Abstract
Within the ongoing U.S.-based program on the development of liquid metal plasma-facing components, numerical simulations and analyses are performed to address the feasibility of the open-surface Li divertor. In the previous scoping studies (Smolentsev, 2021), heat-removal capabilities of the divertor were assessed using a simplified flow model for a slug-type velocity profile and constant flow thickness. Here, new analyses take into account forces acting on the flowing Li layer. Three reduced-order mathematical models are applied under the conditions of the U.S. Fusion Nuclear Science Facility (FNSF) to access magnetohydrodynamic (MHD) flow development effects, velocity distribution, and surface waves: 1) fully developed MHD flow; 2) quasi-2-D developing MHD flow; and 3) multiphase MHD flow. The obtained results for MHD flows and the surface heat flux computed with the plasma code scrape-off layer plasma simulation for ITER (SOLPS-ITER) are then used as input data to compute the temperature distribution in the divertor by solving the convection-diffusion energy equation.
Original language | English |
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Pages (from-to) | 4193-4198 |
Number of pages | 6 |
Journal | IEEE Transactions on Plasma Science |
Volume | 50 |
Issue number | 11 |
DOIs | |
State | Published - Nov 1 2022 |
Funding
This work was supported in part by the U.S. Department of Energy (DOE) under Grant DE-SC0020979 and Grant DEAC05-00OR22725.
Funders | Funder number |
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U.S. Department of Energy | DE-SC0020979, DEAC05-00OR22725 |
Keywords
- Divertor
- fusion nuclear science facility (FNSF)
- heat transfer
- liquid metal (LM)
- magnetohydrodynamic (MHD)
- open-surface flow