Published August 2015 | Version v1
Journal article

Modeling detachment physics in the NSTX snowflake divertor

  • 1. Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)
  • 2. Princeton Plasma Physics Laboratory, Princeton, NJ 08540 (United States)

Description

The snowflake divertor is a proposed technique for coping with the tokamak power exhaust problem in next-step experiments and eventually reactors, where extreme power fluxes to material surfaces represent a leading technological and physics challenge. In lithium-conditioned National Spherical Torus Experiment (NSTX) discharges, application of the snowflake divertor typically induced partial outer divertor detachment and severalfold heat flux reduction. UEDGE is used to analyze and compare conventional and snowflake divertor configurations in NSTX. Matching experimental upstream profiles and divertor measurements in the snowflake requires target recycling of 0.97 vs. 0.91 in the conventional case, implying partial saturation of the lithium-based pumping mechanism. Density scans are performed to analyze the mechanisms that facilitate detachment in the snowflake, revealing that increased divertor volume provides most of the parallel heat flux reduction. Also, neutral gas power loss is magnified by the increased wetted area in the snowflake, and plays a key role in generating volumetric recombination

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2015.01.007

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2015.01.007;
PII
S0022-3115(15)00011-2;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
463
Journal Page Range
p. 1200-1204
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
21. international conference on plasma-surface interactions in controlled fusion devices
Acronym
Plasma-Surface Interactions 21
Dates
26-30 May 2014
Place
Kanazawa (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
47030401
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DIVERTORS; ELECTRIC DISCHARGES; HEAT FLUX; LITHIUM; NSTX DEVICE; PLASMA DENSITY; PLASMA SIMULATION; POWER LOSSES; RECYCLING; SPHERICAL CONFIGURATION; SURFACES; U CODES
Descriptors DEC
ALKALI METALS; CLOSED PLASMA DEVICES; COMPUTER CODES; CONFIGURATION; ELEMENTS; ENERGY LOSSES; EVALUATION; LOSSES; METALS; SIMULATION; SPHEROMAK DEVICES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.