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Options for a high heat flux enabled helium cooled first wall for DEMO

Arbeiter, Frederik 1; Chen, Yuming 1; Ghidersa, Bradut-Eugen 1; Klein, Christine 1; Neuberger, Heiko 1; Ruck, Sebastian 1; Schlindwein, Georg 1; Schwab, Florian 1; Weth, Axel von der 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

Helium is considered as coolant in the plasma facing first wall of several blanket concepts for DEMO fusion reactors, due to the favorable properties of flexible temperature range, chemical inertness, no activation, comparatively low effort to remove tritium from the gas and no chemical corrosion. Existing blanket designs have shown the ability to use helium cooled first walls with heat flux densities of 0.5 MW/m2. Average steady state heat loads coming from the plasma for current EU DEMO concepts are expected in the range of 0.3 MW/m2. The definition of peak values is still ongoing and depends on the chosen first wall shape, magnetic configuration and assumptions on the fraction of radiated power and power fall off lengths in the scrape off layer of the plasma. Peak steady state values could reach and excess 1 MW/m2. Higher short-term transient loads are expected.

Design optimization approaches including heat transfer enhancement, local heat transfer tuning and shape optimization of the channel cross section are discussed. Design points to enable a helium cooled first wall capable to sustain heat flux densities of 1 MW/m2 at an average shell temperature lower than 500 °C are developed based on experimentally validated heat transfer coefficients of structured channel surfaces. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000069606
Veröffentlicht am 02.03.2018
Originalveröffentlichung
DOI: 10.1016/j.fusengdes.2017.04.083
Scopus
Zitationen: 9
Dimensions
Zitationen: 10
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2017
Sprache Englisch
Identifikator ISSN: 0920-3796, 1873-7196
urn:nbn:de:swb:90-696069
KITopen-ID: 1000069606
HGF-Programm 31.03.06 (POF III, LK 01) Brutblanket-Entwicklung
Erschienen in Fusion engineering and design
Verlag Elsevier
Band 119
Seiten 22–28
Schlagwörter Plasma Facing Components; First Wall; Helium; Thermo-mechanics; Heat transfer enhancement; Design optimization
Nachgewiesen in Dimensions
Scopus
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