Nuclear Science and Engineering / Volume 59 / Number 4 / April 1976 / Pages 440-441
Technical Note / dx.doi.org/10.13182/NSE76-A26845
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Recalculation of sodium voiding ramp rates in a loss-of-flow accident for a model of a 4000-MW(e) oxide-fueled liquid-metal fast breeder reactor gave results much lower than those found previously by Bleiweis et al. Only a part of this difference could be ascribed to differences in the primary coolant loop model.