LBLOCA analysis in a Westinghouse PWR 4-loop design using TRACE

Abstract EN

This study documents the analysis of a postulated Large Break Loss-of-Coolant Accident (LBLOCA) in a Westinghouse 4-Loop PWR design analyzed using the best-estimate code TRACE (TRAC/RELAP Advanced Computational Engine).

SNAP (Symbolic Nuclear Analysis Program) was used to facilitate system modeling work.

The obtained results show sufficient margins to the 10 CFR 50.46 limits, which indicates that the maximum peak cladding temperature is well below 2,200°F (1,477.59 K), the maximum local oxidation is well below 17% of the initial cladding thickness, and the overall hydrogen generation is well below 1%.

A coolable core geometry is maintained, and long term cooling of the core is assured