Potential Use of High Thermal-Conductivity Fuels in Advanced Heavy-Water Moderated Reactors
International Conference on the Future of Heavy Water Reactors - 2011 October 02-05

Presented at:
International Conference on the Future of Heavy Water Reactors
2011 October 02-05
Ottawa, Canada
Session Title:
Fuel and Fuel Safety

W. Peiman (University of Ontario Institute of Technology)
Igor Pioro (University of Ontario Institute of Technology)
K. Gabriel (University of Ontario Institute of Technology)


This paper focuses on the investigation of the potential use of  high thermal-conductivity fuels such as uranium dioxide plus silicon carbide (UO2-SiC), uranium dioxide plus beryllium oxide (UO2-BeO), and uranium dioxide composed of graphite fibers (UO2-C) in SuperCritical Water-cooled Reactors (SCWRs), which are considered as advanced heavy-water moderated reactors.  The objective of this paper is to evaluate several high thermal-conductivity fuels, namely, UO2-SiC, UO2-BeO, and UO2-C.  In order to fulfill the objective of this paper, the fuel centerline temperature and sheath temperature profiles of these fuels have been calculated and compared against the industry accepted limit and the design limit of 1850°C and 850°C for the fuel and the sheath, respectively.  The result showed that the fuel centerline temperatures of the examined high thermal conductivity fuels are below the temperature limit of 1850°C under the operating conditions of the SCWR fuel channels with the maximum thermal power when 43-element fuel bundles, which have 42 fuel elements with an outer diameter of 11.5 mm, are used.

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