RELAP/MOD1. 5 analysis of steam line break transients for a 3-loop and a 4-loop Westinghouse nuclear steam supply system

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6278867

Peeler, G B; McDonald, T A; Kennedy, M F

RELAP/MOD1.5 (Cycle 31 and 34) calculations were made to assess the assumptions used by Westinghouse (W) to analyze mainsteam line break transients. Models of a W 3-loop and 4-loop nuclear steam supply system were used. Sensitivity studies were performed to determine the effect of the availability of offsite power, break size and initial core power. Comparison with W results indicated that if the assumptions used by W are replicated within the RELAP5 framework, then the W methodology for prediction of the Nuclear Steam Supply System (NSSS) response is conservative for steam line break transients.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6278867
• Report Number(s): CONF-841115-4; ON: DE85000578
• Resource Relation: Conference: International conference on power plant simulation, Mexico City, Mexico, 19 Nov 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

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