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RELAP5/MOD2 Code Manual. Volume 1: Code Structure, Systems Models, and Solution Methods.

NUREGCR4312

Publication Date	1985
Personal Author	Ransom, V. H.; Wagner, R. J.; Trapp, J. A.; Feinauer, L. R.; Johnsen, G. W.
Page Count	378
Abstract	The principal objective of the RELAP5 project is to provide the United States Nuclear Regulatory Commission (USNRC) with a fast running and user convenient light water reactor system transient analysis code for use in rule making, licensing audit calculations, evaluation of operator guidelines, and as a basis for a nuclear plant analyzer. The RELAP5/MOD2 code has been developed for best estimate transient simulation of pressurized water reactors and associated systems. The code modeling capabilities are simulation of large and small break loss-of-coolant accidents, as well as operational transients such as anticipated transient without SCRAM, loss-of-offsite power, loss of feedwater, and loss of flow. A generic modeling approach utilizes as much of a particular system to be modeled as necessary. RELAP5/MOD2 extends the modeling base and capabilities offered by previous versions of the code. In particular, MOD2 contains two energy equations, reflood heat transfer, a two-step numerics option, a gap conductance model, revised constitutive models, and additional component and control system models.
Keywords	Nuclear power plants Reactor accidents Accident simulation Mathematical models Transients PWR type reactors Loss of coolant ATWS Heat transfer Equations Accident analysis RELAP5/MOD2 computer program
Source Agency	Technical Information Center Oak Ridge Tennessee Nuclear Regulatory Commission
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Nuclear Regulatory Commission, Washington, DC.; Department of Energy, Washington, DC.
Supplemental Notes	Also available from Supt. of Docs. See also NUREG/CR-4312-REV-1. Sponsored by Nuclear Regulatory Commission, Washington, DC., and Department of Energy, Washington, DC.
Document Type	Technical Report
Title Note	Technical rept.,
NTIS Issue Number	198821
Contract Number	DE-AC07-76ID01570

RELAP5/MOD2 Code Manual. Volume 1: Code Structure, Systems Models, and Solution Methods.

RELAP5/MOD2 Code Manual. Volume 1: Code Structure, Systems Models, and Solution Methods.
NUREGCR4312

Publication Date	1985
Personal Author	Ransom, V. H.; Wagner, R. J.; Trapp, J. A.; Feinauer, L. R.; Johnsen, G. W.
Page Count	378
Abstract	The principal objective of the RELAP5 project is to provide the United States Nuclear Regulatory Commission (USNRC) with a fast running and user convenient light water reactor system transient analysis code for use in rule making, licensing audit calculations, evaluation of operator guidelines, and as a basis for a nuclear plant analyzer. The RELAP5/MOD2 code has been developed for best estimate transient simulation of pressurized water reactors and associated systems. The code modeling capabilities are simulation of large and small break loss-of-coolant accidents, as well as operational transients such as anticipated transient without SCRAM, loss-of-offsite power, loss of feedwater, and loss of flow. A generic modeling approach utilizes as much of a particular system to be modeled as necessary. RELAP5/MOD2 extends the modeling base and capabilities offered by previous versions of the code. In particular, MOD2 contains two energy equations, reflood heat transfer, a two-step numerics option, a gap conductance model, revised constitutive models, and additional component and control system models.
Keywords	Nuclear power plants Reactor accidents Accident simulation Mathematical models Transients PWR type reactors Loss of coolant ATWS Heat transfer Equations Accident analysis RELAP5/MOD2 computer program
Source Agency	Technical Information Center Oak Ridge Tennessee Nuclear Regulatory Commission
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Nuclear Regulatory Commission, Washington, DC.; Department of Energy, Washington, DC.
Supplemental Notes	Also available from Supt. of Docs. See also NUREG/CR-4312-REV-1. Sponsored by Nuclear Regulatory Commission, Washington, DC., and Department of Energy, Washington, DC.
Document Type	Technical Report
Title Note	Technical rept.,
NTIS Issue Number	198821
Contract Number	DE-AC07-76ID01570