Open Access
Interactions between Liquid-Wall Vapor and Edge Plasmas
T.D. Rognlien,M.E. Rensink +1 more
TLDR
In this paper, the authors analyzed the influx of impurity ions to the core plasma from the vapor of liquid side-walls for a slab geometry which approximates the edge region of a reactor-size tokamak.Abstract:
The use of liquid walls for fusion reactors could help solve problems associated with material erosion from high plasma heat-loads and neutronic activation of structures. A key issue analyzed here is the influx of impurity ions to the core plasma from the vapor of liquid side-walls. Numerical 2D transport simulations are performed for a slab geometry which approximates the edge region of a reactor-size tokamak. Both lithium vapor (from Li or SnLi walls) and fluorine vapor (from Flibe walls) are considered for hydrogen edge-plasmas in the high- and low-recycling regimes. It is found that the minimum influx is from lithium with a low-recycling hydrogen plasma, and the maximum influx occurs for fluorine with a high-recycling hydrogen plasma.read more
Citations
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Journal ArticleDOI
Deuterium retention in liquid lithium
TL;DR: In this article, the authors measured deuterium retention in samples of lithium exposed in the liquid state to deutium plasma using thermal desorption spectrometry and found that full uptake was consistent with the full uptake of all ion incident on the liquid metal surface and was independent of the temperature of liquid lithium over the range explored.
Journal ArticleDOI
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI
TL;DR: A review of the potential of robust PFCs with liquid surfaces for applications in future D/T fusion device summarizes the critical issues for liquid surfaces and research being done worldwide in confinement facilities, and supporting R&D in plasma surface interactions as mentioned in this paper.
Journal ArticleDOI
Modeling of sputtering erosion/redeposition—status and implications for fusion design
TL;DR: In this paper, the authors present a review of sputtering erosion/redeposition modeling for plasma facing surfaces and present an example analysis for erosion of a liquid tin fusion reactor divertor.
Journal ArticleDOI
Lithium coating for H-mode and high performance plasmas on EAST in ASIPP
TL;DR: Recently, routine coatings of plasma facing materials with lithium were carried out on EAST using both upgraded evaporative ovens and real-time injection of lithium powder as discussed by the authors, achieving a 10 s H-mode plasma.
A fusion reactor design with a liquid first wall and divertor.
M.E. Rensink,M. Z. Sawan,Sergey Smolentsev,M. E. Youssef,T.D. Rognlien,D.-K. Sze,Richard Majeski,B.E. Nelson,Richard Einar Nygren,C. Eberle,P.J. Fogarty +10 more
TL;DR: The ARIES-RS as mentioned in this paper is a prototype of a future fusion reactor with liquid wall technology for a first wall and divertor and a blanket with adequate tritium breeding.
References
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Journal ArticleDOI
Deuterium retention in liquid lithium
TL;DR: In this article, the authors measured deuterium retention in samples of lithium exposed in the liquid state to deutium plasma using thermal desorption spectrometry and found that full uptake was consistent with the full uptake of all ion incident on the liquid metal surface and was independent of the temperature of liquid lithium over the range explored.
Journal ArticleDOI
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI
TL;DR: A review of the potential of robust PFCs with liquid surfaces for applications in future D/T fusion device summarizes the critical issues for liquid surfaces and research being done worldwide in confinement facilities, and supporting R&D in plasma surface interactions as mentioned in this paper.
Journal ArticleDOI
Modeling of sputtering erosion/redeposition—status and implications for fusion design
TL;DR: In this paper, the authors present a review of sputtering erosion/redeposition modeling for plasma facing surfaces and present an example analysis for erosion of a liquid tin fusion reactor divertor.
Journal ArticleDOI
A fusion reactor design with a liquid first wall and divertor
Richard E. Nygren,T.D. Rognlien,M.E. Rensink,Sergey Smolentsev,M.Z. Youssef,Mohamed E. Sawan,Brad J. Merrill,C. Eberle,P.J. Fogarty,B.E. Nelson,D.-K. Sze,Richard Majeski +11 more
TL;DR: The ARIES-RS as discussed by the authors is a prototype of a future fusion reactor with liquid wall technology for a first wall and divertor and a blanket with adequate tritium breeding.
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