Refine your search:     
Report No.

Development of fast reactor containment safety analysis code, CONTAIN-LMR, 3; Development and validation of debris-related analysis models

Seino, Hiroshi; Kawaguchi, Munemichi; Izumi, Keitaro*

The CONTAIN-LMR code has been developed in the Japan Atomic Energy Agency to evaluate ex-vessel severe accident progression in a liquid metal fast reactor. As a part of several studies in JAEA, this paper mainly describes a state of the art of a debris-concrete interaction model.



- Accesses





[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.