Description
WOODHEAD PUBLISHING Probabilistic Safety Assessment For Optimum Nuclear Power Plant Life Management 2012 Edition by ARKADOV G V ET. AL.
Probabilistic safety assessment methods are used to calculate nuclear power plant durability and resource lifetime. Successful calculation of the reliability and ageing of components is critical for forecasting safety and directing preventative maintenance, and Probabilistic safety assessment for optimum nuclear power plant life management provides a comprehensive review of the theory and application of these methods.Part one reviews probabilistic methods for predicting the reliability of equipment. Following an introduction to key terminology, concepts and definitions, formal-statistical and various physico-statistical approaches are discussed. Approaches based on the use of defect-free models are considered, along with those using binomial distribution and models based on the residual defectiveness of structural materials. The practical applications of probabilistic methods for strength reliability are subsequently explored in part two. Probabilistic methods for increasing the reliability and safety of nuclear power plant components are investigated, as are the use of such methods for optimising non-destructive tests, hydraulic tests, technical certification and planned-preventative maintenance. Finally, the book concludes with information on the use of probabilistic methods in ensuring leak tightness of nuclear power plant steam generator heat exchanger pipes.With its distinguished authors, Probabilistic safety assessment for optimum nuclear power plant life management is a valuable reference for all nuclear plant designers, operators, nuclear safety engineers and managers, as well as academics and researchers in this field. Woodhead Publishing Series in EnergyPrefacePart One: Probabilistic methods for predicting the reliability of equipmentChapter 1: Terminology, concepts and definitions1.1 Terminology, abbreviations, symbolsAbbreviationsSymbols1.2 Basic terms and formulas of reliability theory, probability theory and mathematical statistics1.3 Safety of nuclear power stations. Active and passive safety features1.4 Strength reliability and its connection with nuclear safety and service life of NPP1.5 Ageing of equipment and pipelines. Ageing considered and not considered in design1.6 Quantitative characteristics of reliability and their implications for safety analysis and optimisation of operating costs1.7 Formal-statistical and physico-statistical approaches to predicting the reliability of technical systemsChapter 2: Formal-Statistical methods2.1 The simplest model2.2 Markov processes2.3 The Monte Carlo method2.4 Risk theory2.5 Accounting for ageing in formal mathematical modelsChapter 3: Physico-statistical approach: Procedures using the defect-free model of structural material3.1 Probability of failure under random static loading. The method proposed by Rzhanitsyn3.2 Probability of failure under cyclic loading causing fatigue of constructional materialsChapter 4: Physico-statistical approach taking defects into account and using binomial distribution4.1 Key elements of the behaviour of structures with crack-type defects4.2 Methods of determining failure probability using a binomial distributionChapter 5: Physico-statistical models based on the residual defectiveness of structural materials5.1 Regularities of the formation, detection and omission of defects during non-destructive testingStudy of detection of defects at the given constant conditions of inspectionComparison of different inspection methodsInvestigation of inspection methods to enhance their effectivenessInvestigation of the influence of the 'human factor' on test results5.2 Residual defects as the most important characteristic of the state of the structure. Methods of determination5.3 Probabilistic methods for assessing strength and service life taking into account residual defectiveness in structural elementsPart Two: Practical application of probabilistic methods for strength reliabilityChapter 6: Probabilistic analysis of safety: Increasing the reliability and safety of nuclear power plant components6.1 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 plant6.3 Method of bringing the product to the desired level of quality, reliability and safety security6.4 Improving the safety of main circulation pipelines of nuclear power plant with first-generation VVER-440 reactorsChapter 7: Optimisation of non-destructive testing7.1 General7.2 Overview of approaches to optimising ISI, based on information about risks: Semiquantitative approach7.3 Optimisation of the risk-based oriented in-service inspection at the Ignalinsk nuclear power plant1117.4 Quantitative approach to optimisation of ISIChapter 8: Optimisation of hydraulic tests, technical certification and planned-preventative maintenance8.1 Method for determination of the optimum pressure of hydraulic stress tests to ensure reliability and operational safety8.2 Optimisation of the frequency of hydraulic tests8.3 Optimisation of the technical inspection and scheduled preventive maintenanceChapter 9: Using probabilistic methods for solving the problem of ensuring leak tightness of heat exchanger tubes of nuclear power plant steam generators9.1 Ensuring the leak tightness of tubes of vertical and horizontal steam generators9.2 Application of the Monte Carlo method to the problem of ensuring the integrity of HETs of VSG9.3 Application of a probabilistic method based on two-parameter distribution9.4 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 reactors9.5 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 ConclusionsAppendix 1Appendix 2: Application of the Markov model for forecasting reliability of PWR pipelinesAppendix 3: Russian Scientific Research Institute of Operation of Nuclear Power Plants (VNIIAES)ReferencesIndex