Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant. International Agreement Report

摘要

The first step is the establishment of TRACE (TRAC/RELAP Advanced Computational Engine) models for important components, such as pressurizers, steam generators, the feedwater control system, the steam dump control system, and so on, in Maanshan Nuclear Power Plant (NPP) using SNAP(Symbolic Nuclear Analysis Program)/TRACE. These component models were tested and compared with Maanshan startup test data to verify their accuracy. Key parameters were identified to refine the models further. The next step is the incorporation of the above component models into the Maanshan NPP TRACE model. TRACE transient analyses of scenarios such as load reduction and turbine trip were performed and their results were compared with the corresponding plant data from Maanshan startup tests. The TRACE model of Maanshan NPP is also used to analyze Loss of Flow transient as defined in FSAR Chapter 15 which includes Partial Loss of Flow (PLOF), Complete Loss of Flow-Under Voltage (CLOF-UV), and Complete Loss of Flow-Under Frequency (CLOF-UF). Analysis results indicate that the Maanshan NPP TRACE model predicts not only the behaviors of important plant parameters consistent with the plant data, but also their associated numerical values with respectable accuracy.