TRAC-BF1/MOD1 models and correlations

Technical Report · Sat Aug 01 04:00:00 EDT 1992

OSTI ID:7281346

Borkowski, J A; Wade, N L ^[1]; Rouhani, S Z; Shumway, R W; Weaver, W L; Rettig, W H; Kullberg, C L ^[2]

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1. eds.
2. EG and G Idaho, Inc., Idaho Falls, ID (United States)

The TRAC-BWR code development program at the Idaho National Engineering Laboratory has developed versions of the Transient Reactor Analysis Code (TRAC) for the US Nuclear Regulatory Commission and the public. The TRAC-BF1/MOD1 version of the computer code provides a best-estimate analysis capability for analyzing the full range of postulated accidents in boiling water reactor (BWR) systems and related facilities. This version provides a consistent and unified analysis capability for analyzing all areas of a large- or small-break loss-of-coolant accident (LOCA), beginning with the blowdown phase and continuing through heatup, reflood with quenching, and, finally, the refill phase of the accident. Also provided is a basic capability for the analysis of operational transients up to and including anticipated transients without scram (ATWS). The TRAC- BF1/MOD1 version produces results consistent with previous versions. Assessment calculations using the two TRAC-BF1 versions show overall improvements in agreement with data and computation times as compared to earlier versions of the TRAC-BWR series of computer codes.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7281346
• Report Number(s): NUREG/CR-4391; EGG--2680; ON: TI92040315
• Country of Publication: United States
• Language: English

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