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SPERT-II benchmarks of a dynamic model for the Advanced Neutron Source reactor

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3 Author(s)
M. Ibn-Khayat ; Tennessee Univ., Knoxville, TN, USA ; J. March-Leuba ; H. L. Dodds

A series of benchmark calculations were performed with a dynamic model of the Advanced Neutron Source reactor against data from the SPERT-II experiments. Satisfactory agreement has been obtained for the SPERT-II long period transients that did not involve localized boiling. The dynamic model represents the reactor core, the vessel, and the primary system as lumped parameter equations. The neutronics module uses the point kinetics approximation and effective reactivity feedbacks computed from one-node representations of the average fuel and coolant channels. Hot-spot fuel temperatures are estimated using the outlet coolant conditions of the hot channel. Single-phase lumped parameter equations are used to model the primary coolant circuits that include piping, heat exchangers, pumps, and a let-down-makeup systems

Published in:

IEEE Transactions on Nuclear Science  (Volume:37 ,  Issue: 3 )