Ruiz, Kevin S. (2022) Análisis y modelado de combustibles nucleares avanzados en estacionarios y durante rampas de potencia / Analysis and modelling of advanced nuclear fuels in steady states and during power ramps. Maestría en Ingeniería, Universidad Nacional de Cuyo, Instituto Balseiro.
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Resumen en español
En el presente trabajo se lleva a cabo el estudio, desarrollo, mejora y validación de códigos y modelos de simulación del comportamiento de combustibles nucleares bajo irradiación en estados estacionarios y frente a rampas de potencia de combustibles PHWR, PWR, BWR, VVER, CAREM y diseños avanzados tipo ATF (Accident Tole- rant Fuels). En particular, se estudiaron los códigos FUELROD, BaCo y FRAPCON y para cada uno de ellos se analizaron los aspectos computacionales, se evaluaron las capacidades predictivas bajo distintos estados de carga e historias de potencia y se realizaron tareas de validación y comparación con otros códigos dentro de marcos internacionales de intercomparación y testeo de códigos como los CRP FUMEX I, II, III y ACTOF de IAEA y de análisis de PCI-SCC en rampas de potencias de NEA-OECD. FUELROD es un código simple y de orientación académica que demostró ser muy eficaz para cálculos en estado estacionario y se considera una herramienta notable para análisis paramétrico, diseño conceptual, entrenamiento en el área de diseño de elementos combustibles y para docencia en el curso de elementos combustibles de la carrera de Ingeniería Nuclear. Como parte del trabajo se desarrolló la versión 3.0 del código en la cual se destacan diversas actualizaciones de modelos físicos, mejoras y correcciones en los cálculos y una extensión de la aplicación del código para combustibles ATF. Por otro lado, BaCo y FRAPCON resultan ser herramientas mucho más complejas que permiten un tratamiento detallado de los fenómenos termo-mecánicos involucrados durante la operación de las barras combustibles. Estos últimos dos códigos resultan ideales para realizar cálculos y análisis sumamente precisos. La investigación finaliza con un extenso estudio sobre combustibles tolerantes a accidentes, donde se evalúa su desempeño bajo diversas condiciones de operación, utilizando todas las herramientas computacionales disponibles. A modo de complementar el abanico de herramientas de análisis de ATF, se desarrolló un código termo-mecánico por elementos finitos escrito en lenguaje OCTAVE. Los resultados indican que la línea de combustibles avanzados es prometedora ya que permitiría mejorar el desempeño global de los combustibles nucleares actuales.
Resumen en inglés
This work presents the study, development, improvement and validation of codes and simulation models of the behavior of nuclear fuels under irradiation in steady states and power ramps, including of PHWR, PWR, CAREM fuels and advanced designs such as the ATFs (Accident Tolerant Fuels ). In particular, the FUELROD, BaCo and FRAPCON codes were studied. For each of them, the computational aspects were analyzed and the predictive capacities were evaluated under different load states and power histories. In addition, several validation and comparison tasks were carried out within international frameworks for intercomparison and testing of codes, such as CRP FUMEX I, II, III, ACTOF of IAEA and analysis of PCI-SCC during power ramps of NEA-OECD. FUELROD is a simple and academically oriented code that proved to be very effective for steady-state calculations and is considered as a remarkable tool for parametric analysis, conceptual design, training in the area of fuel rods design, and for teaching in nuclear fuel and materials courses of the Nuclear Engineering career. As part of the research, version 3.0 of the FUELROD code was developed, which presents several updates to physical models, improvements and corrections in the calculations and an extension of the code's application for accident-tolerant fuels with advanced materials. On the other hand, BaCo and FRAPCON turn out to be much more complex tools that allow a detailed treatment of the thermo-mechanical phenomena involved during the operation of the fuel rods. These last two codes are ideal for extremely precise calculations and analysis. The investigation ends with an extensive study on accident-tolerant fuels, where their performance under various operating conditions was evaluated using all available computational tools. To complement the range of ATF analysis tools, a finite element thermo-mechanical code written in OCTAVE language was developed. The results indicate that this new line of advanced fuels is very promising since they would improve the thermo-mechanical performance of current nuclear fuels.
| Tipo de objeto: | Tesis (Maestría en Ingeniería) |
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| Palabras Clave: | Nuclear fuels; Combustibles nucleares; Simulation; Simulación; Modeling; Modelización; Nuclear reactors; Reactores nucleares; [Analysis; Análisis; Designs; Diseño; Advanced materials; Materiales avanzados] |
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Benchmark of fuel performance codes for fecral cladding behavior analysis. págs. 1038-1047. 2020. 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 ; Conference date: 22-09-2019 Through 27-09-2019. |
| Materias: | Química > Materiales Ingeniería nuclear > Combustibles nucleares |
| Divisiones: | Presidencia > Gcia. Ciclo de combustible nuclear > Diseño, simulación y materiales > Laboratorio de simulación de materiales combustibles |
| Código ID: | 1052 |
| Depositado Por: | Tamara Cárcamo |
| Depositado En: | 09 Jun 2022 15:45 |
| Última Modificación: | 09 Jun 2022 15:45 |
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