A 2-D correlation to evaluate fuel-cladding gap thermal conductance in mixed oxide fuel elements for sodium-cooled fast reactors

Bubelis, E.; Chauvin, N.; Davies, U.; Gianfelici, S.; Gicquel, S.; Krepel, J.; Lainet, M.; Lavarenne, J.; Lindley, B.; Mikityuk, K.; Murphy, C.; Perrin, B.; Pfrang, W.; Ponomarev, A.; Schubert, A.; Shwageraus, E.; Stopher, M.; Van Uffelen, P.; Zhao, X.

A 2-D correlation to evaluate fuel-cladding gap thermal conductance in mixed oxide fuel elements for sodium-cooled fast reactors

Bubelis, E.; Chauvin, N.; Davies, U.; Gianfelici, S.; Gicquel, S.; Krepel, J.; Lainet, M.; Lavarenne, J.; Lindley, B.; Mikityuk, K.; Murphy, C.; Perrin, B.; Pfrang, W.; Ponomarev, A.; Schubert, A.; Shwageraus, E.; Stopher, M.; Van Uffelen, P.; Zhao, X.

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Seitenaufrufe: 54
seit 17.05.2019

Zugehörige Institution(en) am KIT	Institut für Kern- und Energietechnik (IKET)
Publikationstyp	Vortrag
Publikationsjahr	2019
Sprache	Englisch
Identifikator	KITopen-ID: 1000094567
HGF-Programm	32.01.12 (POF III, LK 01) Transmutation:Sicherheitsanal.u.Studien
Veranstaltung	14th International Nuclear Fuel Cycle Performance Conference / Light Water Reactor Fuel Conference (GLOBAL / TOP FUEL 2019), Seattle, WA, USA, 22.09.2019 – 27.09.2019

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A 2-D correlation to evaluate fuel-cladding gap thermal conductance in mixed oxide fuel elements for sodium-cooled fast reactors