Modeling detachment physics in the NSTX snowflake divertor
Creators
- 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.2015.01.007Additional 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.