The status of the TRAC-BWR (Transient Reactor Analysis Code for Boiling Water Reactors) program

Conference · Wed Dec 31 23:00:00 EST 1986

OSTI ID:5262369

Weaver, III, W L; Johnsen, G W

The Transient Reactor Analysis Code for Boiling Water Reactors (TRAC-BWR) is being developed and maintained at the Idaho National Engineering Laboratory (INEL) for the Division of Accident Evaluation, Office of Nuclear Regulatory Research of the United States Nuclear Regulatory Commission (USNRC). The objective of this development is to provide the USNRC with a detailed, best estimate, efficient computer code for the analysis of postulated accidents and transients in boiling water reactor (BWR) systems. This program is unique among advanced code development projects in that it focuses on the hardware, thermal-hydraulics, and heat transfer phenomena that distinguish BWR systems and their response in transients. In addition to providing a best estimate analysis capability for BWR systems, the code can also be used to address current licensing concerns such as anticipated transients without scram (ATWS) or the small break loss-of-coolant accident (SBLOCA). It also provides analytical support to the USNRC experimental safety programs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5262369
• Report Number(s): EGG-M-26887; CONF-8710111-36; ON: DE88006766
• Country of Publication: United States
• Language: English

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