A literature search of available technical publications, and a survey of recent experiments and current practices relevant to the prediction of heat transfer in a containment building following a loss-of-coolant accident have been completed. Very little information with direct applicability to large power reactor containments is available on which to base concrete recommendations. A correlation based on the work of Tagami is suggested for use in safety analyses because its trend is consistent with the Carolinas Virginia Tube Reactor (CVTR) measurements and because its use leads to predicted containment pressures being higher and thus more conservative than those measured at CVTR. This conservatism is desired because of the uncertainty associated with extrapolating results from atypical small-scale experiments to large power plants.
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