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RELAP/MOD3 code manual: User`s guidelines. Volume 5, Revision 1
Author(s) -
C.D. Fletcher,
Richard R. Schultz
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 - 10.2172/100083
Subject(s) - scram , boiler feedwater , coolant , nuclear engineering , transient (computer programming) , thermal hydraulics , code (set theory) , environmental science , computer science , feedwater heater , pressurized water reactor , engineering , mechanical engineering , turbine , heat transfer , mechanics , operating system , physics , set (abstract data type) , programming language , combined cycle , steam electric power station
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 V contains guidelines that have solved over the past several years through the use of the RELAP5 code

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