A TRAC-PF1/MOD1 analysis of the Ginna tube-rupture event on January 25, 1982

Technical Report · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:6120384

Lime, J F; Jenks, R P

The R.E. Ginna steam-generator tube-rupture (SGTR) event on January 25, 1982, was simulated using the Transient Reactor Analysis Code TRAC-PF1/MOD1, version 12.3. A complete TRAC model of the Ginna plant was developed, and the SGTR event was calculated to 5000 s. The overall plant behavior was simulated, with excellent to reasonable agreement obtained between calculated results and measured data. A primary objective of calculating and matching the actual reactor trip time was achieved. The analysis demonstrates that TRAC can accurately simulate full-scale plant SGTR transients.

• Research Organization: Los Alamos National Lab., NM (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Accident Analysis
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6120384
• Report Number(s): NUREG/CR-4988; LA-11094; ON: DE88001664
• Country of Publication: United States
• Language: English

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