Selva García, Anahí D. (2022) Estudio de integridad estructural de boquillas con defectos tipo fisuras en el reactor CAREM-25 / Structural integrity assessment of crack-like defects on the CAREM-25 reactors nozzles. Maestría en Ingeniería, Universidad Nacional de Cuyo, Instituto Balseiro.
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Resumen en español
En la industria nuclear es de gran importancia la evaluación de defectos que puedan estar presente en las distintas soldaduras que se efectúan en los componentes sometidos a presión interna. Esta evaluación se realiza mediante técnicas de ensayos no destructivos con la finalidad de determinar la integridad estructural empleando distintos criterios de aceptación de defectos. En el caso del reactor CAREM-25, las diferencias existentes en los materiales y estados de carga frente a los casos considerados en los reactores tradicionales, hacen que los criterios desarrollados no puedan ser aplicados de forma directa. El objetivo de este trabajo es efectuar el análisis de geometrías aceptables de defectos tipo fisura circunferenciales en la soldadura del plenum del reactor CAREM-25. Para llevar el mismo a cabo, se utiliza la metodología FAD (Diagrama de Evaluación de Fallas), que se vale de parámetros empleados en análisis de fractura lineal elástica para considerar tanto este caso de falla como colapso plástico y fractura elastoplástica. Se calculan los parámetros utilizados en el diagrama a partir de las soluciones provistas por la practica recomendada API-579/ASME-FFS-1 para un cilindro infinito, considerando las tensiones generadas durante los distintos estados de carga planteados a lo largo de la vida del reactor. Estos valores son extraídos a partir de las simulaciones por elementos finitos provistas por el departamento de Mecánica del CAREM que se encuentran disponibles. Tras la identificación del estado de carga y las geometrías fisuras mas severas, se procede a realizar la simulación por elementos finitos de distintas fisuras para validar los resultados analíticos obtenidos y la aplicabilidad de las distintas hipótesis efectuadas durante el análisis por API-579/ASME-FFS-1. Finalmente, se realiza un estudio de propagación por fatiga de distintas fisuras se- mielíticas con geometrías iniciales definidas. Se analizan las dimensiones finales y la evolución del factor de forma. Debido a la naturaleza aleatoria de los eventos postulados, se emplea el método de Monte Carlo para generar resultados relevantes a nivel estadístico.
Resumen en inglés
Evaluation of the defects that could be present on welded seams of pressurized components is of great importance in the nuclear industry. Non destructive tests are used for this, and structural integrity is determined according with different defect tolerance criteria. In this sense, the more usually applied criteria can not be used directly for the CAREM-25 reactor, given the significant differences concerning the materials and the load states between this reactor and the more traditional ones. In this master thesis, acceptability of circumferential crack-like defects in the CAREM- 25 reactor’s plenum is analysed. In order to carry out this task, the FAD (Failure As- sessment Diagram) approach is used. This methodology applies linear elastic fracture mechanic parameters and incorporates adequate correction factors in order to consider this cause of failure, alongside elastoplastic fracture and plastic collapse. The param- eters are calculated according to API-579/ASME-FFS-1 recommended practices, by applying an infinite cylinder simplifying hypothesis. A set of loading cases expected to happen during the reactor’s life cycle is considered. Currently available finite element method simulations provided by the CAREM Mechanics Department are used as an input for relevant stress values. After identifying the load cases and the geometries of the more severe cracks, finite element method simulations are carried out with different crack shapes in order to validate the analytical results and the used hypotheses. Finally, a fatigue crack growth study is performed, in which different semielliptical cracks with predefined initial geometries are used. Both the final geometries and the evolution of the crack’s shape factor are studied. Due to the random nature of the postulated load cases, the Monte Carlo method is applied in order to generate statistically relevant results.
| Tipo de objeto: | Tesis (Maestría en Ingeniería) |
|---|---|
| Palabras Clave: | CAREM-25 reactor; Reactor CAREM-25; Fractures; Fracturas; Finite element method; Métodos de elementos finitos; [ASME; Fitness for service; Aptitud de servicio] |
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| Materias: | Ingeniería mecánica > CAREM-25 |
| Divisiones: | Gcia. de área de Investigación y aplicaciones no nucleares > Gcia. de Física > Ciencias de materiales > Física de metales |
| Código ID: | 1132 |
| Depositado Por: | Tamara Cárcamo |
| Depositado En: | 07 Mar 2023 12:34 |
| Última Modificación: | 07 Mar 2023 12:34 |
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