In order to ensure the safety of fuel rods in nuclear reactor, it is necessary to consider the condition of the power ramp during reactor operation, which may cause breakage risk of fuel rod at the time of pellet-cladding interaction (PCI) appearing. To analyze this phenomenon and reduce the risk, a performance analysis model for fuel rod is developed to carry out the steady state and transient simulation using commercial software COSMOL. The full model has three main computational models, which are heat transfer model, mechanical model and internal pressure model. The calculation results show that the stress and strain of NHR200-II fuel rods has enough margins during the power ramp process, which indicates that the risks of fuel rod damage are very low.
- Nuclear Engineering Division
Analysis on Pellet-Cladding Interaction of Fuel Rod During Power Ramp of NHR200-II
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Kang, T, Li, S, Wang, D, Jiang, Y, & Li, W. "Analysis on Pellet-Cladding Interaction of Fuel Rod During Power Ramp of NHR200-II." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. London, England. July 22–26, 2018. V003T02A029. ASME. https://doi.org/10.1115/ICONE26-81596
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