Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U
Authors:
- P. RindtPRP. Rindt
- N.J. Lopes CardozoNCN.J. Lopes Cardozo
- J.A.W. van DommelenJDJ.A.W. van Dommelen
- R. KaitaRKR. Kaita
- M.A. JaworskiMJM.A. Jaworski
Open Access
- 1 November 2016
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 112, 204-212
Abstract
No abstract availableKeywords
This publication has 25 references indexed in Scilit:
- Self-Regulated Plasma Heat Flux Mitigation Due to Liquid Sn Vapor ShieldingPhysical Review Letters, 2016
- Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performanceFusion Engineering and Design, 2013
- Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmasNuclear Fusion, 2013
- Laboratory Investigation of Vapor Shielding for Lithium-Coated Molybdenum in DevexIEEE Transactions on Plasma Science, 2012
- FTU results with a liquid lithium limiterNuclear Fusion, 2011
- Recent analysis of key plasma wall interactions issues for ITERJournal of Nuclear Materials, 2009
- Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devicesPlasma Physics and Controlled Fusion, 2006
- Testing of liquid lithium limiters in CDX-UFusion Engineering and Design, 2004
- Calculation and experimental investigation of fusion reactor divertor plate and first wall protection by capillary-pore systems with lithiumJournal of Nuclear Materials, 1999
- Development of a liquid-metal fusion reactor divertor with a capillary-pore systemJournal of Nuclear Materials, 1996