The GINNA Tube-Rupture Event: A Plant-Transient Benchmark for TRAC

Abstract

The R.E. Ginna steam-generator tube-rupture (SGTR) event on January 25, 1982 was simulated using the Transient Reactor Analysis Code (TRAC), version TRAC-PF1/MOD1. 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 Ginna SGTR event provided a meaningful plant-transient benchmark for reactor-safety thermal-hydraulic computer codes. The analysis presented demonstrates that TRAC can accurately simulate full-scale plant SGTR transients.