An Assessment of Pressure Tube Rupture Event in The Refurbished Wolsong-1 Nuclear Power Plant

Abstract

A postulated pressure tube rupture (PTR) event, which is one of the in-core loss-of-coolant accidents (LOCA), has been analysed and evaluated for the refurbished Wolsong-1 Nuclear Power Plant (NPP). This plant is planned to undergo a long period of maintenance shutdown, beginning from the late 2009. The major activities would be the replacement of all 380 fuel channels, calandria tube assemblies and the connecting feeder pipes. As a part of its refurbishment project, a full scope of safety analyses is being jointly performed by Korean engineering companies. The industry standard toolset (IST) codes developed by CANDU Owners Group and updated models including ageing parameters are applied to the event analysis. The developed methodology and the results of pressure tube rupture event assessment are presented herein. The analysis results show that the implementation of the developed ageing model with the newly introduced computer codes is proved to be successful in the Refurbished Wolsong-1 NPP.