Liquid lithium divertor analysis using coupled plasma material interaction model
• Axis-symmetric coupled model of the plasma edge, and plasma facing components codes is introduced. • The model is applied to a divertor configuration with efficient vapor shielding. • Analytical model is used as a boundary condition for SOLPS-ITER plasma edge code. • SOLPS-ITER results are confirmed using 3D CFD MHD analysis with modified ANSYS CFX. • A modified sputtering model is introduced based on the experimental data obtained in literature. A liquid lithium divertor can improve performance of future fusion devices by creating efficient power exhaust and improving the energy confinement via pumping of the hydrogen isotopes. In addition, significantly higher heat fluxes can be handled if controlled vapor shielding is used to redistribute the divertor heat flux over a wider area. Design and optimization of such a system calls for an analysis model which includes a strong two-way coupling between the plasma and divertor material. The incoming plasma heat and particle flux will affect the divertor surface temperature, which is a defining factor of the lithium evaporative and sputtered flux going into the plasma. Results of the coupled model based on the plasma edge code SOLPS-ITER and the computational fluid dynamics (CFD) code ANSYS-CFX will be presented for different configurations. An analytical slab flow model is used as a heat transfer boundary condition for SOLPS, defining particle flux from the wall via calculation of the surface temperature. At the final step, results of the SOLPS analysis are verified using a 3D CFD magnetohydrodynamics (MHD) analysis which uses heat and particle flux from SOLPS as a boundary condition. In addition to plasma heat flux, both analytical and CFD temperature models include several plasma material interaction effects, such as lithium evaporation, condensation and sputtering based on deuterium target flux. New adatom sputtering model based on the available experimental data is presented. Analytical model is expanded to include free surface axisymmetric configurations. Results of parametric studies of the divertor configurations with different lithium inlet temperature and velocity will be presented leading to the optimal design resulting in the lowest possible lithium contamination in the core.
Authors
- R.J. Goldston (ORCID: https://orcid.org/0000-0002-0368-5514)
- Andrei Khodak (ORCID: https://orcid.org/0000-0002-8273-6614)
- R. Maingi (ORCID: https://orcid.org/0000-0003-1238-8121)
- Eric Emdee (ORCID: https://orcid.org/0000-0003-3334-2077)
Institutions
- Princeton Plasma Physics Laboratory (US)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2024-11-19
- DOI
- https://doi.org/10.1016/j.nme.2024.101821
- Citations
- 1
- Primary Topic
- Magnetic confinement fusion research
- Type
- article
- Field-Weighted Citation Impact
- 0.66
Funders
- U.S. Department of Energy
- Princeton University
- Office of Science
- Fusion Energy Sciences