Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations
<|begin_of_text|><|start_header_id|>system<|end_header_id|> You are a research archivist expert in dataset metadata. Answer the question truthfully.  <|eot_id|><|start_header_id|>user<|end_header_id|> Here is the Description of a dataset. Description:'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 ﬁeld-aligned grids, 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' . Please return only a json list of at most 3 Keywords corresponding to the Description:.<|eot_id|><|start_header_id|>assistant<|end_header_id|> {"Answer" : ["Alcator C-Mod","divertor modeling","misaligned grids","neutral model","SOLPS-ITER"]} <|eot_id|>
 Here is the Description of a dataset. Description:'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 ﬁeld-aligned grids, 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' . Please return only a json list of at most 3 Keywords corresponding to the Description:.
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 ﬁeld-aligned grids, 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
Alcator C-Mod; divertor modeling; misaligned grids; neutral model; SOLPS-ITER