Simulation of Thermohydraulic Phenomena in a Pressurized Water Reactor Primary Loop.

摘要

Several fluid flow and heat transfer phenomena were investigated. Scaling and modeling laws for PWRs are reviewed and a new scaling approach focusing on the overall loop behavior is presented. Scaling criteria for one- and two-phase natural circulation are developed. Reactor vessel vent valve effects are included in the analysis. Two new dimensionless numbers, which uniquely describe one-phase flow in natural circulation loops, were deduced and are discussed. A scaled model of the primary loop of a typical Babcock and Wilcox reactor was designed, built, and tested. Experiment measurements included primary side temperatures, hot leg velocities, and other primary and secondary loop performance data. All test data is compared to the theoretically derived performance predictions and scaling laws. The capability of the model to simulate reactor vent valve effects and small break loss of coolant accidents is discussed.