SCDAP/RELAP5/MOD 3.3 Code Manual:MATPRO - A Library of Materials Properties for Light-Water-Reactor Accident Analysis (NUREG/CR-6150, Volume 4, Revision 2)

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• Publication Information
• Abstract

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• NUREG/CR-6150, Volume 4, Revision 2
  • Cover – Section 3 (PDF - 10.69 MB)
  • Section 4 (PDF - 11.33 MB)
  • Section 5 – End (PDF - 9.82 MB)

Publication Information

Manuscript Completed: August 2000
Date Published: January 2001

Prepared by:
L. J. Siefken, E. W. Coryell, E. A. Harvego,
J. K. Hohorst

Idaho National Engineering and Environmental Laboratory
P.O. Box 1625
Idaho Falls, ID 83415-3129

S. A. Arndt, NRC Project Manager

Prepared for:
Division of Systems Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC Job Code W6095

Availability Notice

Abstract

The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system and reactor core during severe accidents as well as large and small break loss-of-coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. The coolant system behavior is calculated using a two-phase model allowing for unequal temperatures and velocities of the two phases of the fluid, and the flow of fluid through porous debris and around bockages caused by reactor core damage. The reactor core behavior is calculated using models for the ballooning and oxidation of fuel rods, the meltdown of fuel rods and control rods, fission product release, and debris formation. The code also calculates the heatup and structural damage of the lower head of the reactor vessel resulting from the slumping of reactor core material. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems.

This volume, Volume 4, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. Formulation of the materials properties are generally semiempirical in nature. The materials property subroutines contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium, dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium alloy, cadmium, boron carbide, Inconel 718, zirconium-uranium-oxygen melts, fill gas mixtures, carbon steel, and tungsten. This document also contains descriptions of the reaction and solution rate models needed to analyze a reactor accident. Revision 2 includes changes incorporated since the manuals were released in July 1998.