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Title: Impact of plasma density/collisionality on divertor heat flux width

Journal Article · · Nuclear Fusion

Both ASDEX-Upgrade (AUG) data and the generalized HD (GHD) model showed that the scrape-off width broadens as the density/collisionality increases [1, 2]. A series of BOUT++ transport simulations are performed to study the physics of the scaling characteristics of the divertor heat flux width vs density/collisionality via a plasma density scan with either fixed pressure profile or fixed temperature profile inside separatrix. Additionally, the simulations show that even in the drift dominated regime, the divertor heat flux width can be broadened due to the transition of the SOL residence time from the parallel particle flow time to the enhanced parallel conduction time as the collisionality/density increases as posited in the GHD model. In addition, the heat flux width is found to be proportional to the square root of ion mass for low collisionality while it has a weakly dependence on ion mass for high collisionality. Furthermore, our simulations show that as the density increases, the radial electric field (Er) well shallows, which potentially weakens Er × B flow shear stabilization of turbulence at high density.

Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); National Key Research and Development Program of China; China Postdoctoral Science Foundation; National Natural Science Foundation of China (NSFC)
Grant/Contract Number:
AC52-07NA27344; AC02-09CHII466; 2017YFE0301206; 2017YFE0300402; 2017YFE0301100; 2020M670740; 11675037
OSTI ID:
1830500
Report Number(s):
LLNL-JRNL-812170; 1019348; TRN: US2216499
Journal Information:
Nuclear Fusion, Vol. 61, Issue 2; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

References (13)

Consequences of a reduction of the upstream power SOL width in ITER journal July 2013
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER journal August 2013
Turbulence driven widening of the near-SOL power width in ASDEX Upgrade H-Mode discharges journal April 2020
Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework journal January 2020
Calculation of two-dimension radial electric field in boundary plasmas by using BOUT++ journal July 2018
A new scaling for divertor detachment journal March 2017
Neutral pressure and separatrix density related models for seed impurity divertor radiation in ASDEX Upgrade journal January 2019
The Plasma Boundary of Magnetic Fusion Devices book January 2000
Inter-ELM Power Decay Length for JET and ASDEX Upgrade: Measurement and Comparison with Heuristic Drift-Based Model journal November 2011
Impact of E × B shear flow on low-n MHD instabilities journal May 2017
Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER journal August 2017
Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks journal December 2011
Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths journal May 2018

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