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Report No.
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Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactor, 38; Development of long-term leak enlargement and propagation analysis code

Hamada, Hirotsugu; Uchibori, Akihiro; Ohshima, Hiroyuki

For the purpose of a safety evaluation of heat transfer tube failure in the FBR steam generator, the long-term leak enlargement and propagation analysis code (LEAP-III) is under development. A model of overheating tube rupture was incorporated into LEAP-III and LEAP-III was applied to an analysis of SWAT-3 test to evaluate the applicability of the code.

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