Abstract
Abstract This paper presents methods and results of a theoretical investigation of the dynamic response of large oxide-fueled fast reactor cores during transient over-power or under-flow situations which result in bulk boiling of the coolant. The validity of the analysis is restricted to the regime before the cladding melts or fails otherwise; that is, before material motion other than that due to thermal expansion is experienced. The model and computational scheme for predicting coolant boiling (sodium voiding) behavior, described in an earlier paper, has been incorporated into a closed loop calculation which includes reactor kinetics with sodium voiding and Doppler reactivity feedbacks. The results of calculations for power increase (reactivity ramp) transients for two cores with different geometry are presented and compared. Results of calculations for a flow coastdown transient are also presented and discussed. Some of the limitations of the model and method are also discussed briefly.
Published Version
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