Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

2015 ◽  
Vol 81 ◽  
pp. 240-248 ◽  
Author(s):  
Wenzhong Zhou ◽  
Rong Liu ◽  
Shripad T. Revankar
2020 ◽  
Vol 52 (8) ◽  
pp. 1603-1610 ◽  
Author(s):  
Amir Safavi ◽  
Mohammad Hossein Esteki ◽  
Seyed Mohammad Mirvakili ◽  
Mehdi Khaki Arani

Author(s):  
Wenzhong Zhou ◽  
Rong Liu

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.


2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin

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