SCDAP/RELAP5/MOD 3.1 code manual: User`s guide and input manual. Volume 3

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

DOI:https://doi.org/10.2172/101155· OSTI ID:101155

Coryell, E W; Johnsen, E C ^[1]; Allison, C M ^[2]

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1. eds.
2. 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, core, fission product 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 provides guidelines to code users based upon lessons learned during the developmental assessment process. A description of problem control and the installation process is included. Appendix a contains the description of the input requirements.

• Research Organization: US Nuclear Regulatory Commission (NRC), 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: AC07-94ID13223
• OSTI ID: 101155
• Report Number(s): NUREG/CR-6150-Vol.3; EGG-2720-Vol.3; ON: TI95015066; TRN: 95:020302
• Resource Relation: Other Information: PBD: Jun 1995
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
BWR TYPE REACTORS
REACTOR ACCIDENTS
PWR TYPE REACTORS
COMPUTERIZED SIMULATION
S CODES
R CODES
INSTALLATION
REACTOR COOLING SYSTEMS
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
LOSS OF COOLANT
OUTAGES
LOSS OF FLOW
TRANSIENTS