Recent progress in the development of liquid metal plasma facing components for magnetic fusion devices

Hu, J. S.; Zuo, G. Z.; Li, L.; Zhang, D. H.; Bi, H. L.; Ye, Z. B.; Pan, J. H.; Dai, S. Y.; Meng, X. C.; Sun, Z.; Ono, M.; Hirooka, Y.; Ruzic, D. N.

doi:10.1016/j.nme.2024.101776

Recent progress in the development of liquid metal plasma facing components for magnetic fusion devices

Journal Article · Fri Oct 18 04:00:00 EDT 2024 · Nuclear Materials and Energy

DOI:https://doi.org/10.1016/j.nme.2024.101776· OSTI ID:2475835

Hu, J. S. ^[1]; Zuo, G. Z. ^[1]; Li, L. ^[1]; Zhang, D. H. ^[1]; Bi, H. L. ^[2]; Ye, Z. B. ^[3]; Pan, J. H. ^[4]; Dai, S. Y. ^[5]; ^[6]; ^[7]; ^[7]; Hirooka, Y. ^[8]; Ruzic, D. N. ^[9]

Chinese Academy of Sciences, Hefei (China)
Hefei University of Technology (China)
Sichuan University, Chengdu (China)
University of Chinese Academy of Sciences, Beijing (China)
Dalian University of Technology (China)
Hefei Comprehensive National Science Center (China)
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Chubu University, Aichi (Japan)
University of Illinois at Urbana-Champaign, IL (United States)

One of the most critical challenges for future fusion reactors is to develop longevity plasma-facing components (PFCs) exposed to extremely high heat and neutron loads. As opposed to those employing solid metals, PFCs with flowing liquid metals (LM) have shown self-healing, heat removal and good impurity control capabilities, all essential to fusion devices. Recently, significant progress in LM-PFC development has been reported globally, with data from several magnetic fusion devices. These studies reveal that LM-PFCs can endure extreme heat fluxes while maintaining plasma compatibility. New design concepts have been proposed and numerically analyzed, advancing models for liquid PFCs in future reactors. Despite existing technical challenges, these developments suggest that LM-PFCs hold promise for future fusion applications.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE; National Key Research and Development Program of China; Strategic Priority Research Program of Chinese Academy of Sciences; Hefei Science Center CAS

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 2475835

Journal Information:: Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Vol. 41; ISSN 2352-1791

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Predictive modelling of liquid metal divertor: from COMPASS tokamak towards Upgrade Horacek, J.; Cecrdle, J.; Tskhakaya, D. Physica Scripta, Vol. 96, Issue 12 https://doi.org/10.1088/1402-4896/ac1dc9	journal	August 2021
Mitigation of plasma–material interactions via passive Li efflux from the surface of a flowing liquid lithium limiter in EAST Zuo, G. Z.; Hu, J. S.; Maingi, R. Nuclear Fusion, Vol. 57, Issue 4 https://doi.org/10.1088/1741-4326/aa5ea0	journal	March 2017
Power handling limit of liquid lithium divertor targets Rindt, P.; Morgan, T. W.; Jaworski, M. A. Nuclear Fusion, Vol. 58, Issue 10 https://doi.org/10.1088/1741-4326/aad290	journal	July 2018
EMC3-EIRENE modelling of edge plasma and impurity emissions compared with the liquid lithium limiter experiment on EAST Xie, T.; Dai, S. Y.; Zuo, G. Z. Nuclear Fusion, Vol. 58, Issue 10 https://doi.org/10.1088/1741-4326/aad42f	journal	August 2018
Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST Zuo, G. Z.; Hu, J. S.; Maingi, R. Nuclear Fusion, Vol. 59, Issue 1 https://doi.org/10.1088/1741-4326/aaedcb	journal	November 2018
Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI Rindt, P.; Morgan, T. W.; van Eden, G. G. Nuclear Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1741-4326/ab0560	journal	March 2019
Formulized average surface binding energy elevation and lithium vaporization and redeposition investigations in capillary pore systems Cao, X.; Zhang, D. H.; Zhao, Y. J. Nuclear Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1741-4326/ab05f0	journal	April 2019
Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses Rindt, P.; Mata González, J.; Hoogerhuis, P. Nuclear Fusion, Vol. 59, Issue 5 https://doi.org/10.1088/1741-4326/ab0a76	journal	March 2019
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
Overview of the FTU results Pucella, G.; Alessi, E.; Angelini, B. Nuclear Fusion, Vol. 59, Issue 11 https://doi.org/10.1088/1741-4326/ab19ef	journal	July 2019
Vapor shielding of liquid lithium divertor target during steady state and transient events Marenkov, E.; Pshenov, A. Nuclear Fusion, Vol. 60, Issue 2 https://doi.org/10.1088/1741-4326/ab5eb5	journal	January 2020
Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks Horacek, J.; Adamek, J.; Komm, M. Nuclear Fusion, Vol. 60, Issue 6 https://doi.org/10.1088/1741-4326/ab7e47	journal	May 2020
Magnetohydrodynamic effects on liquid metal film flowing along an inclined plate relating to plasma facing components Yang, J. -C.; Qi, T. -Y.; Ren, D. -W. Nuclear Fusion, Vol. 60, Issue 8 https://doi.org/10.1088/1741-4326/ab9257	journal	July 2020
Numerical investigation of hydrogen isotope retention by an yttrium pebble-bed from flowing liquid lithium Hendricks, S. J.; Carella, E.; Moreno, C. Nuclear Fusion, Vol. 60, Issue 10 https://doi.org/10.1088/1741-4326/aba672	journal	September 2020
Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency Abdou, Mohamed; Riva, Marco; Ying, Alice Nuclear Fusion, Vol. 61, Issue 1 https://doi.org/10.1088/1741-4326/abbf35	journal	November 2020
Modeling the vapor shielding of a liquid lithium divertor target using SOLPS 4.3 code Marenkov, E. D.; Kukushkin, A. S.; Pshenov, A. A. Nuclear Fusion, Vol. 61, Issue 3 https://doi.org/10.1088/1741-4326/abd642	journal	February 2021
Performance of liquid-lithium-filled 3D-printed tungsten divertor targets under deuterium loading with ELM-like pulses in Magnum-PSI Rindt, P.; Korving, S. Q.; Morgan, T. W. Nuclear Fusion, Vol. 61, Issue 6 https://doi.org/10.1088/1741-4326/abf854	journal	May 2021
Overview of the FTU results Pucella, G.; Alessi, E.; Almaviva, S. Nuclear Fusion, Vol. 62, Issue 4 https://doi.org/10.1088/1741-4326/ac1802	journal	March 2022
Vapour shielding of liquid-metal CPS-based targets under ELM-like and disruption transient loading Garkusha, I. E.; Makhlai, V. A.; Petrov, Yu. V. Nuclear Fusion, Vol. 61, Issue 11 https://doi.org/10.1088/1741-4326/ac26ec	journal	October 2021
Deuterium retention of liquid Sn and SnLi in a CPS target under plasma exposure at high temperatures Oyarzabal, E.; Tabarés, F. L. Nuclear Fusion, Vol. 61, Issue 12 https://doi.org/10.1088/1741-4326/ac30c5	journal	November 2021
Structured large-pore foams improve thermal performance of LiMIT-style liquid lithium PFC Szott, M.; Stemmley, S.; Moynihan, C. Nuclear Fusion, Vol. 62, Issue 1 https://doi.org/10.1088/1741-4326/ac39f3	journal	December 2021
SOLPS-ITER simulations of a CPS-based liquid metal divertor for the EU DEMO: Li vs Sn Nallo, G. F.; Mazzitelli, G.; Moscheni, M. Nuclear Fusion, Vol. 62, Issue 3 https://doi.org/10.1088/1741-4326/ac4867	journal	March 2022
Divertorlets concept for low-recycling fusion reactor divertor: experimental, analytical and numerical verification Saenz, F.; Sun, Z.; Fisher, A. E. Nuclear Fusion, Vol. 62, Issue 8 https://doi.org/10.1088/1741-4326/ac6682	journal	June 2022
Surface instability of static liquid metal in magnetized fusion plasma Somboonkittichai, N.; Zuo, G. Z. Nuclear Fusion, Vol. 63, Issue 2 https://doi.org/10.1088/1741-4326/acaedb	journal	January 2023
Magnetohydrodynamics in free surface liquid metal flow relevant to plasma-facing components Sun, Z.; Al Salami, J.; Khodak, A. Nuclear Fusion, Vol. 63, Issue 7 https://doi.org/10.1088/1741-4326/acd864	journal	June 2023
The effect of gas injection location on a lithium vapor box divertor in NSTX-U Emdee, E. D.; Goldston, R. J. Nuclear Fusion, Vol. 63, Issue 9 https://doi.org/10.1088/1741-4326/ace6be	journal	July 2023
Analysis and design of fast flow liquid Li divertor for fusion nuclear science facility (FNSF) using coupled plasma boundary and LM MHD/heat transfer codes ^* Islam, M. S.; Lore, J. D.; Smolentsev, S. Nuclear Fusion, Vol. 64, Issue 5 https://doi.org/10.1088/1741-4326/ad3a7b	journal	April 2024
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak Hu, J. S.; Sun, Z.; Guo, H. Y. Physical Review Letters, Vol. 114, Issue 5 https://doi.org/10.1103/PhysRevLett.114.055001	journal	February 2015
Self-Regulated Plasma Heat Flux Mitigation Due to Liquid Sn Vapor Shielding van Eden, G. G.; Morgan, T. W.; Aussems, D. U. B. Physical Review Letters, Vol. 116, Issue 13 https://doi.org/10.1103/PhysRevLett.116.135002	journal	April 2016
Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment Boyle, D. P.; Majeski, R.; Schmitt, J. C. Physical Review Letters, Vol. 119, Issue 1 https://doi.org/10.1103/PhysRevLett.119.015001	journal	July 2017
Magnetic Propulsion of Intense Lithium Streams in a Tokamak Magnetic Field Zakharov, Leonid E. Physical Review Letters, Vol. 90, Issue 4 https://doi.org/10.1103/PhysRevLett.90.045001	journal	January 2003
Numerical Analysis of Liquid Metal MHD Flow and Heat Transfer for Open-Surface Li Divertor in FNSF Smolentsev, Sergey; Kessel, Charles E.; Lore, Jeremy D. IEEE Transactions on Plasma Science https://doi.org/10.1109/TPS.2022.3162141	journal	January 2022
Simulation of Liquid Lithium Divertor Geometry Using SOLPS-ITER Lore, J. D.; Islam, M. S.; Kessel, C. E. IEEE Transactions on Plasma Science https://doi.org/10.1109/TPS.2022.3166402	journal	January 2022
Design and Analysis of Liquid Lithium Plasma Facing Components Khodak, Andrei; Emdee, Eric D.; Goldston, Robert J. IEEE Transactions on Plasma Science https://doi.org/10.1109/TPS.2024.3385729	journal	January 2024
First Spectroscopic Results with Tin Limiter on FTU Plasma No authors listed Plasma Physics Reports, Vol. 44, Issue 7 https://doi.org/10.1134/S1063780X18070012	journal	July 2018
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Magnetically Guided Liquid Metal Divertor (MAGLIMD) with Resilience to Disruptions and ELMs Shimada, Michiya; Tobita, Kenji Plasma and Fusion Research, Vol. 15, Issue 0 https://doi.org/10.1585/pfr.15.1401011	journal	April 2020
Novel Non-Evaporable Getter Materials and Their Possible Use in Fusion Application for Tritium Recovery Santucci, Alessia; Farina, Luca; Tosti, Silvano Molecules, Vol. 25, Issue 23 https://doi.org/10.3390/molecules25235675	journal	December 2020
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70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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