Dynamic Simulation of a Sodium-Cooled Fast Reactor Power Plant.

摘要

Simulation of the dynamic behavior of the Clinch River Breeder Reactor Plant (CRBRP) is the subject of this dissertation. The range of transients under consideration extends from transients of the type referred to as Anticipated Transient Without Scram (ATWS),to a transient initiated by an unexpected accident followed by reactor scram. This range of transient can be simulated by a digital simulator referred to as the CRBRP ATWS simulator. Two versions of this simulator were prepared;in one,the plant controllers were not included,whereas,in the other,the controllers were incorporated. In addition to the usual assumption of lumped parameters,uniform heat transfer and point kinetics (prompt jump) have been the main approximations in this and other simulators. Two different transport-delay models have also been installed in all simulators. The simulators were constructed using the DARE-P System,developed by the Electrical Engineering Department at The University of Arizona.