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RELAP5 Thermal-Hydraulic Analysis of the SNUPPS Pressurized Water Reactor.

NUREGCR5557

Publication Date	1990
Personal Author	Kullberg, C. M.
Page Count	96
Abstract	Thermal-hydraulic analyses of five hypothetical accident scenarios were performed with the RELAP5 computer code for the Westinghouse Standardized Nuclear Power Plant System pressurized water reactor. The work was sponsored by the U.S. Nuclear Regulatory Commission and is being done in conjunction with future analysis work at the U.S. Nuclear Regulatory Commission Technical Training Center in Chattanooga, TN. These accident scenarios were chosen to assess and benchmark the thermal hydraulic capabilities of the Technical Training Center Standardized Nuclear Unit Power Plant System simulator to model abnormal transient conditions.
Keywords	Westinghouse standard reactor Loss of coolant Accident analysis Thermal analysis Hydraulics PWR type reactors RELAP5 computer program
Source Agency	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. Div. of Systems Research.
Supplemental Notes	Also available from Supt. of Docs. See also DE85-003425. Sponsored by Nuclear Regulatory Commission, Washington, DC. Div. of Systems Research.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	199016

RELAP5 Thermal-Hydraulic Analysis of the SNUPPS Pressurized Water Reactor.

RELAP5 Thermal-Hydraulic Analysis of the SNUPPS Pressurized Water Reactor.
NUREGCR5557

Publication Date	1990
Personal Author	Kullberg, C. M.
Page Count	96
Abstract	Thermal-hydraulic analyses of five hypothetical accident scenarios were performed with the RELAP5 computer code for the Westinghouse Standardized Nuclear Power Plant System pressurized water reactor. The work was sponsored by the U.S. Nuclear Regulatory Commission and is being done in conjunction with future analysis work at the U.S. Nuclear Regulatory Commission Technical Training Center in Chattanooga, TN. These accident scenarios were chosen to assess and benchmark the thermal hydraulic capabilities of the Technical Training Center Standardized Nuclear Unit Power Plant System simulator to model abnormal transient conditions.
Keywords	Westinghouse standard reactor Loss of coolant Accident analysis Thermal analysis Hydraulics PWR type reactors RELAP5 computer program
Source Agency	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. Div. of Systems Research.
Supplemental Notes	Also available from Supt. of Docs. See also DE85-003425. Sponsored by Nuclear Regulatory Commission, Washington, DC. Div. of Systems Research.
Document Type	Technical Report
Title Note	Technical rept.
NTIS Issue Number	199016