2013 Annual Meeting
Session ID : M06
Conference information
Host: Atomic Energy Society of Japan
Development of assessment method to evaluate the material relocation behavior in the core disruptive accident of FBR
(2) Measurement and evaluation of the distance for fragmentation of molten core simulant in liquid-liquid direct contact
Keywords:
sodium-cooled fast reactor,
core disruptive accident,
material relocation,
molten core material,
distance for fragmentation
Details
