Results 141 to 150 of about 248 (163)
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Journal of Nuclear Materials, 2017
Abstract Silicon carbide-silicon carbide (SiC/SiC) composites are considered to replace the current zirconium-based cladding materials thanks to their good behavior under irradiation and their resistance under oxidative environments at high temperature. In the present work, a thermodynamic analysis of the UO 2±x /SiC system is performed.
James Braun +7 more
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Abstract Silicon carbide-silicon carbide (SiC/SiC) composites are considered to replace the current zirconium-based cladding materials thanks to their good behavior under irradiation and their resistance under oxidative environments at high temperature. In the present work, a thermodynamic analysis of the UO 2±x /SiC system is performed.
James Braun +7 more
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Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, 2017
In this study, based on the code FROBA (Fuel ROd Behavior Analysis), a thermal-mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version named FROBA-ATF was developed to perform the fuel performance simulation of ATFs with different claddings, including Zr-4, SiC and Zr-4 coated with SiC.
Yangbin Deng +6 more
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In this study, based on the code FROBA (Fuel ROd Behavior Analysis), a thermal-mechanical analysis code initially developed for traditional UO2-Zr fuel elements by our research group, a modified version named FROBA-ATF was developed to perform the fuel performance simulation of ATFs with different claddings, including Zr-4, SiC and Zr-4 coated with SiC.
Yangbin Deng +6 more
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Nuclear Engineering and Design, 2016
Abstract Since the events at the Fukushima-Daiichi nuclear power plant, there has been increased interest in developing fuels to better withstand accidents for current light water reactors. Four accident tolerant fuel candidates are uranium oxide with beryllium oxide additives, uranium oxide with silicon carbide matrix additives, uranium nitride, and
Kristina Yancey Spencer +8 more
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Abstract Since the events at the Fukushima-Daiichi nuclear power plant, there has been increased interest in developing fuels to better withstand accidents for current light water reactors. Four accident tolerant fuel candidates are uranium oxide with beryllium oxide additives, uranium oxide with silicon carbide matrix additives, uranium nitride, and
Kristina Yancey Spencer +8 more
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The Accident Tolerant Fuels Neutronics Scoping Study (ATF-2Pert)
Transactions of the American Nuclear Society, 2023Tristen Rogers +3 more
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Legierungen auf Zirkoniumbasis werden seit langem in großem Umfang als Hüllrohrrohrmaterialien in Kernkraftwerken eingesetzt. Es werden jedoch noch weitere Verbesserungen bei Hüllrohren auf Zr-Basis erwartet, insbesondere hinsichtlich der Verbesserung ihrer Unfalltoleranz.
Pan, Boyu, Janani Ramesh, Devi
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Pan, Boyu, Janani Ramesh, Devi
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Searching for the Optimum Accident Tolerant Fuel (Atf) for the Nuclear Power Plant Vver-1200
SSRN Electronic Journal, 2022ahmed abdelghafar galahom +3 more
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Accident Tolerant Fuel Test (ATF-2c) Irradiation Test Report
2023David Kamerman +3 more
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ACCIDENT TOLERANT FUEL TEST 2B (ATF-2B) IRRADIATION TEST REPORT
2021David Kamerman +5 more
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Accident-Tolerant Fuels (ATFs) represent a significant advancement in enhancing reactor safety, with dual-cooled designs offering improved thermal–hydraulic performance. The placement of burnable absorber (BA) rods within such assemblies critically influences neutronic behavior, including reactivity control and power distribution.
GholamReza Ansarifar +1 more
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GholamReza Ansarifar +1 more
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