Development and validation of a new oxide fuel rod performance analysis code for the liquid metal fast reactor  

作　　者：Guang-Liang Yang Hai-Long Liao Tao Ding Hong-Li Chen 

机构地区：[1]School of Nuclear Science and Technology,University of Science and Technology of China,Hefei,230026,China

出　　处：《Nuclear Science and Techniques》2022年第5期167-177,共11页核技术（英文）

摘　　要：The integrity and reliability of fuel rods under both normal and accidental operating conditions are of great importance for nuclear reactors.In this study,considering various irradiation behaviors,a fuel rod performance analysis code,named KMC-Fueltra,was developed to evaluate the thermal–mechanical performance of oxide fuel rods under both normal and transient conditions in the LMFR.The accuracy and reliability of the KMC-Fueltra were validated by analytical solutions,as well as the results obtained from codes and experiments.The results indicated that KMC-Fueltra can predict the performance of oxide fuel rods under both normal and transient conditions in the LMFR.

关 键 词：Fuel rod analysis code Thermal-mechanical performance Irradiation behaviors Pellet-cladding mechanical interaction Liquid metal fast reactor 

分 类 号：TL352[核科学技术—核技术及应用]