标题
Conceptual design of a liquid-metal divertor for the European DEMO
作者
关键词
DEMO, Liquid metal, Divertor
出版物
FUSION ENGINEERING AND DESIGN
Volume 173, Issue -, Pages 112812
出版商
Elsevier BV
发表日期
2021-08-07
DOI
10.1016/j.fusengdes.2021.112812
参考文献
相关参考文献
注意:仅列出部分参考文献,下载原文获取全部文献信息。- Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues
- (2021) Jeong-Ha You et al. FUSION ENGINEERING AND DESIGN
- Nuclear loads and nuclear shielding performance of EU DEMO divertor: A comparative neutronics evaluation of two interim design options
- (2020) J.H. You et al. Nuclear Materials and Energy
- High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign
- (2020) J.H. You et al. JOURNAL OF NUCLEAR MATERIALS
- Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses
- (2019) P. Rindt et al. NUCLEAR FUSION
- Designs and technologies for plasma-facing wall protection in EU DEMO
- (2019) Thomas R. Barrett et al. NUCLEAR FUSION
- Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI
- (2019) P. Rindt et al. NUCLEAR FUSION
- An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort
- (2019) G. Federici et al. FUSION ENGINEERING AND DESIGN
- Deuterium retention in Sn-filled samples exposed to fusion-relevant flux plasmas
- (2019) Wei Ou et al. NUCLEAR FUSION
- Wall protection strategies for DEMO plasma transients
- (2018) F. Maviglia et al. FUSION ENGINEERING AND DESIGN
- The thermo-mechanical behaviour of W-Cu metal matrix composites for fusion heat sink applications: The influence of the Cu content
- (2018) E. Tejado et al. JOURNAL OF NUCLEAR MATERIALS
- Evolution of mechanical performance with temperature of W/Cu and W/CuCrZr composites for fusion heat sink applications
- (2018) E. Tejado et al. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
- Power handling limit of liquid lithium divertor targets
- (2018) Peter Rindt et al. NUCLEAR FUSION
- Integrated core-SOL-divertor modelling for DEMO with tin divertor
- (2017) M. Poradziński et al. FUSION ENGINEERING AND DESIGN
- A stepladder approach to a tokamak fusion power plant
- (2017) H. Zohm et al. NUCLEAR FUSION
- European DEMO design strategy and consequences for materials
- (2017) G. Federici et al. NUCLEAR FUSION
- Tritium resources available for fusion reactors
- (2017) M. Kovari et al. NUCLEAR FUSION
- Liquid metals as a divertor plasma-facing material explored using the Pilot-PSI and Magnum-PSI linear devices
- (2017) T W Morgan et al. PLASMA PHYSICS AND CONTROLLED FUSION
- Simulation of divertor targets shielding during transients in ITER
- (2016) Sergey Pestchanyi et al. FUSION ENGINEERING AND DESIGN
- Conceptual design studies for the European DEMO divertor: Rationale and first results
- (2016) J.H. You et al. FUSION ENGINEERING AND DESIGN
- The lithium vapor box divertor
- (2016) R J Goldston et al. PHYSICA SCRIPTA
- Self-Regulated Plasma Heat Flux Mitigation Due to Liquid Sn Vapor Shielding
- (2016) G. G. van Eden et al. PHYSICAL REVIEW LETTERS
- ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets
- (2015) B.N. Sorbom et al. FUSION ENGINEERING AND DESIGN
- Advances in the physics basis for the European DEMO design
- (2015) R. Wenninger et al. NUCLEAR FUSION
- Liquid-metal plasma-facing component research on the National Spherical Torus Experiment
- (2013) M A Jaworski et al. PLASMA PHYSICS AND CONTROLLED FUSION
- FTU results with a liquid lithium limiter
- (2011) G. Mazzitelli et al. NUCLEAR FUSION
- Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices
- (2011) D.N. Ruzic et al. NUCLEAR FUSION
- Interlaboratory Test on Thermophysical Properties of the ITER Grade Heat Sink Material Copper–Chromium–Zirconium
- (2010) G. Pintsuk et al. INTERNATIONAL JOURNAL OF THERMOPHYSICS
- Thermocapillary and thermoelectric effects in liquid lithium plasma facing components
- (2009) M.A. Jaworski et al. JOURNAL OF NUCLEAR MATERIALS
- Application of lithium in systems of fusion reactors. 2. The issues of practical use of lithium in experimental facilities and fusion devices
- (2009) I. E. Lyublinski et al. PLASMA DEVICES AND OPERATIONS
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