Overview of TRAC-PD2 assessment calculations

Technical Report · Fri Nov 01 04:00:00 EST 1985

DOI:https://doi.org/10.2172/6475367· OSTI ID:6475367

Waterman, M E

A summary of Transient Reactor Analysis Code Version PD2 (TRAC-PD2) calculations performed at the Idaho National Engineering Laboratory (INEL) is presented in this report as part of the US Nuclear Regulatory Commission's (NRCs) overall assessment program of TRAC-PD2. The calculated and measured parameters summarized in this report are break mass flow rate, primary coolant system pressure, reactor core flow rates, and fuel rod cladding temperatures. The data were obtained from seven tests that were performed at two test facilities. The tests were conducted to study the various aspects of cold leg break transients, including the effects of large and small beaks, and core reflood phenomena. User experience gained from the various calculations is also summarized. 42 figs., 10 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6475367
• Report Number(s): NUREG/CR-4195; EGG-2380; ON: TI86003980
• Country of Publication: United States
• Language: English

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