Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commissions Division of Reactor Safety Research, October--December 1976
Description:
Light water reactor safety research performed October through December 1976 is discussed. An analysis to determine the effect of emergency core coolant (ECC) injection location and pump speed on system response characteristics was performed. An analysis to evaluate the capability of commonly used critical heat flux (CHF) correlations to calculate the time of the first CHF in the Semiscale core during a loss-of-coolant experiment (LOCE) was performed. A test program and study to determine the ef…
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Date:
April 1977
Creator:
Ferguson, J. B.
Item Type:
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