1016/j.fusengdes.2016.07.009

Title: Upgrades toward high-heat flux, liquid lithium plasma-facing components in the NSTX-U

Journal Article · Mon Aug 08 00:00:00 EDT 2016 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2016.07.009· OSTI ID:1335162

Jaworski, M. A. ^[1]; Brooks, A. ^[1]; Kaita, R. ^[1]; Lopes-Cardozo, N. ^[2]; Menard, J. ^[1]; Ono, M. ^[1]; Rindt, P. ^[2]; Tresemer, K. ^[1]

Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
TU/Eindhoven, Eindhoven (The Netherlands)

Liquid metal plasma-facing components (PFCs) provide numerous potential advantages over solid-material components. One critique of the approach is the relatively less developed technologies associated with deploying these components in a fusion plasma-experiment. Exploration of the temperature limits of liquid lithium PFCs in a tokamak divertor and the corresponding consequences on core operation are a high priority informing the possibilities for future liquid lithium PFCs. An all-metal NSTX-U is envisioned to make direct comparison between all high-Z wall operation and liquid lithium PFCs in a single device. By executing the all-metal upgrades incrementally, scientific productivity will be maintained while enabling physics and engineering-science studies to further develop the solid- and liquid-metal components. Six major elements of a flowing liquid-metal divertor system are described and a three-step program for implementing this system is laid out. The upgrade steps involve the first high-Z divertor target upgrade in NSTX-U, pre-filled liquid metal targets and finally, an integrated, flowing liquid metal divertor target. As a result, two example issues are described where the engineering and physics experiments are shown to be closely related in examining the prospects for future liquid metal PFCs.

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

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 1335162

Alternate ID(s):: OSTI ID: 1359139

Journal Information:: Fusion Engineering and Design, Vol. 112, Issue C; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 12 works

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Self-consistent modelling of a liquid metal box-type divertor with application to the divertor tokamak test facility: Li versus Sn Nallo, G. F.; Mazzitelli, G.; Savoldi, L. Nuclear Fusion, Vol. 59, Issue 6 https://doi.org/10.1088/1741-4326/ab145b	journal	May 2019
Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility Wallace, G. M.; Kessel, C. E.; Hosea, J. Fusion Science and Technology, Vol. 76, Issue 1 https://doi.org/10.1080/15361055.2019.1629253	journal	July 2019

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