Optimization of test and maintenance of ageing components consisting of multiple items and addressing effectiveness

[EN] There are many models in the literature that have been proposed in the last decades aimed at assessing the reliability, availability and maintainability (RAM) of safety equipment, many of them with a focus on their use to assess the risk level of a technological system or to search for appropriate design and/or surveillance and maintenance policies in order to assure that an optimum level of RAM of safety systems is kept during all the plant operational life. This paper proposes a new approach for RAM modelling that accounts for equipment ageing and maintenance and testing effectiveness of equipment consisting of multiple items in an integrated manner. This model is then used to perform the simultaneous optimization of testing and maintenance for ageing equipment consisting of multiple items. An example of application is provided, which considers a simplified High Pressure Injection System (HPIS) of a typical Power Water Reactor (PWR). Basically, this system consists of motor driven pumps (MDP) and motor operated valves (MOV), where both types of components consists of two items each. These components present different failure and cause modes and behaviours, and they also undertake complex test and maintenance activities depending on the item involved. The results of the example of application demonstrate that the optimization algorithm provide the best solutions when the optimization problem is formulated and solved considering full flexibility in the implementation of testing and maintenance activities taking part of such an integrated RAM model.Authors are grateful to the Spanish Ministry of Science and Innovation for the financial support of this work (research project ENE2013-45540-R) and the Doctoral fellow (BES-2011-043906 and BES-2014-067602).Martón Lluch, I.; Martorell Aigües, P.; Mullor, R.; Sánchez Galdón, AI.; Martorell Alsina, SS. (2016). Optimization of test and maintenance of ageing components consisting of multiple items and addressing effectiveness. Reliability Engineering and System Safety. 153:151-158. https://doi.org/10.1016/j.ress.2016.04.015S15115815

SPEA2-based safety system multi-objective optimization

Safety systems are designed to prevent the occurrence of certain conditions and their future development into a hazardous situation. The consequence of the failure of a safety system of a potentially hazardous industrial system or process varies from minor inconvenience and cost to personal injury, significant economic loss and death. To minimise the likelihood of a hazardous situation, safety systems must be designed to maximise their availability. Therefore, the purpose of this thesis is to propose an effective safety system design optimization scheme. A multi-objective genetic algorithm has been adopted, where the criteria catered for includes unavailability, cost, spurious trip and maintenance down time. Analyses of individual system designs are carried out using the latest advantages of the fault tree analysis technique and the binary decision diagram approach (BDD). The improved strength Pareto evolutionary approach (SPEA2) is chosen to perform the system optimization resulting in the final design specifications. The practicality of the developed approach is demonstrated initially through application to a High Integrity Protection System (HIPS) and subsequently to test scalability using the more complex Firewater Deluge System (FDS). Computer code has been developed to carry out the analysis. The results for both systems are compared to those using a single objective optimization approach (GASSOP) and exhaustive search. The overall conclusions show a number of benefits of the SPEA2 based technique application to the safety system design optimization. It is common for safety systems to feature dependency relationships between its components. To enable the use of the fault tree analysis technique and the BDD approach for such systems, the Markov method is incorporated into the optimization process. The main types of dependency which can exist between the safety system component failures are identified. The Markov model generation algorithms are suggested for each type of dependency. The modified optimization tool is tested on the HIPS and FDS. Results comparison shows the benefit of using the modified technique for safety system optimization. Finally the effectiveness and application to general safety systems is discussed

Gestión de la operación, vigilancia y mantenimiento de equipos de seguridad de centrales nucleares a corto y largo plazo

[EN] In the last years, several studies have been developed in order to guarantee safety operation of Nuclear Power Plants (NPP), for both, the design plant life and for the Long Term Operation (LTO). In those situations, NPP must face the Periodic Safety Review (PSR). An important part of PRS involves the evaluation of risk impact of Structures, Systems and Components (SSC) ageing and how current asset management programs, e.g. maintenance and testing programs, are successful to achieve the objective of allowing a safe operation. In order to perform this evaluation, it is necessary to extend the current Probabilistic Safety Assessment (PSA) models to take into account, not only equipment ageing, but also maintenance and testing policies. This Ph Dissertation aims to help in NPP safety evaluation in the framework of PSR in both, design life and long-term operation. In this context, two main objectives are proposed. The first one is based on the proposal and application of risk-informed decision making methodology to evaluate the impact of changes to licensing bases, particularly in the ETF, using PSA models and considering aleatory uncertainties. The second is based on the adaptation and development of SSC reliability and availability models to consider not only the effect of aging, but also the effect of components management policies, in particular the testing and maintenance. Finally, these models have been joined to APS in order to obtain a new and extended APS (APSE). Some application cases, for both, risk-informed decision making on changes of licensing bases and for the use of the new APSA in the process of decision making, are provided in order to assess the feasibility and applicability of the new methodologies proposed The work of this thesis is part of the research supported by the Ministry of Economy and Competitiveness in the project ENE2013-45540-R, "Development of Advanced Surveillance Requirements with a focus on safety and competitiveness of Nuclear Power Plants operation in the long term", and in the Doctoral Fellow ENE2010-17449.[ES] En los últimos años se han desarrollado diversos estudios enfocados a garantizar la operación segura de las centrales nucleares (CCNN), tanto en la operación dentro de la vida de diseño como en la operación a largo plazo. En ambos casos, las centrales deben de afrontar una Revisión Periódica de Seguridad (RPS), la cual, involucra, entre otras tareas, la evaluación del impacto en el riesgo del envejecimiento de Estructuras, Sistemas y Componentes (ESC) y del papel de los programas de gestión de activos, tales como los programas de vigilancia y de mantenimiento de la central. Para llevar a cabo esta evaluación, urge la necesidad de extender los modelos actuales del Análisis Probabilista de Seguridad (APS) para que tenga en cuenta de forma explícita no sólo el efecto del envejecimiento sino también el efecto de las políticas de gestión de componentes activos, en particular, las pruebas y mantenimientos. La presente tesis doctoral pretende servir de ayuda en las evaluaciones de la seguridad de las CCNN, y en el contexto de las RPS, tanto en la operación dentro de la vida de diseño como en la operación a largo plazo. En este contexto se plantean dos objetivos principales. El primero, se basa en la propuesta y aplicación de una metodología de toma de decisiones basada en la utilización de los modelos y datos del APS para llevar a cabo la evaluación del impacto en el riesgo de cambios en las bases de licencia, concretamente en las ETF de las CCNN, en presencia de incertidumbres. El segundo, se basa en la adaptación y desarrollo de los modelos de fiabilidad y disponibilidad convencionales de ESC para que consideren de forma explícita no sólo el efecto del envejecimiento, sino también el efecto de las políticas de gestión de componentes activos, en particular de las pruebas y mantenimiento. Finalmente, estos modelos se han incorporado al APS con el objetivo de obtener un nuevo APS Extendido (APSE). Tanto para la toma de decisiones informada en el riesgo para cambios en las bases de licencia, cómo para la toma de decisiones utilizando el nuevo modelo extendido, APSE, se aportan casos de aplicación que demuestran la viabilidad y aplicabilidad de los mismos. El trabajo realizado en la presente tesis doctoral se enmarca dentro de la línea de investigación financiada por el Ministerio de Economía y Competitividad en el proyecto ENE2013-45540-R, "Desarrollo de Requisitos de vigilancia avanzados enfocados a la seguridad y competitividad de la operación a largo plazo de centrales nucleares" y en la beca de Formación de Personal Investigador (FPI) ENE2010-17449.[CA] En els últims anys s'han desenvolupat diversos estudis enfocats a garantir l'operació segura de les centrals nuclears (CCNN), tant en l'operació dins de la vida de disseny com en l'operació a llarg termini. En ambdos casos, les centrals han d'afrontar una Revisió Periòdica de Seguretat (RPS), la qual, involucra, entre altres tasques, l'avaluació de l'impacte en el risc de l'envelliment d'Estructures, Sistemes i components (ESC) i del paper dels programes de gestió d'actius, com els programes de vigilància i de manteniment de la central. Per dur a terme aquesta avaluació, urgeix la necessitat d'estendre els models actuals de l'Anàlisi Probabilista de Seguretat (APS) perquè tinga en compte de manera explícita no sols l'efecte de l'envelliment sinó també l'efecte de les polítiques de gestió de components actius, en particular, les proves i manteniments. La present tesi doctoral pretén servir d'ajuda en les avaluacions de la seguretat de les CCNN, i en el context de les RPS, tant en l'operació dins de la vida de disseny com en l'operació a llarg termini. En aquest context es plantegen dos objectius principals. El primer, es basa en la proposta i aplicació d'una metodologia de presa de decisions basada en la utilització dels models i dades de l'APS per a dur a terme l'avaluació de l'impacte en el risc de canvis en les bases de llicència, concretament en les ETF de les CCNN, en presència d'incerteses. El segon, es basa en l'adaptació i desenvolupament dels models de fiabilitat i disponibilitat convencionals d'estructures, sistemes i components perquè considerin de forma explícita no només l'efecte de l'envelliment, sinó també l'efecte de les polítiques de gestió de components actius, en particular de les proves i manteniment. Finalment, aquests models s'han incorporat al APS amb l'objectiu d'obtenir un nou APS Estès (APSE). Tant per a la presa de decisions informada en el risc per canvis en les bases de llicència com per a la presa de decisions utilitzant el nou model estès, APSE, s'aporten casos d'aplicació que demostren la viabilitat i aplicabilitat dels mateixos. El treball realitzat en la present tesi doctoral s'emmarca dins de la línia d'investigació finançada pel Ministeri d'Economia i Competitivitat en el projecte ENE2013-45540-R, "Desarrollo de Requisitos de vigilancia avanzados enfocados a la seguridad y competitividad de la operación a largo plazo de centrales nucleares" i en la beca de Formació de Personal Investigador (FPI) ENE2010-17449.Martón Lluch, I. (2015). Gestión de la operación, vigilancia y mantenimiento de equipos de seguridad de centrales nucleares a corto y largo plazo [Tesis doctoral no publicada]. Universitat Politècnica de València. https://doi.org/10.4995/Thesis/10251/58615TESI

Nuclear Power

The world of the twenty first century is an energy consuming society. Due to increasing population and living standards, each year the world requires more energy and new efficient systems for delivering it. Furthermore, the new systems must be inherently safe and environmentally benign. These realities of today's world are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. The goal of the book is to show the current state-of-the-art in the covered technical areas as well as to demonstrate how general engineering principles and methods can be applied to nuclear power systems

SPEA2-based safety system multi-objective optimization

Safety systems are designed to prevent the occurrence of certain conditions and their future development into a hazardous situation. The consequence of the failure of a safety system of a potentially hazardous industrial system or process varies from minor inconvenience and cost to personal injury, significant economic loss and death. To minimise the likelihood of a hazardous situation, safety systems must be designed to maximise their availability. Therefore, the purpose of this thesis is to propose an effective safety system design optimization scheme. A multi-objective genetic algorithm has been adopted, where the criteria catered for includes unavailability, cost, spurious trip and maintenance down time. Analyses of individual system designs are carried out using the latest advantages of the fault tree analysis technique and the binary decision diagram approach (BDD). The improved strength Pareto evolutionary approach (SPEA2) is chosen to perform the system optimization resulting in the final design specifications. The practicality of the developed approach is demonstrated initially through application to a High Integrity Protection System (HIPS) and subsequently to test scalability using the more complex Firewater Deluge System (FDS). Computer code has been developed to carry out the analysis. The results for both systems are compared to those using a single objective optimization approach (GASSOP) and exhaustive search. The overall conclusions show a number of benefits of the SPEA2 based technique application to the safety system design optimization. It is common for safety systems to feature dependency relationships between its components. To enable the use of the fault tree analysis technique and the BDD approach for such systems, the Markov method is incorporated into the optimization process. The main types of dependency which can exist between the safety system component failures are identified. The Markov model generation algorithms are suggested for each type of dependency. The modified optimization tool is tested on the HIPS and FDS. Results comparison shows the benefit of using the modified technique for safety system optimization. Finally the effectiveness and application to general safety systems is discussed.EThOS - Electronic Theses Online ServiceGBUnited Kingdo

SPEA2-based safety system multi-objective optimization

Safety systems are designed to prevent the occurrence of certain conditions and their future development into a hazardous situation. The consequence of the failure of a safety system of a potentially hazardous industrial system or process varies from minor inconvenience and cost to personal injury, significant economic loss and death. To minimise the likelihood of a hazardous situation, safety systems must be designed to maximise their availability. Therefore, the purpose of this thesis is to propose an effective safety system design optimization scheme. A multi-objective genetic algorithm has been adopted, where the criteria catered for includes unavailability, cost, spurious trip and maintenance down time. Analyses of individual system designs are carried out using the latest advantages of the fault tree analysis technique and the binary decision diagram approach (BDD). The improved strength Pareto evolutionary approach (SPEA2) is chosen to perform the system optimization resulting in the final design specifications. The practicality of the developed approach is demonstrated initially through application to a High Integrity Protection System (HIPS) and subsequently to test scalability using the more complex Firewater Deluge System (FDS). Computer code has been developed to carry out the analysis. The results for both systems are compared to those using a single objective optimization approach (GASSOP) and exhaustive search. The overall conclusions show a number of benefits of the SPEA2 based technique application to the safety system design optimization. It is common for safety systems to feature dependency relationships between its components. To enable the use of the fault tree analysis technique and the BDD approach for such systems, the Markov method is incorporated into the optimization process. The main types of dependency which can exist between the safety system component failures are identified. The Markov model generation algorithms are suggested for each type of dependency. The modified optimization tool is tested on the HIPS and FDS. Results comparison shows the benefit of using the modified technique for safety system optimization. Finally the effectiveness and application to general safety systems is discussed.EThOS - Electronic Theses Online ServiceGBUnited Kingdo

Nuclear Power

The world of the twenty first century is an energy consuming society. Due to increasing population and living standards, each year the world requires more energy and new efficient systems for delivering it. Furthermore, the new systems must be inherently safe and environmentally benign. These realities of today's world are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. The goal of the book is to show the current state-of-the-art in the covered technical areas as well as to demonstrate how general engineering principles and methods can be applied to nuclear power systems