SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4

Technical Report · Thu Jun 01 04:00:00 EDT 1995

DOI:https://doi.org/10.2172/100327· OSTI ID:100327

Hagrman, D T ^[1]; Allison, C M; Berna, G A ^[2]

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1. ed.
2. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); and others

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, the core, fission products released during a severe accident transient 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. 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 IV, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. formulation of the materials properties are generally semi-empirical 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.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 100327
• Report Number(s): NUREG/CR--6150-Vol.4; EGG--2720-Vol.4; ON: TI95015168
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CORIUM
DATA
DATA BASE MANAGEMENT
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LOSS OF FLOW
MECHANICAL PROPERTIES
OUTAGES
PHYSICAL PROPERTIES
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTOR SAFETY
S CODES
SCRAM
TRANSIENTS