Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 59 / Number 4
H. H. Hummel, Kalimullah, and P. Pizzica
Nuclear Science and Engineering
Volume 59 / Number 4 / April 1976 / Pages 440-441
Format:electronic copy (download)
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.
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