1995•Unpublished venueOpen access
RELAP5/MOD3 code manual: Code structure, system models, and solution methods. Volume 1
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology, Nuclear Regulatory Commission, Washington, DC (United States), Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
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Abstract
The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and 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 simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. RELAP5/MOD3 code documentation is divided into seven volumes: Volume I provides modeling theory and associated numerical schemes.