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

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–mech...

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Bibliographic Details
Published in:Nuclear science and techniques 2022-05, Vol.33 (5), p.167-177, Article 66
Main Authors: Yang, Guang-Liang, Liao, Hai-Long, Ding, Tao, Chen, Hong-Li
Format: Article
Language:English
Subjects:
Beam Physics
Nuclear Energy
Particle Acceleration and Detection
Particle and Nuclear Physics
Physics
Physics and Astronomy
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Summary: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.
ISSN:1001-8042
2210-3147
DOI:10.1007/s41365-022-01045-7