20 research outputs found

    Coupled NOFLOW-FIPDIF Computer Program

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    This report describes the Coupled NOFLOW-FIPDIF computer program which has been written to perform the following two related functions: (1) Determination of the temperature attained by reactor materials following a loss of coolant accident. (2) Evaluation of the fission product inventory which would exist at any time (following loss of coolant)

    C2 support system tests. Computer program to reduce and plot static strain gage data

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    The primary object of the C2 tests for the NRX- A reactor support system is to survey the capabilities of the structure

    Evaluation of the thermal response of three proposed reactor designs to post-operational heating conditions

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    Description of the digital analysis programs used to analyze the wide band test data

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