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Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations
- Source :
- Nuclear Materials and Energy, Vol 18, Iss, Pp 125-130 (2019)
- Publication Year :
- 2019
- Publisher :
- ELSEVIER SCIENCE BV, 2019.
-
Abstract
- The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well as for the design of the ITER divertor. The numerical scheme of the plasma solver of the code, B2.5, is based on the assumption of perfectly orthogonal grids in the poloidal plane, aligned with the magnetic field, while in practice grids are often strongly distorted to match divertor target shapes. Neglecting these grid distortion leads to qualitatively and quantitatively incorrect results for fluid neutral simulations, and may affect results in cold (detached) divertors even when using kinetic neutral simulations. In this contribution, we present the first results of a newly implemented 9-point stencil in B2.5 to properly handle misaligned grids. The new scheme is then applied to fluid neutral simulations of a well-diagnosed and previously modeled Alcator C-Mod discharge. Results are compared with the original 5-point scheme neglecting grid distortion effects, as well as with simulations including a full kinetic neutral model. We conclude that the 9-point stencil is essential to correctly model the transport of fluid neutrals on distorted grids, and to capture the effects of divertor closure on the fluid neutral behavior. Keywords: SOLPS-ITER, Divertor modeling, Fluid neutral modeling, Misaligned grids, Alcator C-Mod
- Subjects :
- Nuclear and High Energy Physics
Technology
Materials Science (miscellaneous)
Kinetic energy
01 natural sciences
Stencil
010305 fluids & plasmas
SOLPS-ITER
LEAKAGE
Alcator C-Mod
Misaligned grids
Physics::Plasma Physics
Divertor modeling
0103 physical sciences
Nuclear Science & Technology
010302 applied physics
Physics
Science & Technology
Divertor
Plasma
Mechanics
Solver
Grid
lcsh:TK9001-9401
Magnetic field
Fluid neutral modeling
Nuclear Energy and Engineering
lcsh:Nuclear engineering. Atomic power
Subjects
Details
- Language :
- English
- Database :
- OpenAIRE
- Journal :
- Nuclear Materials and Energy, Vol 18, Iss, Pp 125-130 (2019)
- Accession number :
- edsair.doi.dedup.....f7be128eb2c32afdef391ea788ed1ca2