Desarrollo y aplicación de herramientas de valoración de riesgos tecnológicos en centrales nucleares españolas a partir de la técnica de análisis probabilista de seguridad
- Autores: Pedro Díaz Bayona
- Directores de la Tesis: Alfredo de Blas del Hoyo (dir. tes.), Javier Dies Llovera (dir. tes.)
- Lectura: En la Universitat Politècnica de Catalunya (UPC) ( España ) en 2018
- Idioma: español
- Tribunal Calificador de la Tesis: Guillem Cortes Rossell (presid.), José Cesar Queral Salazar (secret.), Miguel Angel Jiménez García (voc.)
- Programa de doctorado: Programa de Doctorado en Ingeniería Nuclear y de las Radiaciones Ionizantes por la Universidad Politécnica de Catalunya
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- Resumen
The PhD thesis Desarrollo y aplicación de herramientas de valoración de riesgos tecnológicos en centrales nucleares españolas a partir de la técnica de Análisis Probabilista de Seguridad” results from the research projects carried out between the Nuclear Engineering Research group, which belongs to UPC’s Divisió d’Enginyeria Nuclear, and one of the operator companies of Spanish nuclear power plants during the period of 2013-2017. Both the Secretaria de Recerca i Universitats of the Generalitat de Catalunya and the Ministerio de Econom ía, Industria y Competitividad of the Spanish government are also participants because they have awarded grants for the development of the projects herein presented. The main objective of this PhD thesis is to delve into the field of the risk-informed applications used in nuclear power plants, putting forward, developing, and testing new tools that allow a more detailed awareness and evaluation of nuclear power plants risks so that nuclear power plants can be operation and maintenance safely. For that purpose, the first part of this thesis presents the state of the art of risk-informed applications and their role in the frame of nuclear safety. The second part of the thesis presents the development and results analysis of a pilot probabilistic safety assessment for an independent spent fuel storage installation, which is devoted to store nuclear spent fuel. This assessment, which is pioneer in the Spanish nuclear industry, analyzes the installation’s response to abnormal events, and allows to quantify the risk related to the occurrence of an undesired consequence in this installation. Moreover, this part of the thesis presents a novel contribution to the field of human reliability analysis as applied to probabilistic safety assessment in the form of the development of a human reliability analysis methodology applicable to the storage installation handling operations. It is concluded that the contribution of the storage installation to the risk of radionuclide emission of the whole plant is virtually nonexistent. The third part of the thesis presents the development and application of methodologies and tools derived from fire probabilistic safety assessments whose purpose is to introduce the evaluation of the fire induced risk in the decision-making processes devoted to the configuration of systems, structures, and components in nuclear power plants. Historically, the assessment of the fire induced risk had been either carried out qualitatively or belittled mainly because of the late evolution of the fire induced risk quantitative assessment techniques. In consequence, the tools presented in this thesis are a novel contribution to the field of risk-informed decision making since they provide a quantitative evaluation of the fire induced risk by means of a fire probabilistic safety assessment. Two matrix-shaped novel tools are described and applied to the real case of a Spanish nuclear power plant. The use of these tools demonstrates that number of elements who are significant to the fire induced risk of the plant is small. The projects presented in this PhD thesis as well as others developed through the period 2013-2017 have presented in national and international conferences and have been published in international indexed journals.
