Status of the TRAC-BWR program

Technical Report · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6376645

Weaver, III, W L; Rouhani, S Z

The Transient Reactor Analysis Code for Boiling Water Reactors (TRAC-BWR) is being developed at the Idaho National Engineering Laboratory for the Division of Accident Evaluation, Office of Nuclear Regulatory Research of the United States Nuclear Regulatory Commission (USNRC). The objective of developing these codes is to provide the USNRC and the public with a best estimate 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 during transients from other reactor types. This paper focuses on the work performed during the last year and discusses the latest released version of the code, TRAC-BD1/MOD1, which was released in April 1984, and TRAC-BF1, the code version currently under development.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6376645
• Report Number(s): EGG-M-19584; CONF-8410142-49; ON: TI85003423
• Country of Publication: United States
• Language: English

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