Development and validation of a new oxide fuel rod performance analysis code for the liquid metal fast reactor
Nuclear Science and Techniques（2022）
Abstract
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.
MoreTranslated text
Key words
Fuel rod analysis code,Thermal–mechanical performance,Irradiation behaviors,Pellet-cladding mechanical interaction,Liquid metal fast reactor
AI Read Science
Must-Reading Tree
Example
Generate MRT to find the research sequence of this paper
Chat Paper
Summary is being generated by the instructions you defined