SIMMER-IV application to safety assessment of severe accident in a small SFR

A sodium-cooled fast reactor (SFR) core has a potential of prompt criticality due to a change of core material distribution during a severe accident, and the resultant energy release has been one of the safety issues of SFRs. In this study, the safety assessment of an unprotected loss-of-flow (ULOF)...

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Bibliographic Details

Published in:	Nuclear Engineering and Technology
Main Authors:	H. Tagami, Y. Tobita
Format:	Article
Language:	English
Published:	Elsevier 2024-03-01
Subjects:	Severe accident Small sodium-cooled fast reactor (SSFR) Unprotected loss of flow (ULOF) SIMMER-IV Prompt-critical power excursion
Online Access:	http://www.sciencedirect.com/science/article/pii/S173857332300476X