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RELAP5/MOD3 code manual: User`s guide and input requirements. Volume 2
Author(s) -
Washington
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/100207
Subject(s) - volume (thermodynamics) , code (set theory) , boiler feedwater , documentation , computer science , source code , nuclear engineering , programming language , engineering , mechanical engineering , thermodynamics , physics , turbine , set (abstract data type)
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. Volume II contains detailed instructions for code application and input data preparation

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