Articles with "divertor" as a keyword



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Calculation of the Heat Flux on the First Wall During Disruption on Tokamak

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Published in 2017 at "Journal of Fusion Energy"

DOI: 10.1007/s10894-016-0118-6

Abstract: Disruptions are the most dangerous instabilities in tokamak plasma. During plasma disruption, the large amounts of energy will be deposited on Plasma Facing Components (PFCs) which is a damaging threat for the divertor target and… read more here.

Keywords: divertor; disruption; first wall; heat ... See more keywords
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CPS Based Liquid Metal Divertor Target for EU-DEMO

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Published in 2020 at "Journal of Fusion Energy"

DOI: 10.1007/s10894-020-00263-4

Abstract: Power exhaust is a key mission in the roadmap to the realization of a future fusion reactor. Among the different solutions, the use of liquid metals as plasma facing materials are of interest due to… read more here.

Keywords: liquid metal; metal divertor; metal; cps based ... See more keywords

Influence of Krypton Seeding on EU DEMO Operation with Lithium Divertor

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Published in 2020 at "Journal of Fusion Energy"

DOI: 10.1007/s10894-021-00283-8

Abstract: DEMO reactor with liquid lithium divertor operation in presence of krypton seeding is analyzed. Integrated core-scrape-off layer-divertor code COREDIV is used. Sputtering model is revised and sputtering dependence on the divertor surface temperature fitted to… read more here.

Keywords: krypton seeding; divertor; lithium divertor; demo operation ... See more keywords
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Feasibility study of fast swept divertor strike point suppressing transient heat fluxes in big tokamaks

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.01.027

Abstract: Abstract In order to avoid metal surface melting of divertor targets of big tokamak fusion reactors by localized ELM heat loads, sudden detachment loss or VDEs, we study a new technique of spreading the heat… read more here.

Keywords: strike point; heat fluxes; divertor strike; big tokamaks ... See more keywords
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Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.02.013

Abstract: Abstract One of the fundamental input parameters required for the thermo hydraulic and structural design of a divertor cassette is the operation temperature range. In the current design activities to develop European DEMO divertor in… read more here.

Keywords: temperature; demo; divertor cassette; divertor ... See more keywords
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Degradation of tungsten monoblock divertor under cyclic high heat flux loading

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.04.102

Abstract: Abstract The degradation behavior of the ITER divertor under the cyclic high heat flux loading has been varied in the previous studies, which would be induced by the intrinsic difference in the thermo-mechanical properties of… read more here.

Keywords: degradation; high heat; cyclic high; heat flux ... See more keywords
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Qualification, manufacturing and assembly of the WEST divertor structure and coils

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.04.104

Abstract: Abstract In order to fully validate “ITER-like” actively water cooled tungsten plasma facing units, addressing the issues of long plasma discharges, an axisymmetric divertor structure has been studied and manufactured for the implementation in the… read more here.

Keywords: structure coils; order; divertor structure; manufacturing ... See more keywords
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Study on divertor heat flux of L-H transition with LHCD and NBI in EAST

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.04.110

Abstract: Abstract An infrared (IR)/visible endoscope system was built on the Experimental Advanced Superconducting Tokamak (EAST) in 2014. The temperature distributions of the lower divertor have been measured. Based on the IR data of EAST, the… read more here.

Keywords: transition; study; heat flux; heat ... See more keywords
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An optimized upper divertor with divertor-coils to study enhanced divertor configurations in ASDEX Upgrade

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.05.074

Abstract: Abstract A new upper divertor with in-vessel coils to investigate ‘advanced’ magnetic configurations will be installed in ASDEX Upgrade. ‘Advanced’ magnetic configurations are part of a risk mitigation strategy should the conventional divertor configuration approach… read more here.

Keywords: asdex upgrade; upper divertor; optimized upper; divertor divertor ... See more keywords
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Effect of ELMS and disruptions on FNSF plasma-facing components

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Published in 2017 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2017.07.022

Abstract: Abstract Previous work has addressed the thermomechanical and electromagnetic effects of ELMs and disruptions on plasma-facing components in conceptual, commercial fusion reactors. Given that the proposed Fusion Nuclear Science Facility (FNSF) will have different geometry… read more here.

Keywords: facing components; effect; plasma facing; first wall ... See more keywords
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EU contribution to the procurement of blanket first wall and divertor components for ITER

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Published in 2018 at "Fusion Engineering and Design"

DOI: 10.1016/j.fusengdes.2018.04.050

Abstract: Abstract Fusion for Energy (F4E), the European Domestic Agency for ITER, is responsible for a significant share of the overall procurement of internal components inside the vacuum vessel, the largest ones being as follows: (1)… read more here.

Keywords: first wall; blanket first; contribution procurement; procurement ... See more keywords