Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI
Author:
Funder
H2020 Euratom
Publisher
IOP Publishing
Subject
Condensed Matter Physics,Nuclear and High Energy Physics
Link
http://iopscience.iop.org/article/10.1088/1741-4326/ab0560/pdf
Reference36 articles.
1. Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices
2. Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices
3. Development of a liquid-metal fusion reactor divertor with a capillary-pore system
4. Liquid-metal plasma-facing component research on the National Spherical Torus Experiment
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