Accidend Analysis in Multi-Loop PWR Nuclear Power Plants

Abstract

The objective of this work is to develope a digital Simulator of a complete Pressurized Water Reactor Nuclear Power Plant (PWRNPP) capable of simulating accidents in which vapor may be generated in the reactor core and transported along the primary loop. Extensive heat transfer correlations, two-phase friction multiplier, and thermodynamic properties covering a wide range of pressure and temperature are included. The reactor coolant pump behaviour in the presence of two phase flow is simulated via empirical curves available from post-TMI publications.