An enhanced thermal conductivity UO2-BeO composite nuclear fuel was studied. A methodology to generate ANSYS (an engineering simulation software) FEM (Finite Element Method) thermal models of enhanced thermal conductivity oxide nuclear fuels was developed. Two fabrication methods to produce high thermal conductivity UO2-BeO oxide nuclear fuels were summarized. These two processing routes generated pellets with two different microstructures. The characteristics and microstructures of the fuel are determined for use in FEM thermal models, and the relevant thermal properties for UO2-BeO fuels by two different fabrication methods were determined. The results showed significant increase in the fuel thermal conductivities. The reactor performance analysis showed that the decrease in centerline temperature was 250–350K for the UO2-BeO composite fuel, and thus we can improve nuclear reactors’ performance and safety, and high-level radioactive waste generation.
- Nuclear Engineering Division
Enhanced Thermal Conductivity UO2-BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors
- Views Icon Views
- Share Icon Share
- Search Site
Zhou, W, & Liu, R. "Enhanced Thermal Conductivity UO2-BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T02A013. ASME. https://doi.org/10.1115/ICONE22-30647
Download citation file: