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Report No.
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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.

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