[HTML][HTML] First snowflake divertor experiments in MAST-U tokamak

VA Soukhanovskii, G Cunningham, JR Harrison… - Nuclear Materials and …, 2022 - Elsevier
First snowflake (SF) divertor experiments in the MAST-U tokamak demonstrated steady-state
snowflake-plus divertor configurations in 450 kA ohmic L-mode plasmas. The SF divertor …

Modeling of deuterium and carbon radiation transport in MAST-U tokamak advanced divertors

VA Soukhanovskii, AI Khrabry, HA Scott… - Nuclear …, 2022 - iopscience.iop.org
Modest effects of deuterium and carbon radiation opacity in the Super-X and snowflake
divertor plasmas are predicted for MAST Upgrade tokamak with core plasma input power 2.5 …

UEDGE modeling of plasma detachment of CFETR with ITER‐like divertor geometry by external impurity seeding

MZ Zhang, CF Sang, ML Zhao… - … to Plasma Physics, 2024 - Wiley Online Library
Efficient handling of high heat flux on the plasma‐facing components, particularly the
divertor targets, poses a significant challenge for the Chinese Fusion Engineering Testing …

Modeling snowflake divertors in MAST-U Tokamak

AI Khrabry, VA Soukhanovskii, TD Rognlien… - Nuclear …, 2021 - iopscience.iop.org
In a snowflake (SF) divertor, two magnetic field nulls are placed close to each other, creating
four strike points (SPs) compared to two in a standard X-point divertor. In preparation for …

Addressing the carbon and nitrogen impurity screening issue on HL-2M snowflake minus and conventional divertor using SOLPS

Y Zhou, G Zheng, H Du, J Li, W Pan… - Plasma Physics and …, 2023 - iopscience.iop.org
This paper demonstrates the benefits of the HL-2M SF (snowflake) minus divertor on power
exhaust and impurity screening compared with the LSN (lower single null) conventional …

INGRID: An interactive grid generator for 2D edge plasma modeling

BM Garcia, MV Umansky, J Watkins, J Guterl… - Computer Physics …, 2022 - Elsevier
A fusion boundary-plasma domain is defined by axisymmetric magnetic surfaces where the
geometry is often complicated by the presence of one or more X-points; and modeling …

Analysis of radial electric field in the scrape-off layer in SOLPS-ITER modeling of ASDEX-upgrade and ITER

E Kaveeva, V Rozhansky - Plasma Physics and Controlled …, 2023 - iopscience.iop.org
Formation of the radial electric field profile in the scrape-off layer of the tokamak in the outer
midplane is analyzed on the basis of SOLPS-ITER modeling for various regimes of ASDEX …

[PDF][PDF] Modeling of deuterium and carbon radiation transport in Super-X and snowflake divertor plasmas in MAST-U tokamak

VA Soukhanovskii - 2021 - osti.gov
Modest effects of deuterium radiation opacity in MAST Upgrade tokamak Super-X and
snowflake divertor plasmas are found based on SOLPS-EIRENE and UEDGE code divertor …