Presentation Information
[3K07]Development of Integrated Severe Accident Analysis Code fof Sodium-cooled Fast Reactors(2)Outline of In-vessel Analysis Method and its Preliminary Application to Reactor Scale Analysis
*Hiroki Sonoda1, Satoshi Fujita1, Masaaki Inoue1 (1. NRA)
Keywords:
Sodium-cooled Fast Reactors,Severe Accident,FP transfer behavior,Analysis Code
Password required to view
If you have already registered, please click the login button below to log in with your Confit account.
Invitees and Proceedings purchasers, please enter your password in the password box below.
Invitees and Proceedings purchasers, please enter your password in the password box below.
Log in
or
Comment
To browse or post comments, you must log in.Log in