SUSTAINABLE DEVELOPMENT
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Probabilistic safety assessment methods are used to calculate nuclear power plant durability and resource lifetime. Successful calculation of the reliability and ageing of… Read more
SUSTAINABLE DEVELOPMENT
Save up to 30% on top Physical Sciences & Engineering titles!
Woodhead Publishing Series in Energy
Preface
Part One: Probabilistic methods for predicting the reliability of equipment
Chapter 1: Terminology, concepts and definitions
1.1 Terminology, abbreviations, symbols
Abbreviations
Symbols
1.2 Basic terms and formulas of reliability theory, probability theory and mathematical statistics
1.3 Safety of nuclear power stations. Active and passive safety features
1.4 Strength reliability and its connection with nuclear safety and service life of NPP
1.5 Ageing of equipment and pipelines. Ageing considered and not considered in design
1.6 Quantitative characteristics of reliability and their implications for safety analysis and optimisation of operating costs
1.7 Formal-statistical and physico-statistical approaches to predicting the reliability of technical systems
Chapter 2: Formal-Statistical methods
2.1 The simplest model
2.2 Markov processes
2.3 The Monte Carlo method
2.4 Risk theory
2.5 Accounting for ageing in formal mathematical models
Chapter 3: Physico-statistical approach: Procedures using the defect-free model of structural material
3.1 Probability of failure under random static loading. The method proposed by Rzhanitsyn
3.2 Probability of failure under cyclic loading causing fatigue of constructional materials
Chapter 4: Physico-statistical approach taking defects into account and using binomial distribution
4.1 Key elements of the behaviour of structures with crack-type defects
4.2 Methods of determining failure probability using a binomial distribution
Chapter 5: Physico-statistical models based on the residual defectiveness of structural materials
5.1 Regularities of the formation, detection and omission of defects during non-destructive testing
Study of detection of defects at the given constant conditions of inspection
Comparison of different inspection methods
Investigation of inspection methods to enhance their effectiveness
Investigation of the influence of the ‘human factor’ on test results
5.2 Residual defects as the most important characteristic of the state of the structure. Methods of determination
5.3 Probabilistic methods for assessing strength and service life taking into account residual defectiveness in structural elements
Part Two: Practical application of probabilistic methods for strength reliability
Chapter 6: Probabilistic analysis of safety: Increasing the reliability and safety of nuclear power plant components
6.1 Probabilistic safety analysis model taking into account the initiating event ‘a large break loss-of-coolant accident’
6.2 Taking into account in PSA models the first level of ageing effects of systems and equipment in nuclear power plant
6.3 Method of bringing the product to the desired level of quality, reliability and safety security
6.4 Improving the safety of main circulation pipelines of nuclear power plant with first-generation VVER-440 reactors
Chapter 7: Optimisation of non-destructive testing
7.1 General
7.2 Overview of approaches to optimising ISI, based on information about risks: Semiquantitative approach
7.3 Optimisation of the risk-based oriented in-service inspection at the Ignalinsk nuclear power plant111
7.4 Quantitative approach to optimisation of ISI
Chapter 8: Optimisation of hydraulic tests, technical certification and planned-preventative maintenance
8.1 Method for determination of the optimum pressure of hydraulic stress tests to ensure reliability and operational safety
8.2 Optimisation of the frequency of hydraulic tests
8.3 Optimisation of the technical inspection and scheduled preventive maintenance
Chapter 9: Using probabilistic methods for solving the problem of ensuring leak tightness of heat exchanger tubes of nuclear power plant steam generators
9.1 Ensuring the leak tightness of tubes of vertical and horizontal steam generators
9.2 Application of the Monte Carlo method to the problem of ensuring the integrity of HETs of VSG
9.3 Application of a probabilistic method based on two-parameter distribution
9.4 Application of the generalised method of probabilistic analysis and systematic methodology for analyzing and ensuring integrity of steam generator heat exchanger tubes in nuclear power plants with VVER-1000 and VVER-440 reactors
9.5 Guidance Document RD E0-0552-2004 ‘Guidelines on the application of system methodology to ensure the integrity of steam generator heat exchanger tubes of NPP with VVER-440 and VVER-1000 reactors’
9.6 Conclusions
Appendix 1
Appendix 2: Application of the Markov model for forecasting reliability of PWR pipelines
Appendix 3: Russian Scientific Research Institute of Operation of Nuclear Power Plants (VNIIAES)
References
Index
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