Steam generator tube rupture study

Abstract

This report describes our investigation of steam generator behavior during a postulated tube rupture accident. Our study was performed using the steam generator, thermal-hydraulic analysis code THERMIT-UTSG. The purpose of our work was to provide an independent assessment of the Los Alamos National Laboratory system code TRAC-PF1 with respect to steam generator tube rupture analysis. Results of our work are presented and compared with previous TRAC-PF1 results. There are substantial differences in the results of the two codes. These discrepancies are discussed and deficiencies in both codes are noted. Our results lead us to believe that further investigation and code development are necessary to gain more than a basic understanding of steam generator behavior during such accidents and to provide a simulation capability that is acceptable.