Novel SOLPS-ITER simulations of X-point target and snowflake divertors
Name
22ja109_full.pdf
Size
12.57 MB
Format
Adobe PDF
Checksum (MD5)
024d550b4955b14e18ce12280a6c1aa9
Author(s)
Cowley, C.
Kuang, Adam Q.
Moulton, D.
Lore, J.D.
Canik, J.
Umansky, M.
Wigram, Mike
Ballinger, S.
Lipschulz, B.
Date Issued
November 2022
Journal
Plasma Physics and Controlled Fusion
Publisher
IOP
Abstract
The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple X-point alternative divertor geometries such as snowflakes and X-point targets have great potential in reducing power loads, but have not yet been simulated widely in codes with kinetic neutrals. This paper discusses recent changes made to the SOLPS-ITER code to allow for the simulation of X-point target and low-field side snowflake divertor geometries. Snowflake simulations using this method are presented, in addition to the first SOLPS-ITER simulation of the X-point target. Analysis of these results show reasonable consistency with the simple modelling and theoretical predictions, supporting the validity of the methodology implemented.
Description
Submitted for publication in Plasma Physics and Controlled Fusion
MIT Department
Massachusetts Institute of Technology. Plasma Science and Fusion Center
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1088/1361-6587/acb4ba
