Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

Nygren, R.E.; Tabarés, F.L.

doi:10.1016/j.nme.2016.08.008

Cited by 97 publications

(58 citation statements)

References 98 publications

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“…Liquid Li PFCs would continuously flow out of a reactor for fuel extraction (and possibly heat removal, with fast flow) before being returned. Several concepts for extraction of tritium from lithium have been proposed [8,9], though large scale extraction from liquids remains an open challenge perhaps larger than trace retention in solids [9][10][11].…”

Section: Pacs Numbersmentioning

confidence: 99%

Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment

et al. 2017

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Section: Pacs Numbersmentioning

confidence: 99%

Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment

et al. 2017

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“…To be more specific, these service conditions include high-energy neutron (14.1 MeV) bombardments, highfluence-rate plasma erosions [10 24 H + m −2 s −1 (1-10 eV), 10 22 -10 24 He 2+ m −2 s −1 (< 500 eV)], and intense thermal loads (up to 20 MW m −2 ) [1,[38][39][40][41][42]. Furthermore, transient pulsed heat loadings (up to GW m −2 ) by major disruptions, vertical displacement events, and edge localized modes could also be applied to the divertor surfaces.…”

Section: Pfms and Wkmentioning

confidence: 99%

“…and alloys (W-Re, etc.). Pertinent reviews of W-based materials for fusion applications are well organized [2,4,8,9,13,15,22,28,36,[41][42][43][44][45][46][47][48][49][50]. However, WK as a rapidly developed PFM has not been specially summarized yet.…”

Section: Pfms and Wkmentioning

confidence: 99%

Tungsten–potassium: a promising plasma-facing material

2019

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Tungsten-potassium (potassium-doped tungsten or WK), initially known from the electric filament industry, is a promising plasma-facing material (PFM) in future fusion facilities like International Thermonuclear Experimental Reactor (ITER). However, the brittle nature of W and irradiation-induced defects of WK materials may result in a risk of deuterium-tritium reaction failure in fusion reactors. Previous studies revealed that advanced W with ultrafine grains and nanostructures might be able to address these problems. However, K-doped W, a rapidly developed material for PFMs, lacks a systematical summary. In this review, we firstly describe the powder metallurgy and plastic deformation for the preparation of WK. Then, the mechanical properties of WK and thermal shock resistance results are reviewed. Important issues such as irradiation damages from neutron, heavy ion, and plasma (H isotope or He) irradiation are also discussed. Hitherto, WK under irradiations shows comparable or even better performances compared with other counterparts such as ITER grade pure tungsten. This review could be benefitial to the future efforts of improving the ductility and irradiation tolerance of WK materials.

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“…Free-surface flows of Lithium and other liquid metals are considered a promising plasma-facing "first wall" for a nuclear fusion reactor: liquid walls could protect the underlying solid walls from high heat and neutron fluxes [1,2], and have been shown to lead to cleaner [3,4,5,6] and more stable plasmas [7,8].…”

Section: Introductionmentioning

confidence: 99%

Passive and active electromagnetic stabilization of free-surface liquid metal flows

Mirhoseini¹,

Diaz-Pacheco²,

Volpe³

2017

MHD

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Free-surface liquid metal flows tend to be uneven due to instabilities and other effects. Some applications, however, require constant, uniform liquid metal thickness. This is for example the case of liquid walls in nuclear fusion reactors. With this motivation, here we present experimental results on the stabilization of a free-surface flow of Galinstan. The flow was sustained by an electromagnetic induction pump featuring rotating permanent magnets. Evidence is reported of the flowing Galinstan layer becoming flatter in the presence of a sufficiently strong magnetic field, either alone (passive stabilization) or in combination with an electrical current passing through the liquid metal (active stabilization). The results are interpreted in terms of an effective viscosity and effective gravity, respectively.

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Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

Cited by 97 publications

References 98 publications

Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment

Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment

Tungsten–potassium: a promising plasma-facing material

Passive and active electromagnetic stabilization of free-surface liquid metal flows

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