The lithium vapor box divertor

Goldston, Robert James; Myers, Richard A.; Schwartz, Jacob

doi:10.1088/0031-8949/t167/1/014017

Cited by 49 publications

(50 citation statements)

References 12 publications

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“…The influence of Γ supply , surface layer thickness, cool , t, and R is visualized in fig. acceptable ← Γnet [23] acceptable ← Γnet with vapor box [24] Net Li loss rate, Γ net [1/m Illustrated is also the influence of cool (dashed), which mainly impacts the regime where dissipation via lithium is dominant, and R (solid), which impacts surface temperature to reach a given Γnet and thus the conductive dissipation. The cyan line illustrates the effect of increasing the target conductance with a factor of 2.…”

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confidence: 99%

Power handling limit of liquid lithium divertor targets

et al. 2018

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A model is formulated to make a first estimate of the maximum tolerable power of liquid lithium divertor targets, and to gain insight into their behavior in terms of lithium loss rate and surface temperature. The model, formulated as a simple analytical expression, states that the incoming power is balanced by heat conduction through the target and by the lithium which is dissipating energy in the plasma by ionizing and radiating. A target is considered to fail when the net lithium loss flux from the surface exceeds the available supply. The model is evaluated over a range of input parameters: lithium supply rate, surface layer thickness, redeposition coefficient, and dissipated energy per Li particle lost to the plasma. Based on the results, first, surface temperature locking is expected above a deposited power of ∼ 10 MW/m 2. Second, lithium targets are expected to be extremely robust against power deposited during short transient events. A surface layer thickness of 50 micron is sufficient to withstand 60 MJ/m 2 vertical displacement events or 20 MJ/m 2 disruptions.

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confidence: 99%

Power handling limit of liquid lithium divertor targets

et al. 2018

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“…Tungsten and beryllium as the plasma facing materials of ITER have problems even during steady state plasma operation. Nowadays, a lithium vapour box [7] is being considered as an alternative divertor concept, which can reduce the parallel heat fluxes by 4 orders of magnitude for the DEMO conditions, namely from 20 GW/m 2 down to about 2 MW/m 2 [8], with moderate lithium efflux from the box to the plasma core. The design of lithium vapour boxes compatible with continuous liquid lithium flow has been developed for DEMO-FNS.…”

Section: Concept Of Lithium Vapor Box For Demo-fns Divertormentioning

confidence: 99%

Progress in the design of the DEMO-FNS hybrid facility

Shpanskiy¹

2019

Nucl. Fusion

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Further development of a fusion-fission hybrid facility based on superconducting tokamak DEMO-FNS [1] continues in Russia for integrated commissioning of steady-state and nuclear fusion technologies at the power level up to 40 MW fusion and 400 MW fission reactions. This facility is considered as the main source of technological and nuclear scientific information in the RF National program on controlled fusion and plasma technologies that is currently being developed and submitted to the authorities for approval.

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“…Away from exposed liquid or vapour-based proposals [5,6] which have a number of significant outstanding technical and physics challenges, leading concepts broadly fall into two categories: water cooled pipes in tungsten monoblocks similar to the design used for ITER [7] and helium cooled thimbles or pipes employing jet impingement [8]. Figure 1 shows two example divertor target designs: one ITER-like and the other a helium-cooled alternative.…”

Section: Divertor Target State Of the Artmentioning

confidence: 99%

“…For fusion, this has included use as both coolant and as plasma facing material for blanket and divertor applications (e.g. [57,6,58,59]), to the extent that a lead-lithium divertor was included as the baseline of the most advanced of the European powerplant conceptual study concepts [45].…”

Section: Liquid Metalsmentioning

confidence: 99%

Refractory metals as structural materials for fusion high heat flux components

Hancock

Homfray

Porton

et al. 2018

Journal of Nuclear Materials

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Tungsten is the favoured armour material for plasma facing components for future fusion reactors, but studies examining the use of tungsten or other refractory metals in the underlying cooled structures have historically excluded them, leaving current concepts heavily dependent on copper alloys such as copper chrome zirconium. This paper first outlines the challenge of selecting an appropriate alternative material for this application, with reference to historical selection methodology and design solutions, and then reexamines the use of refractory metals in the light of current design priorities and manufacturing techniques. The rationale for considering refractory alloys as structural materials is discussed, showing how this is the result of relatively small changes to the logic previously applied, with a greater emphasis on high temperature operation, a re-evaluation of current costs, a relaxation of absolute activation limits, and the availability of advanced manufacturing techniques such as additive manufacturing. A set of qualitative and quantitative assessment criteria are proposed, drawing on the requirements detailed in the first section; including thermal and mechanical performance, radiation damage tolerance, manufacturability, and cost and availability. Considering these criteria in parallel rather than sequence gives a less binary approach to material selection and instead provides a strengths and weaknesses based summary from which more nuanced conclusions can be drawn. Data on relevant material properties for a range of candidate materials, including elemental refractory metals and a selection of related alloys are gathered from a range of sources and collated using a newly developed set of tools written in the python language. These tools are then used to apply the aforementioned assessment criteria and display the results. The lack of relevant data for a number of promising materials is highlighted, and although a conclusive best material cannot be identified, refractory alloys in general are proposed as worthy of further investigation.

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The lithium vapor box divertor

Cited by 49 publications

References 12 publications

Power handling limit of liquid lithium divertor targets

Power handling limit of liquid lithium divertor targets

Progress in the design of the DEMO-FNS hybrid facility

Refractory metals as structural materials for fusion high heat flux components

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