NEDO-10527, "Rod Drop Accident Analysis For Large Boiling Water Reactors."
نویسندگان
چکیده
This report describes the current methods used by the Atomic Power Equipment Depart ment of the Genervl Electric Company for the analysis of superprompr critical nuclear excurions in lare war-rnsoderantd reactors The 7mchnical analysis tools used in studying hypothetical nuclear transients adescribed herein, without considering the probability of such an occurrence. The rod drop accident has been reanalyzed generically using the improved methtods, and the results of thew analysts are presented. In addition, derauled sensitiviry studies have been performed to evaluate the effects of initial reactor conditions, control rod worth, rod drop velocity, and scram instrton rate on the ruiltant peak fuel enthalpy.
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