Presentation Information
[3K04]Conceptual design for the sodium-cooled pool-type fast reactor(9) Core safety evaluation for fuel selection (oxide fuel)
*Yuya Imaizumi1, Enki Kinoshita2, Ryuzaburo Kubota2, Shinya Ishida1, Yuichi Onoda1 (1. JAEA, 2. MFBR)
Keywords:
pool-type sodium-cooled fast reactor,controlled material relocation duct,low sodium void reactivity,SIMMER,ULOF: Unprotected Loss Of Flow
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