National Repository of Grey Literature 4 records found  Search took 0.01 seconds. 
FACTORS LIMITING LIFE TIME OF NUCLEAR POWER PLANTS WITH PRESSURIZED-WATER REACTORS
Křivánek, Robert ; Kolat, Pavel (referee) ; Liszka, Ervin (referee) ; Fiedler, Jan (advisor)
The aim of the thesis is to analyze the state of preparedness of nuclear power plants (NPP) for long term operation (LTO) based on the IAEA SALTO (Safety Aspects of Long Term Operation) peer review service, analysis of the most significant failures, accidents and operational experience with type reactors PWR/VVER focusing on cases caused by equipment ageing and identification of major structures and components limiting life time of PWR/VVER-type nuclear power plants, and possible measures to ensure their required service life. Based on the results of the IAEA SALTO peer review service, an analysis of the main deficiencies and measures of NPPs in preparation for a safe LTO was performed, focusing on topics whose deeper knowledge is important for the future more precise determination of technical factors limiting the lifetime of NPPs. The main deficiencies and measures in the preparatory phase for LTO and the most important technical measures are summarized in chapter 4.5. The main deficiencies and the most important technical corrective measures in the area of ageing management of structures and components are discussed separately. The history of major failures and operational experience of nuclear power plants with PWR/VVER reactors from the point of view of ageing of structures and components is analyzed in chapter 6.2. The result is a statistic analysis of ageing-related events, an overview of the most significant PWR/VVER reactor failures with an impact on their service life, a statistical overview and discussion of the most important degradation mechanisms, and other important findings from the history of major failures and operational experience. Chapter 6.3 analyzes factors limiting the operation of nuclear power plants with PWR/VVER reactors with focus on structures and components potentially limiting the life of PWR/VVER reactors and possible measures to ensure their required life. In conclusion, the main reasons of permanent shut down of NPPs (actual and potential) for 40, 60 and 80 years of operation and the measures to ensure their required life are summarized.
INTEGRATED SOLUTION OF DIAGNOSTICS OF PRODUCTION EQUIPMENT IN THE CZECH ENERGY INDUSTRY
Cvešpr, Pavel ; Szabó,, Radek (referee) ; Kratochvíl, Petr (referee) ; Hammer, Miloš (advisor)
This dissertation thesis is concerned with the diagnostics of the main production facilities in Czech power engineering with a focus on its integrating role in the process of gaining, saving and processing information for the purpose of evaluating the technical state of the operated facilities and the plan to manage their lifetime. It is divided into two parts, theoretical and practical. The theoretical part presents the conclusions of examination of the needs of involved workers in the areas of diagnostics, maintenance and expert assessment of technical state of equipment. These conclusions were formulated based on the completed analysis of the current status ("as - is" analysis) of performing diagnostics of systems operated in the technological units of both nuclear and classical power engineering. The monitored equipment involves electrical installations and machinery, steel and building constructions, measuring instruments and vibrodiagnostics. Based on the analysis results, process diagrams are created for the solution of partial tasks. The analysis of the proposed solution for problems in question ("should - be" analysis) includes a design of the fundamental scheme of the data model for a software solution and a design of data flows from the individual data sources. The following part presents an application layer which includes a detailed description of major functionalities. Further, important activities and procedures are described that are necessary to evaluate the technical state of equipment. The practical part deals with the implementation of the LTO suite software product in the environment of power engineering in Czech Republic, specifically within ČEZ, a.s.. The LTO suite functionality is demonstrated in this part of the thesis by screens recorded within the LTO suite individual modules, which work above the actual data. It starts with the initial screen for configuration of displayed data, continues to present examples of the equipment register, planning, processing and saving of information collected through the diagnostic activities over to the module of integration – analytical layer, which is designed for evaluation of the technical state of equipment at the entered date with a reporting output. The thesis also includes the chapters on "Aims of the Study" and "Conclusion". The key chapter presents the "Benefits of the Study", whose overview describes the original results of the research as well as those applicable also outside the power engineering area.
FACTORS LIMITING LIFE TIME OF NUCLEAR POWER PLANTS WITH PRESSURIZED-WATER REACTORS
Křivánek, Robert ; Kolat, Pavel (referee) ; Liszka, Ervin (referee) ; Fiedler, Jan (advisor)
The aim of the thesis is to analyze the state of preparedness of nuclear power plants (NPP) for long term operation (LTO) based on the IAEA SALTO (Safety Aspects of Long Term Operation) peer review service, analysis of the most significant failures, accidents and operational experience with type reactors PWR/VVER focusing on cases caused by equipment ageing and identification of major structures and components limiting life time of PWR/VVER-type nuclear power plants, and possible measures to ensure their required service life. Based on the results of the IAEA SALTO peer review service, an analysis of the main deficiencies and measures of NPPs in preparation for a safe LTO was performed, focusing on topics whose deeper knowledge is important for the future more precise determination of technical factors limiting the lifetime of NPPs. The main deficiencies and measures in the preparatory phase for LTO and the most important technical measures are summarized in chapter 4.5. The main deficiencies and the most important technical corrective measures in the area of ageing management of structures and components are discussed separately. The history of major failures and operational experience of nuclear power plants with PWR/VVER reactors from the point of view of ageing of structures and components is analyzed in chapter 6.2. The result is a statistic analysis of ageing-related events, an overview of the most significant PWR/VVER reactor failures with an impact on their service life, a statistical overview and discussion of the most important degradation mechanisms, and other important findings from the history of major failures and operational experience. Chapter 6.3 analyzes factors limiting the operation of nuclear power plants with PWR/VVER reactors with focus on structures and components potentially limiting the life of PWR/VVER reactors and possible measures to ensure their required life. In conclusion, the main reasons of permanent shut down of NPPs (actual and potential) for 40, 60 and 80 years of operation and the measures to ensure their required life are summarized.
INTEGRATED SOLUTION OF DIAGNOSTICS OF PRODUCTION EQUIPMENT IN THE CZECH ENERGY INDUSTRY
Cvešpr, Pavel ; Szabó,, Radek (referee) ; Kratochvíl, Petr (referee) ; Hammer, Miloš (advisor)
This dissertation thesis is concerned with the diagnostics of the main production facilities in Czech power engineering with a focus on its integrating role in the process of gaining, saving and processing information for the purpose of evaluating the technical state of the operated facilities and the plan to manage their lifetime. It is divided into two parts, theoretical and practical. The theoretical part presents the conclusions of examination of the needs of involved workers in the areas of diagnostics, maintenance and expert assessment of technical state of equipment. These conclusions were formulated based on the completed analysis of the current status ("as - is" analysis) of performing diagnostics of systems operated in the technological units of both nuclear and classical power engineering. The monitored equipment involves electrical installations and machinery, steel and building constructions, measuring instruments and vibrodiagnostics. Based on the analysis results, process diagrams are created for the solution of partial tasks. The analysis of the proposed solution for problems in question ("should - be" analysis) includes a design of the fundamental scheme of the data model for a software solution and a design of data flows from the individual data sources. The following part presents an application layer which includes a detailed description of major functionalities. Further, important activities and procedures are described that are necessary to evaluate the technical state of equipment. The practical part deals with the implementation of the LTO suite software product in the environment of power engineering in Czech Republic, specifically within ČEZ, a.s.. The LTO suite functionality is demonstrated in this part of the thesis by screens recorded within the LTO suite individual modules, which work above the actual data. It starts with the initial screen for configuration of displayed data, continues to present examples of the equipment register, planning, processing and saving of information collected through the diagnostic activities over to the module of integration – analytical layer, which is designed for evaluation of the technical state of equipment at the entered date with a reporting output. The thesis also includes the chapters on "Aims of the Study" and "Conclusion". The key chapter presents the "Benefits of the Study", whose overview describes the original results of the research as well as those applicable also outside the power engineering area.

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