Javascript must be enabled to continue!
SOLPS-ITER modeling with activated drifts for a snowflake divertor in ASDEX Upgrade
View through CrossRef
Abstract
We report on the first SOLPS-ITER simulations of a low-field side snowflake minus (LFS SF−) divertor configuration with drifts fully activated in ASDEX Upgrade. Compared to a reference case without drifts, the simulation in normal toroidal magnetic field configuration (B × ∇B points to the primary X-point) shows a larger low-field-side/high-field-side asymmetry, an enhanced radial cross field transport, as well as a flux redistribution between the primary and secondary strike points. Although small compared to the total input power, power is found even on a strike point magnetically disconnected from the outer mid-plane, which is hard to explain by purely diffusive transport.
IOP Publishing
Title: SOLPS-ITER modeling with activated drifts for a snowflake divertor in ASDEX Upgrade
Description:
Abstract
We report on the first SOLPS-ITER simulations of a low-field side snowflake minus (LFS SF−) divertor configuration with drifts fully activated in ASDEX Upgrade.
Compared to a reference case without drifts, the simulation in normal toroidal magnetic field configuration (B × ∇B points to the primary X-point) shows a larger low-field-side/high-field-side asymmetry, an enhanced radial cross field transport, as well as a flux redistribution between the primary and secondary strike points.
Although small compared to the total input power, power is found even on a strike point magnetically disconnected from the outer mid-plane, which is hard to explain by purely diffusive transport.
Related Results
Comparison of SOLPS5.0 and SOLPS‐ITER simulations for ASDEX upgrade L‐mode
Comparison of SOLPS5.0 and SOLPS‐ITER simulations for ASDEX upgrade L‐mode
AbstractThis paper examines the backward compatibility of SOLPS‐ITER with SOLPS5.0 and produces a basic test of the physics/numerics improvements/additions in SOLPS‐ITER recommende...
Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments
Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments
Abstract
Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak à Configu...
SOLPS-ITER numerical simulations of ITER-scale Snowflake divertors: low-field-side SF−/SF+ and high-field-side SF−/SF+ configurations
SOLPS-ITER numerical simulations of ITER-scale Snowflake divertors: low-field-side SF−/SF+ and high-field-side SF−/SF+ configurations
Abstract
Using the edge plasma code package SOLPS-ITER, we study the four types of Snowflake (SF) divertors for an ITER-size tokamak, with to...
Initial TCV operation with a baffled divertor
Initial TCV operation with a baffled divertor
Abstract
The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative diver...
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
Abstract
Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called ‘Tokamak Expl...
Iterative design and virtual assessment of the DTT Vacuum Vessel interface to Divertor
Iterative design and virtual assessment of the DTT Vacuum Vessel interface to Divertor
The upcoming Divertor Tokamak Test (DTT) facility, whose construction is starting at ENEA Frascati Research Centre in Italy, plays a key role in the EUROfusion roadmap to achieve n...
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development
Abstract
An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling of AUG discharges was estab...
Analysis of fuelling requirements in ITER H-modes with SOLPS-EPED1 derived scalings
Analysis of fuelling requirements in ITER H-modes with SOLPS-EPED1 derived scalings
Abstract
Fuelling requirements for ITER are analysed in relation to pellet fuelling and ELM pacing, and a divertor power load control consistent with the ITER pumpin...

