CAC is analytical prediction program to study heat-transfer and fluid-flow characteristics of circular coolant passage. Predicts, as function of time, axial and radial fluid conditions, temperatures of passage walls, rates of flow in each coolant passage, and approximate maximum material temperatures. Written in ANSI standard FORTRAN 77.


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    Title :

    Analyzing Flows In Rocket Nuclear Reactors


    Contributors:
    Clark, J. S. (author) / Walton, J. T. (author) / Mcguire, M. (author)

    Published in:

    Publication date :

    1994-03-01



    Type of media :

    Miscellaneous


    Type of material :

    No indication


    Language :

    English


    Keywords :



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