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

Journal Article · · Contributions to Plasma Physics
 [1];  [1];  [2];  [2];  [1];  [1];  [1];  [1]
  1. Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of Education), School of Physics Dalian University of Technology Dalian China
  2. Lawrence Livermore National Laboratory Livermore California USA
Abstract

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 Reactor (CFETR) with fusion power of Gigawatt. This work investigates the divertor plasma detachment of CFETR with a standard ITER‐like divertor geometry by neon (Ne) or argon (Ar) impurity seeding using UEDGE code. The cross‐field drifts terms are switched off, and fluid neutral models and a “fixed‐fraction” impurity model are applied to enable efficient simulations for the study of CFETR detachment. In order to reduce the heat load on the divertor targets below the acceptable level (<10 MW/m 2 ), the impurity fraction ( f ), pumping speed ( S ), and upstream density are varied to identify the suitable operations window during Ne seeding. The effects of Ne and Ar impurities on the plasma detachment are compared. It is found that with the power across the core‐edge interface P SOL  = 200 MW and separatrix density of 2.8  10 19 , Ne impurity fraction ≥1.7%, and Ar impurity fraction ≥0.24% can achieve the partial detachment. Achieving similar total radiation power (˜148 MW), the Ne fraction is 2.3% and the Ar fraction is 0.24%. Moreover, the simulation results indicate that Ar exhibits better power radiation efficiency and core compatibility compared with Ne.

Sponsoring Organization:
USDOE
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
2280708
Journal Information:
Contributions to Plasma Physics, Journal Name: Contributions to Plasma Physics Journal Issue: 7-8 Vol. 64; ISSN 0863-1042
Publisher:
Wiley Blackwell (John Wiley & Sons)Copyright Statement
Country of Publication:
Germany
Language:
English

References (35)

A review of recent developments in atomic processes for divertors and edge plasmas journal April 1995
A fully implicit, time dependent 2-D fluid code for modeling tokamak edge plasmas journal December 1992
Edge-plasma models and characteristics for magnetic fusion energy devices journal July 2002
Effect of N2, Ne and Ar seeding on Alcator C-Mod H-mode confinement journal August 2011
Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET journal August 2017
ITER divertor plasma response to time-dependent impurity injection journal August 2017
Optimization of the snowflake divertor for power and particle exhaust on NSTX–U journal May 2019
Physics basis for the first ITER tungsten divertor journal August 2019
Modeling snowflake divertors in MAST-U tokamak using UEDGE code journal March 2021
Direct removal of edge-localized pollutant emission in a near-infrared bremsstrahlung measurement journal March 2003
Attainment of a stable, fully detached plasma state in innovative divertor configurations journal May 2017
Experimental investigation and SOLPS-ITER modeling of Ne-seeded radiative divertor H-modes plasma on EAST journal May 2019
Improved core-edge compatibility using impurity seeding in the small angle slot (SAS) divertor at DIII-D journal June 2020
Two-dimensional electric fields and drifts near the magnetic separatrix in divertor tokamaks journal May 1999
Simulation studies of divertor power exhaust with neon seeding for CFETR with GW-level fusion power journal September 2020
H mode discharges with feedback controlled radiative boundary in the ASDEX Upgrade tokamak journal October 1995
Comparison of radiating divertor behaviour in single-null and double-null plasmas in DIII-D journal March 2008
Experimental divertor physics journal June 1997
Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO journal November 2013
SOLPS-ITER modeling of EU-DEMO Ar-seeded cases with drifts and kinetic neutrals journal June 2023
Overview of the present progress and activities on the CFETR journal June 2017
Progress of the CFETR design journal June 2019
Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept journal September 2019
Study of passively stable, fully detached divertor plasma regimes attained in innovative long-legged divertor configurations journal October 2019
Progress in DIII-D towards validating divertor power exhaust predictions journal April 2020
Corrigendum: characterisation of highly radiating neon seeded plasmas in JET-ILW (2019 Nucl. Fusion 59 126031) journal June 2020
The role of divertor pumping in plasma detachment and particle exhaust in a closed divertor journal November 2020
X-point radiation, its control and an ELM suppressed radiating regime at the ASDEX Upgrade tokamak journal December 2020
Outer midplane neutral density measurements and H-mode fueling studies in NSTX-U journal January 2021
Comparison of divertor behavior and plasma confinement between argon and neon seeding in EAST journal April 2021
Simulation of the SPARC plasma boundary with the UEDGE code journal July 2021
SOLPS-ITER simulations of high power exhaust for CFETR divertor with full drifts journal February 2022
Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a low-power scenario in the DTT journal March 2022
SOLPS-ITER modeling of CFETR advanced divertor with Ar and Ne seeding journal July 2022
Numerical Studies of Impurities in Fusion Plasmas journal March 1983

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