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Sweet, R. T.; Eckleberry, T. A.; Maldonado, G. I.; Wirth, B. D., E-mail: rsweet1@vols.utk.edu
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); American Nuclear Society (ANS), La Grange Park, IL (United States). Funding organisation: Sociedad Nuclear Mexicana (Mexico); American Nuclear Society (United States); GE Hitachi (United States); Instituto Nacional de Investigaciones Nucleares (Mexico); TerraPower (United States); Consejo Nacional de Ciencia y Tecnologia (Mexico)2018
Sociedad Nuclear Mexicana (SNM), Ciudad de Mexico (Mexico); American Nuclear Society (ANS), La Grange Park, IL (United States). Funding organisation: Sociedad Nuclear Mexicana (Mexico); American Nuclear Society (United States); GE Hitachi (United States); Instituto Nacional de Investigaciones Nucleares (Mexico); TerraPower (United States); Consejo Nacional de Ciencia y Tecnologia (Mexico)2018
AbstractAbstract
[en] This work examined the impact of substituting FeCrAl cladding on a single PWR fuel rod and a single fuel assembly within a full core environment of standard Zircaloy cladded fuel. The goal was to provide insight on a pin-by-pin level of the power peaking effects caused by heterogeneity in the lattice, as well as to investigate some of the key fuel performance parameters. The neutronic analyses herein reported were performed using CASMO- 4/Simulate-3 models of a representative equilibrium PWR core with standard Westinghouse 17 x 17 assemblies, while the fuel performance analysis was performed using the Bison code with FeCrAl constitutive models currently under development at the University of Tennessee in collaboration with Oak Ridge National Laboratory. (Author)
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Jun 2018; 11 p; Sociedad Nuclear Mexicana; Ciudad de Mexico (Mexico); PHYSOR 2018: reactor physics paving the way towards more efficient systems; Cancun, Q. R. (Mexico); 22-26 Apr 2018; Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mx
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Miscellaneous
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Conference
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ALLOYS, DEPOSITION, DEVELOPED COUNTRIES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUEL ELEMENTS, FUELS, INDUSTRY, MATERIALS, NORTH AMERICA, POWER REACTORS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SURFACE COATING, TENNESSEE, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, URBAN AREAS, USA, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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