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Title: Generalization of the Heuristic Drift SOL model for finite collisionality and effect on flow shearing rate vs. interchange growth rate

Journal Article · · Nuclear Materials and Energy

We generalize the low-gas-puff Heuristic Drift (HD) model of the power scrape-off layer width to take into account both the enhanced parallel confinement time in the SOL at high collisionality, due to enhanced thermal resistivity, and the increase of the upstream temperature at very low collisionality, due to finite target temperature. We find a wide range of separatrix densities over which the original HD model is applicable. However, at the region of high separatrix density and collisionality accessible with strong gas puffs the SOL widens, in reasonable agreement with experimental data from ASDEX-Upgrade and JET. We further find that for typical low-gas-puff H-mode conditions, the projected E x B flow shearing rate in the SOL dominates over the interchange growth rate, while at the high separatrix densities at which H-Modes return to L-Mode, the interchange growth rate approximately equals the shearing rate. The result is related to that of Halpern and Ricci with respect to the steep gradient region of the SOL of inner-wall-limiter discharges, which also show HD-like scale lengths. It is also consistent with calculations of shear-flow stabilization of interchange modes by Zhang and Krasheninnikov. Taking ωs > γint as the criterion for retaining H-Mode performance, we use the generalized HD (GHD) model to predict the scaling for the H→L back transition. The power requirements to sustain H-Mode for existing machines and for ITER are in the range of a factor of 2 below the predictions for the L→H transition, consistent with the limited available studies of H-Mode hysteresis. We find reasonable agreement with the scaling of the density at the H→L back transition found by Bernert on ASDEX-Upgrade. Finally, we speculate that the shearing rate in the SOL of H-Mode plasmas contributes to the reduced core turbulence that supports the formation of the H-Mode pedestal and comment on the implications for ITER.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1786396
Alternate ID(s):
OSTI ID: 1818956
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Vol. 27 Journal Issue: C; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (10)

Latest results on the H-mode threshold using the international H-mode threshold database journal May 2000
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
The H-mode density limit in the full tungsten ASDEX Upgrade tokamak journal November 2014
Theoretical aspects and practical implications of the heuristic drift SOL model journal August 2015
The back transition and hysteresis effects in DIII-D journal May 1998
Simple models for the radial and poloidal E × B drifts in the scrape-off layer of a divertor tokamak: Effects on in/out asymmetries journal July 1996
Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks journal December 2011
A new scaling for divertor detachment journal March 2017
Velocity shear, turbulent saturation, and steep plasma gradients in the scrape-off layer of inner-wall limited tokamaks journal December 2016

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