Abstract Details
Abstracts
Author: Ivan Paradela Perez
Requested Type: Poster
Submitted: 2023-03-31 16:49:30
Co-authors: J.D.Lore
Contact Info:
ORNL
1 Bethel Valley Road
Oak Ridge, TN 37830
US
Abstract Text:
In this work, SOLPS-ITER simulations of MAST-U with three different magnetic geometries (Conventional, Elongated, and Super X configurations) and of ST-40 have been used to study the underlying physics of power and momentum transport and removal in spherical tokamaks.
An extensive understanding of power and momentum transport and removal within the Scrape-Off Layer is fundamental for the successful operation of future fusion devices. Spherical tokamaks present unique challenges and opportunities in this area. The exhaust problem is exacerbated due to their more compact sizes, while devices such as MAST-U provide access to advanced divertor configurations such as the super-X.
The simulations have been carried out using the standard version of SOLPS-ITER (3.0.8), as well as the new numerical schemes: 9-point stencil (3.1.0) and the unstructured, Wide Grid (3.2.0). These new versions incorporate improved numerical schemes and enable additional physics studies. Specifically, the 9-point stencil has been shown to improve the performance of the fluid neutral model in SOLPS and, in some cases, result in a modified plasma solution in the divertor region. The wide grid version of the code allows for calculation of the power and particle deposition distribution onto the different plasma facing components of the divertors and the main chamber walls and eliminates boundary conditions that are difficult to constrain.
A set of simulations consisting of density and power scans, high field side vs low field side gas puff locations, and multiple plasma currents and toroidal fields will be presented. Comparisons to upstream and downstream experimental measurements will be shown.
Support from US DOE DE-AC05-00OR22725 and DE-FC02-04ER54698.
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