부산대학교 도서관

The fuel rod performance has great importance for the safety and economy of an operating reactor. Thefuel rod performance analysis code, which considers the thermal-mechanical response and irradiationeffects of fuel rod, is usually developed in order to predict fuel rod performance accurately. The FRIPAC(Fuel Rod Integral Performance Analysis Code) is such a fuel rod performance analysis code that has beendeveloped recently by China Nuclear Power Technology Research Institute Co. Ltd. The code aims at thecomputational simulation of the Pressurized Water Reactor fuel rod behavior for both steady-state andpower ramp condition. A brief overview of FRIPAC is presented including the computational frameworkand the main behavioral models. Validation of the code is also presented and it focuses on the fuel rodbehavior including fuel center temperature, fission gas release, rod internal pressure/internal void volume,cladding outer diameter and cladding corrosion thickness. The validation is based on experimentaldata from several international projects. The validation results indicate that FRIPAC is an accurate andreliable fuel rod performance analysis code because of the satisfactory comparison results between theexperimental measurements and the code predictions.