LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–Metal Shield Technologies for Fusion Reactors
Journal of Fusion Energy ,
Sep 2023
Tanke, V. F. B. , Al, R. S. , Alonso van der Westen, S. , Brons, S. , Classen, I. G. J. , van Dommelen, J. A. W. , van Eck, H. J. N. , et al.
The liquid metal shield laboratory (LiMeS-Lab) will provide the infrastructure to develop, test, and compare liquid metal divertor designs for future fusion reactors. The main research topics of LiMeS-lab will be liquid metal interactions with the substrate material of the divertor, the continuous circulation and capillary refilling of the liquid metal during intense plasma heat loading and the retention of plasma particles in the liquid metal. To facilitate the research, four new devices are in development at the Dutch Institute for Fundamental Energy Research and the Eindhoven University of Technology: LiMeS-AM: a custom metal 3D printer based on powder bed fusion; LiMeS-Wetting, a plasma device to study the wetting of liquid metals on various substrates with different surface treatments; LiMeS-PSI, a linear plasma generator specifically adapted to operate continuous liquid metal loops. Special diagnostic protection will also be implemented to perform measurements in long duration shots without being affected by the liquid metal vapor; LiMeS-TDS, a thermal desorption spectroscopy system to characterize deuterium retention in a metal vapor environment. Each of these devices has specific challenges due to the presence and deposition of metal vapors that need to be addressed in order to function. In this paper, an overview of LiMeS-Lab will be given and the conceptual designs of the last three devices will be presented.
LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–Metal Shield Technologies for Fusion Reactors
Journal of Fusion Energy (2023)42:44
https://doi.org/10.1007/s10894-023-00379-3
(0123456789().,-volV)(0123456789().
,- volV)
REVIEW ARTICLE
LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–
Metal Shield Technologies for Fusion Reactors
V. F. B. Tanke1 • R. S. Al1 • S. Alonso van der Westen1 • S. Brons1 • I. G. J. Classen1 • J. A. W. van Dommelen2 •
H. J. N. van Eck1 • M. G. D. Geers2 • N. J. Lopes Cardozo3 • H. J. van der Meiden1 • C. A. Orrico3 •
M. J. van de Pol1 • M. Riepen4 • P. Rindt3 • T. P. de Rooij3 • J. Scholten1 • R. H. M. Timmer1 •
J. W. M. Vernimmen1 • E. G. P. Vos1 • T. W. Morgan1,3
Accepted: 2 August 2023
The Author(s) 2023
Abstract
The liquid metal shield laboratory (LiMeS-Lab) will provide the infrastructure to develop, test, and compare liquid metal
divertor designs for future fusion reactors. The main research topics of LiMeS-lab will be liquid metal interactions with the
substrate material of the divertor, the continuous circulation and capillary refilling of the liquid metal during intense plasma
heat loading and the retention of plasma particles in the liquid metal. To facilitate the research, four new devices are in
development at the Dutch Institute for Fundamental Energy Research and the Eindhoven University of Technology:
LiMeS-AM: a custom metal 3D printer based on powder bed fusion; LiMeS-Wetting, a plasma device to study the wetting
of liquid metals on various substrates with different surface treatments; LiMeS-PSI, a linear plasma generator specifically
adapted to operate continuous liquid metal loops. Special diagnostic protection will also be implemented to perform
measurements in long duration shots without being affected by the liquid metal vapor; LiMeS-TDS, a thermal desorption
spectroscopy system to characterize deuterium retention in a metal vapor environment. Each of these devices has specific
challenges due to the presence and deposition of metal vapors that need to be addressed in order to function. In this paper,
an overview of LiMeS-Lab will be given and the conceptual designs of the last three devices will be presented.
Keywords Fusion technology Plasma-facing components Liquid metals Lithium Tin
Introduction
Tungsten is considered the baseline divertor plasma facing
material (PFM) for many conceptual designs of DEMOscale fusion reactors [1–3]. While for a quiescent and
steady plasma and heat load tungsten appears to fulfil the
& T. W. Morgan
1
Dutch Institute for Fundamental Energy Research, De Zaale
20, 5612 AJ Eindhoven, The Netherlands
2
Department of Mechanical Engineering, Eindhoven
University of Technology, Groene Loper 3,
5612 AE Eindhoven, The Netherlands
3
Science and Technology of Nuclear Fusion, Eindhoven
University of Technology, Groene Loper 3,
5612 AE Eindhoven, The Netherlands
4
ASML, De Run 6501, 5504 DR Veldhoven, The Netherlands
necessary requirements, large edge localized modes
(ELMs) and disruptions, combined with the very high
neutron loads and operational timelines in such devices,
may make long-term operation with such a divertor
untenable. Liquid metals (LMs) have been widely studied
as alternative PFMs that avoid many of the problems
associated with the use of tungsten or other solid PFMs [4].
Liquid tin (Sn) or lithium (Li) are generally considered the
leading candidates for this approach. Several recent
reviews detail the progress and remaining issues in liquid
metal research for fusion [5–7]. One important open
question is the development of technological solutions for
the application of LMs in fusion reactors. Of main concern
is that an open fluid surface is strongly vulnerable to
destabilization by magnetohydrodynamic forces which can
lead to plasma disruption [8]. Currently several different
concepts have been developed and tested to prove the
possibility of liquid metals as PFCs. Two main solutions
123
44
Page 2 of 8
are a thermoelectric magnetohydrodynamics driven fast
flowing fluid between metal trenches on the PFC [9] and a
capillary porous structure (CPS) which holds the metal via
capillary pressure [10]. Some possible reactor implementations for these solutions consist of an externally cooled
LM filled CPS plate resupplied via a recirculating loop [4];
A box or baffled divertor structure with a high density
lithium vapour cloud to cool the plasma while limiting
metal vapor flows to the core plasma [11]; and the flowing
lithium liquid limiter tested at the EAST tokamak [12].
While the aforementioned concepts have shown promise, compared to current day solid armor walls, LMbased technology is less ready and is technologically more
complex. Current levels of knowledge would not be sufficient to confidently introduce this technology to a multibillion Euro large scale fusion reactor. Therefore a stepping
stone approach to develop this technology to a higher level
of readiness via further scientific and technological investigation and improvement is proposed. To date, although
many tokamak experiments using liquid metals have successfully taken place [13–16], experiments with liquid
metal divertors in medium and large-scale tokamak
experimental facilities are lacking. However, the results
from these devices would be the best way to confidently
extrapolate to DEMO generation reactors. This lack is
mainly due to the absence of well-developed and reliable
liquid-metal based divertor plasma-facing components
(PFCs). Typically, solid PFC designs are tested in highheat flux and plasma loading facilities [17–19]. However,
LM PFCs specifically require high temperature coolants
and liquid metal supply loops which do not exist within
current facilities of this type, and the liquid metal can
contaminate the vacuum systems and diagnostic ports of
multi-purpose facilities. Therefore, this project will
develop a dedicated liquid metal laboratory which can
provide the link between small scale prototype development and larger-scale deployment. Although this project
will predominantly focus on the CPS concept for LMPFCs, the laboratory will also be instrumental for studying
other LM PFC concepts such as the previously mentioned
box divertor and flowing designs.
Within this liquid metal laboratory, the current liquid
metal CPS divertor concepts can further mature to technology suitable for future reactors, by addressing the following challenges:
• Reliably producing tungsten capillary porous structures
(CPS) with optimal pore sizes and high strength by
means of additive manufacturing.
• Wetting and filling of manufactured CPS targets with
the liquid metal in order to take advantage of the
capillary refilling during operation.
123
Journal of Fusion Energy (2023)42:44
• Liquid surface stability and heat load handling capability of a circulating liquid metal in a CPS target
design under plasma exposure.
• Retention of hydrogen isotopes by the liquid metal and
the prevention of impurity formation in the liquid metal
that can result in clogging.
The Liquid Metal Shield (...truncated)
This is a preview of a remote PDF: https://link.springer.com/content/pdf/10.1007/s10894-023-00379-3.pdf
Article home page: https://link.springer.com/article/10.1007/s10894-023-00379-3
Tanke, V. F. B., Al, R. S., Alonso van der Westen, S., Brons, S., Classen, I. G. J., van Dommelen, J. A. W., van Eck, H. J. N., Geers, M. G. D., Lopes Cardozo, N. J., van der Meiden, H. J., Orrico, C. A., van de Pol, M. J., Riepen, M., Rindt, P., de Rooij, T. P., Scholten, J., Timmer, R. H. M., Vernimmen, J. W. M., Vos, E. G. P., Morgan, T. W..
LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–Metal Shield Technologies for Fusion Reactors ,
Journal of Fusion Energy,
2023, pp. 1-8, Volume 42, Issue 2, DOI: 10.1007/s10894-023-00379-3