中法核工程与技术学院核声论坛（总第240期）

讲座摘要：

The models to evaluate the performance and fission product release behavior of TRISO-coated fuel particles for High-Temperature Gas-Cooled Reactors (HTGRs) under both normal operation and accident conditionsare introduced. Thedeveloping and validating process of computer codes, notably the German model FRESCO, to predict fuel failure and the transport of fission products like iodine and noble gasesare detailed discussed. Aninternational benchmark studies coordinated by the IAEA, where the models are compared against experimental data from irradiation tests and heating experiments to verify their accuracywill also be present. Additionally,the specific fuel failure mechanisms, such as the corrosion of the silicon carbide layer by fission products like palladium, and the release of fission products during core heatup accidents, which is critical for reactor safety analysiswill also be introduced.

主讲人简介：

Karl Verfondernearned a Bachelor's degree in Physics from Bonn Universityin 1978; he obtained a Ph.D. in Physics from RWTH Aachenin 1983. From 1983 to 1992, he worked at the Jülich Research Center in Germany, focusing on the development and optimization of models for evaluating fuel behavior and fission product behavior in high-temperature gas-cooled reactors. From 1992 to 2004, he was involved in hydrogen energy utilization safety research at the Jülich Research Center. Since 2004, he has resumed research on high-temperature gas-cooled reactor fuel and fission product behavior, as well as new energy sources such as hydrogen, primarily within EU and other international collaborative frameworks. Dr. Verfondern is the developer of the TRISO fuel failure probability analysis program PANAMA andone of the principal contributors to the Fission Product Release and Transport Code FRESCO.