Published 1986 | Version v1
Book

A small break loss-of-coolant accident simulation with MC-PWR

  • 1. S. Levy Inc., 3425 S. Bascom Avenue, Campbell, CA 95008

Description

MC-PWR is a microcomputer model for dynamic analysis of pressurized water reactor (PWR) plants. The model simulates all major components of the nuclear steam supply system of the plants with U-tube steam generators, and almost all control systems in the primary and secondary sides of the system. The plant model is based on first-principle formulations using mass, energy and momentum conservation equations for thermal-hydraulics, and point-kinetic formulation for reactor neutronics. Its operation was limited to single-phase flow conditions in the primary side. Currently is is being enhanced to simulate both single-phase liquid and two-phase flow conditions in the primary side to allow simulation of transients such as small break loss-of-coolant accident. In the secondary side the model still assumes subcooled conditions for the feedwater flow, and saturated steam conditions in the steam line. Drift-flux formulations are used to calculate vapor fractions in the different two-phase flow regions in both primary and secondary sides

Additional details

Publishing Information

Publisher
University of Tennessee.
Imprint Place
Knoxville, TN (USA)
Imprint Title
Proceedings of power plant dynamics, control and testing symposium
Journal Page Range
p. 33.01-33.03.

Conference

Title
6. power plant dynamics, control and testing symposium.
Dates
14-16 Apr 1986.
Place
Knoxville, TN (USA).