The Spent Fuel Pool Analysis of Chinshan Nuclear Power Plant by Using TRACE/FRAPCON-3.4

Abstract

After Fukushima nuclear power plant (NPP) event, INER (Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.) performed the safety analysis of the failure of spent fuel pool cooling for Chinshan NPP by TRACE. In this study, by using the above TRACE results, we focused on the application of FRAPCON-3.4 in the spent fuel pool safety analysis of Chinshan NPP. FRAPCON-3.4 can calculate the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. There are two steps considered in this study. The first step is the verification of the FRAPCON-3.4 by using IFA-431 experimental data. The next step is the fuel analysis of Chinshan NPP spent fuel pool by using FRAPCON-3.4 and the TRACE results.