<p>One of the major degradation mechanisms in a nuclear power plant structural or mechanical component is the neutron embrittlement of the irradiated steel component. High energy neutrons change the microstructure of the steel, so the steel loses its fracture toughness. This neutron embrittlement increases the risk of the brittle fracture. Meanwhile, the reactor pressure vessel support is exposed in low temperature with high neutron irradiation environment which is an unfavorable condition for the fracture failure. In this study, the failure assessment of a reactor pressure vessel support was conducted using the fitness-for-service failure assessment diagram of API 579-1/ASME FFS-1(2016, API) with quantifying the structural margin under the maximum irradiation and extreme load events. </p> <p>Two interrelated studies were conducted. For the first investigation, the current analytical methods were reviewed to estimate the embrittled properties, such as fracture toughness and the yield strength incorporates the low irradiation temperature. The analytical results indicated that the reactor pressure vessel support may experience substantial fracture toughness decrease during the operation near the lower bound of the fracture toughness. A three-dimensional (3D) solid element finite element model was built for the linear stress analysis. Postulated cracks were located in the maximum stress region to compute the stress intensity and the reference stress ratio. Based on the stress result and the estimated physical properties, the structural margin of the reactor pressure vessel support was analyzed in the failure assessment diagram with respect to the types of the cracks, level of the applied load and the level of the neutron influence. </p> <p>The second study explored the structural stress analysis approaches at hot-spot which was found to be key parameter in failure analysis. Depending on the methods to remove the non-linear peak stress and the stress singularities, the accuracy of the failure assessment result varies. As an alternative proposal to evaluate the structural stress in 3D finite element analysis (FEA), the 3D model was divided into two-dimensional (2D) plane models. Five structural stress determination approaches were applied in 2D FEA for a comparison study, the stress linearization, the single point away approach, the stress extrapolation and the stress equilibrium method and the nodal force method. Reconstructing the structural stress in 3D was carried by the 3x3 stress matrix and compared to the 3D FEA results. The difference in 2D FEA structural stress results were eliminated by the constructing the stress in 3D. </p> <p>This study provides the failure assessment analysis of irradiated steel with prediction of the failure modes and safety margin. Through the failure assessment diagram, we could understand the effects of different levels of irradiation and loadings. Also, this study provides an alternative structural stress determination method, dividing the 3D solid element model into two 2D models, using the finite element analysis. </p><br>

En este trabajo se valida la TDC en dos materiales con comportamiento elástico–lineal en estado fisurado: el polímero PMMA y la aleación Al7075-T651. La validación se ha realizado sobre probetas de fractura y se han establecido rangos de validez de la TDC en régimen elástico-lineal. Igualmente, se demuestra la aplicabilidad de la TDC para la evaluación en rotura de componentes con cualquier concentrador de tensiones (entalla en U, entalla en V, taladro circular, etc) y para cargas de distinta naturaleza (tracción vs. Flexión). Además, se plantea y valida un modelo de evaluación de la integridad estructural de componentes con entallas que combina la TDC con los Diagramas de Fallo, extendiendo el rango de aplicación de la TDC a situaciones con comportamiento elastoplástico. Finalmente, el análisis se completa con un detallado estudio mediante microscopía electrónica de barrido de los micromecanismos de fractura de las probetas analizadas. / This study validates the TDC in two materials with linear elastic behavior in cracked conditions: polymer PMMA and alloy AL7075-T651. The validation has been performed on fracture specimens and validity ranges of the TDC in linear elastic regime have been established. Similarly, it is demonstrated the applicability of the TDC for evaluation of components containing any kind of stress riser (e.g., U-notch, V-notch, hole circular, etc.) and subjected to loads of different nature (tensile vs. bending). In addition, a model for the structural integrity assessment of notched components is presented and validated, combining the TDC with Failure Assessment Diagram. This extends the vailidity range of the TDC to situations with elastic-plastic behaviour. Finally, the analysis is completed with a detailed study by scanning electron microscopy of the fracture micromechanisms of the samples being analysed.

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