A number of operational transient analyses of the nuclear-powered ship Mutsu have been performed in response to Japanese nuclear safety regulatory concerns. The RETRAN and COBRA-IV computer codes were used to provide a quantitative basis for the safety evaluation of the plant. This evaluation includes a complete loss of load without reactor scram, an excessive load increase incident, and an accidental depressurization of the primary system. The minimum departure from nucleate boiling ratio remained in excess of 1.53 for these three transients. Hence, the integrity of the core was shown to be maintained during these transients. Comparing the transient behaviors with those of land-based pressurized water reactors, the characteristic features of the Mutsu reactor were presented and the safety of the plant under the operational transient conditions was confirmed.


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    Title :

    RETRAN safety analyses of the nuclear-powered ship Mutsu


    Additional title:

    RETRAN-Sicherheitsanalyse fuer das durch Kernenergie angetriebene Schiff Mutsu


    Contributors:
    Naruko, Y. (author) / Ishida, T. (author) / Tanaka, Y. (author) / Futamura, Y. (author)

    Published in:

    Nuclear Technology ; 61 , 2 ; 193-204


    Publication date :

    1983


    Size :

    12 Seiten


    Type of media :

    Article (Journal)


    Type of material :

    Print


    Language :

    English




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