Coupled model for liquid lithium plasma facing components

Khodak, Andrei; Emdee, Eric; Goldston, Robert; Maingi, Rajesh

doi:10.1016/j.fusengdes.2024.114651

Coupled model for liquid lithium plasma facing components

Journal Article · Tue Sep 03 00:00:00 EDT 2024 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2024.114651· OSTI ID:2447388

^[1]; ^[1]; ^[1]; ^[1]

Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Numerical analysis provides the design choice and operating window of liquid metal Plasma Facing Components (PFC) concepts. Coupled analysis of boundary plasma together with the surrounding boundary structures is required. Here, to achieve this goal, PPPL is developing a comprehensive multi-physics model for modeling of PFCs in fusion devices. The model includes the fluid-kinetic code SOLPS-ITER and the flow and heat transfer code CFX from ANSYS. SOLPS-ITER was augmented with a liquid metal boundary condition algorithm, allowing direct two-way coupling of the plasma analysis with the two-dimensional analytical slab flow model which includes heat convection in the liquid metal PFC. The target heat flux resulting from this coupled analysis is used as a boundary condition for detailed 3D Computational Fluid Dynamics (CFD) Magneto Hydro Dynamics (MHD) and heat transfer analysis. A new formulation of MHD equations is introduced in the numerical procedure ensuring current conservation of the discretized equations. Results of the 3D analysis are used for final validation of the coupled model. A PFC design where a porous wall is used to stabilize the liquid metal surface, while MHD drive is used to push the liquid metal flow inside the PFC, will be investigated in the regimes where vapor shielding is created for enhanced volumetric plasma heat dissipation.

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

OSTI ID:: 2447388

Alternate ID(s):: OSTI ID: 2439491

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 207; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (15)

3D MHD free surface fluid flow simulation based on magnetic-field induction equations Huang, H. L.; Ying, A.; Abdou, M. A. Fusion Engineering and Design, Vol. 63-64 https://doi.org/10.1016/S0920-3796(02)00261-2	journal	December 2002
Numerical model of dual-coolant lead–lithium (DCLL) blanket Khodak, Andrei; Titus, Peter; Brown, Thomas Fusion Engineering and Design, Vol. 137 https://doi.org/10.1016/j.fusengdes.2018.08.010	journal	December 2018
A current density conservative scheme for incompressible MHD flows at a low magnetic Reynolds number. Part I: On a rectangular collocated grid system Ni, Ming-Jiu; Munipalli, Ramakanth; Morley, Neil B. Journal of Computational Physics, Vol. 227, Issue 1 https://doi.org/10.1016/j.jcp.2007.07.025	journal	November 2007
Study of lithium vapor flow in a detached divertor using DSMC code Emdee, E. D.; Goldston, R. J.; Schwartz, J. A. Nuclear Materials and Energy, Vol. 19 https://doi.org/10.1016/j.nme.2019.01.032	journal	May 2019
Plasma facing components with capillary porous system and liquid metal coolant flow Khodak, Andrei; Maingi, Rajesh Physics of Plasmas, Vol. 29, Issue 7 https://doi.org/10.1063/5.0088015	journal	July 2022
Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility Kessel, C. E.; Andruczyk, D.; Blanchard, J. P. Fusion Science and Technology, Vol. 75, Issue 8 https://doi.org/10.1080/15361055.2019.1610685	journal	June 2019
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
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
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
Optimization of lithium vapor box divertor evaporator location on NSTX-U using SOLPS-ITER Emdee, E. D.; Goldston, R. J.; Khodak, A. Nuclear Fusion, Vol. 64, Issue 8, 086047 https://doi.org/10.1088/1741-4326/ad57d2	journal	July 2024
Parametric Study of a Divertor Cooling System for a Liquid-Metal Plasma-Facing Component Khodak, Andrei; Jaworski, Michael A. IEEE Transactions on Plasma Science, Vol. 42, Issue 8 https://doi.org/10.1109/TPS.2014.2330292	journal	August 2014
Numerical Analysis of 2-D and 3-D MHD Flows Relevant to Fusion Applications Khodak, Andrei IEEE Transactions on Plasma Science, Vol. 45, Issue 9 https://doi.org/10.1109/TPS.2017.2734106	journal	September 2017
Low Recycling Divertor for JET Burning Plasma Regime ($P_{\mathrm{DT}}$ > 25 MW, $Q_{\mathrm{DT}}$ > 5), Insensitive to Plasma Physics Zakharov, Leonid E.; Allain, Jean Paul; Bennett, Samuel X. IEEE Transactions on Plasma Science, Vol. 48, Issue 6 https://doi.org/10.1109/TPS.2019.2953591	journal	June 2020
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

Similar Records

Design and Analysis of Liquid Lithium Plasma Facing Components

Journal Article · Sun Apr 14 20:00:00 EDT 2024 · IEEE Transactions on Plasma Science · OSTI ID:2352436

Liquid lithium divertor analysis using coupled plasma material interaction model

Journal Article · Mon Nov 18 19:00:00 EST 2024 · Nuclear Materials and Energy · OSTI ID:2478177

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
High heat flux
Liquid lithium
Numerical analysis
Plasma facing components

Coupled model for liquid lithium plasma facing components

Citation Formats

References (15)

Similar Records

Related Subjects