Modeling of the behavior under fuel dispersed irradiation of U-Mo with aluminum matrix from the thermal point of view and its interrelationship with the interdiffusion phase fuel / matrix
- 1. Comision Nacional de Energia Atomica, Buenos Aires (Argentina)
- 2. Argonne National Laboratory, Argonne, IL (United States)
Description
Results from postirradiation examinations of U-Mo / Al dispersion fuels plates denotes a strong interrelation and feedback between the fuel-matrix interaction and the fuel temperature, bringing undesired consequences on the total swelling and behavior under irradiation. The present work approaches this problem, modeling the profile of temperatures moment by moment to be able to evaluate the increase of this interaction. The Fast Dart program is used, optimized version of program Dart, developed by Dr. J. Rest in collaboration with Dr. H. Taboada. A subroutine of thermal calculation was implemented in this code, which allowed to calculate the evolution of the interaction between the fuel and the matrix. The results of simulations are compared with the results of postirradiation examinations realized by the Reduced Enrichment for Research and Test Reactors International Program. In particular, a good adjustment in the calculation of the depth of interdiffusion U-Mo/Al is observed, demonstrating a right estimation of the profile of temperatures on the fuel plate. It is considered necessary the inclusion of a model that describes the phases that form in the zone of interaction, denoting its thermal dependency and effects due to the radiation damage. (author)
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Additional details
Additional titles
- Original title (Spanish)
- Modelado del comportamiento bajo irradiación del combustible disperso de U-Mo con matriz de aluminio desde el punto de vista térmico y su interrelación con la fase de interdifusión combustible / matriz
Publishing Information
- Publisher
- AATN
- Imprint Place
- Buenos Aires (Argentina)
- Imprint Pagination
- 10 p.
- Report number
- INIS-AR-C--1686
Conference
- Title
- 36. Annual meeting of the Argentine Association of Nuclear Technology: Nuclear energy in the present world
- Original Conference Title
- AATN 2009: 36. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN): La energia nuclear en el mundo actual
- Acronym
- AATN 2009
- Dates
- 16-20 Nov 2009
- Place
- Buenos Aires (Argentina)
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 44104798
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; COMPUTER CALCULATIONS; F CODES; FOURIER HEAT EQUATION; FUEL PLATES; MOLYBDENUM; POST-IRRADIATION EXAMINATION; SPENT FUELS; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY; URANIUM; URANIUM ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDES; ALLOYS; COMPUTER CODES; DIFFERENTIAL EQUATIONS; ELEMENTS; ENERGY SOURCES; EQUATIONS; FUEL ELEMENTS; FUELS; MATERIALS; METALS; NUCLEAR FUELS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR MATERIALS; REFRACTORY METALS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS
Optional Information
- Notes
- 22 refs., 3 figs., 1 tab.