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Probabilistic safety assessment for optimum nuclear power plant life management (PLiM): Theory and application of reliability analysis methods for major power plant components

G V Arkadov, A F Getman, All-Russia Scientific Research Institute for Nuclear Power Plants Operation (VNIIAES), Russia and A N Rodionov, Institute for Radiological Protection and Nuclear Safety (IRSN), France

Woodhead Publishing Series in Energy No. 49

 - discusses the theory and application of probabilistic safety assessment methods used to calculate nuclear power plant (NPP) durability and lifetime
 -  reviews probabilistic methods in their application to NPP components and ageing pipelines for the forecasting of NPP resource lifetime and safety
 -  addresses the key areas of probabilistic safety analysis, optimization of the operations through in-service inspection (ISI) utilising non-destructive testing, and maintenance, service and repair approaches

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.

Published in association with Cambridge International Science Publishing

£145.00 / US$245.00 / €175.00

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About the authors

Dr Gennadij V. Arkadov and Prof. Alexander F. Getman are based at the All-Russia Scientific Research Institute for Nuclear Power Plants Operation (VNIIAES), Russia. Dr Andrei N. Rodionov is based at the Institute for Radiological Protection and Nuclear Safety (IRSN), France.

Titles which may also be of interest:
Radioactive waste management and contaminated site clean-up
Nuclear decommissioning
Infrastructure and methodologies for the justification of nuclear power programmes

Contents

PART 1 PROBABILISTIC METHODS FOR PREDICTING THE RELIABILITY OF EQUIPMENT
PART 2 PRACTICAL APPLICATION OF PROBABILISTIC METHODS FOR STRENGTH RELIABILITY

PART 1 PROBABILISTIC METHODS FOR PREDICTING THE RELIABILITY OF EQUIPMENT

Terminology, concepts and definitions
 - Abbreviations, terminology, symbols
 - Basic terms and formulas of reliability theory, probability theory and mathematical statistics
 - Safety of nuclear power stations. Active and passive safety features
 - Strength reliability and its connection with nuclear safety and service life of NPP
 - Ageing of equipment and pipelines. Ageing considered and not considered in design
 - Quantitative characteristics of reliability and their implications for safety analysis and optimisation of operating costs
 - Formal-statistical and physico-statistical approaches to predicting the reliability of technical systems

Formal–statistical methods
 - The simplest model
 - Markov processes
 - The Monte Carlo method
 - Risk theory
 - Accounting for ageing in formal mathematical models

Physico–statistical approach: Procedures using the defect-free model of structural material
 - Probability of failure under random static loading
 - The method proposed by Rzhanitsyn
 - Probability of failure under cyclic loading causing fatigue of constructional materials

Physico–statistical approach taking defects into account and using binomial distribution
 - Key elements of the behaviour of structures with crack-type defects
 - Methods of determining the probability of failure on the basis of computer program MAVR-1.1

Physico-statistical models based on the residual defectiveness of structural materials
 - Regularities of the formation, detection and omission of defects during non-destructive testing
 - Residual defects as the most important characteristic of the state of the structure
 - Probabilistic methods for assessing strength and service life taking into account residual defectiveness in structural elements

PART 2 PRACTICAL APPLICATION OF PROBABILISTIC METHODS FOR STRENGTH RELIABILITY

Probabilistic analysis of safety: Increasing the reliability and safety of nuclear power plant components
 - Probabilistic safety analysis model taking into account the initiating event ‘a large break loss-of-coolant accident’
 - Taking into account in PSA models the first level of ageing effects of systems and equipment in nuclear power plant
 - Method of bringing the product to the desired level of quality, reliability and safety security
 - Improving the safety of main circulation pipelines of nuclear power plant with first generation VVER-440 reactors

Optimisation of non-destructive testing
 - General
 - Overview of approaches to optimizing ISI, based on information about risks: Semiquantitative approach
 - Optimisation of the risk-based oriented in-service inspection at the Ignalinsk nuclear power plant
 - Quantitative approach to optimisation of ISI

Optimisation of hydraulic tests, technical certification and planned-preventative maintenance
 - Method for determination of the optimum pressure of hydraulic stress tests to ensure reliability and operational safety
 - Optimisation of the frequency of hydraulic tests
 - Optimisation of the technical inspection and scheduled preventive maintenance

Using probabilistic methods for solving the problem of ensuring leak tightness of heat exchanger pipes of nuclear power plant steam generators
 - Ensuring the leak tightness of tubes of vertical and horizontal steam generators
 - Application of the Monte Carlo method to the problem of ensuring the integrity of HETs of VSG
 - Application of a probabilistic method based on two-parameter distribution
 - Application of the generalized 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
 - Guidance Document RD EO-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’
 - Conclusions