In this study, we analyze and compare the temperature profiles, and temperature gradient profiles of UN, U3Si2 and U3O8 aluminum (Al) dispersed nuclear fuels to propose safer nuclear fuels with enhanced thermal conductivity. To calculate the electronic and lattice thermal conductivities, we use EPW, BoltzTrap and ShengBTE codes implemented with Quantum Espresso. Maxwell-Eucken approximation is used to get the effective thermal conductivity of the considered dispersed fuels. The temperature and temperature gradients are calculated by solving the steady state heat conduction equation for a cylindrical fuel rod. Results show that these fuels have reduced the centerline temperature which will prevent fuel melting, as well it will reduce the thermal stress which leads to cracking the pellet.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5781-6
PROCEEDINGS PAPER
Composite Versus Dispersed Accident Tolerant Nuclear Fuels
Jayangani Ranasinghe,
Jayangani Ranasinghe
University of Saskatchewan, Saskatoon, SK, Canada
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Barbara Szpunar,
Barbara Szpunar
University of Saskatchewan, Saskatoon, SK, Canada
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Ericmoore Jossou,
Ericmoore Jossou
University of Saskatchewan, Saskatoon, SK, Canada
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Linu Malakkal,
Linu Malakkal
University of Saskatchewan, Saskatoon, SK, Canada
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Jerzy A. Szpunar
Jerzy A. Szpunar
University of Saskatchewan, Saskatoon, SK, Canada
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Jayangani Ranasinghe
University of Saskatchewan, Saskatoon, SK, Canada
Barbara Szpunar
University of Saskatchewan, Saskatoon, SK, Canada
Ericmoore Jossou
University of Saskatchewan, Saskatoon, SK, Canada
Linu Malakkal
University of Saskatchewan, Saskatoon, SK, Canada
Jerzy A. Szpunar
University of Saskatchewan, Saskatoon, SK, Canada
Paper No:
ICONE25-67478, V003T02A056; 5 pages
Published Online:
October 17, 2017
Citation
Ranasinghe, J, Szpunar, B, Jossou, E, Malakkal, L, & Szpunar, JA. "Composite Versus Dispersed Accident Tolerant Nuclear Fuels." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application. Shanghai, China. July 2–6, 2017. V003T02A056. ASME. https://doi.org/10.1115/ICONE25-67478
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