Outcomes of the French ICE project on Fuel Coolant Interaction

von Meignen, Renaud
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 5 of 14 (2018)

Influence of Steel Properties on the Progression of a Severe Accident: Measurement of 304L and 16Mnd5 Steel Density and Surface Tension

von Chikhi, Nourdine
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 2 of 14 (2018)

Corrosion of refractories

von Quirmbach, Peter Raimund
Veröffentlicht 2018

Experiments Linked to Fuel Coolant Interaction within The Euro-Chinese Project ALISA

von Cassiaut-Louis, Nathalie
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 5 of 14 (2018)

Corium-Sodium and Corium-Water Fuel-Coolant-Interaction Experimental Programs for the PLINIUS-2 Prototypic Corium Platform

von Journeau, Christophe G.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 2 of 14 (2018)