Presentation Information
[2H06]Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors(42) Model Validation by Analysis of Eutectic Reaction Experiments
*Koji Morita1, Hidemasa Yamano2 (1. Kyushu Univ., 2. JAEA)
Keywords:
sodium-cooled fast reactor,core disruptive accident,B4C-SS eutectic melting reaction,safety analysis code,model validation
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