Reliability And Probabilistic Safety Assessment In Multi Unit Nuclear Power Plants
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Reliability and Probabilistic Safety Assessment in Multi-Unit Nuclear Power Plants by Senthil C. Kumar Pdf
Reliability and Probabilistic Safety Assessment in Multi-Unit Nuclear Power Plants presents the risk contributions from single and multi-unit Nuclear Power Plants to help aggregate the risks that may arise due to applicable hazards and operating states. The book combines the key features of multi-unit risk assessment in one resource, reviewing the practices adopted in various countries around the globe to exemplify the dependencies between units on a site. These dependencies include multi-unit interactions, environmental stresses, the sharing of systems, and the sharing of human resource in a control room, factors which can all introduce an increase potential for heightened accident conditions. This book helps readers systematically identify events and evaluate techniques of possible accident outcomes within multi-units. It serves as a ready reference for PSA analysts in identifying a suitable site and the sharing of resources, while carrying out multi-unit risk assessments to ensure the safety of the public and the environment. It will also be valuable for nuclear researchers, designers and regulators of nuclear power plants, nuclear regulatory agencies, PSA engineers and practicing safety professionals. Provides a framework for nuclear and PSA researchers and professionals on the design and operation of multi-unit risk assessments Reviews practices adopted in various regions around the globe to analyze dependencies between units Includes modeling techniques of inter-connections and shared resources, as well as risk aggregation
Multi-unit Probabilistic Safety Assessment by IAEA Pdf
The accident at the Fukushima Daiichi Nuclear Power Plant underlined the need to assess the nuclear safety of multi-unit sites considering the accident sequences involving more than one reactor units on site. The objective of this Safety Report is to provide a methodology for the development of a Multi-unit Probabilistic Safety Assessment (MUPSA). It provides practical examples and an overview of the actual state of practice in this area. The publication provides a detailed description of Level 1 MUPSA methodology, the principles of development of Level 2 MUPSA models and the path forward for multi-unit consequence analysis (Level 3 MUPSA). In addition, it summarizes the experience available in Member States in the area of MUPSA. The scope of this Safety Report includes consideration of various hazards and plant operational states normally considered in PSA development in the multi-unit context.
Selected Topics in Probabilistic Safety Assessment by Dan Serbanescu,Anatoli Paul Ulmeanu Pdf
Probabilistic Safety Assessment (PSA) is a structured, comprehensive, and logical analysis method aimed at identifying and assessing risks in complex technological systems, such as the nuclear power plants. It is also known as probabilistic risk assessment – PRA. This book presents the theoretical basis to understand the numerous and complex aspects that are covered by PSA and it will help the reader to better understand and to effectively manage risks. The book provides PSA methods and techniques and it includes recommended procedures that are based on the experience of the authors and applicable to different levels and types of PSA that are used for nuclear power plants applications. It can be used as extra reading for PSA courses for practitioners and it provides quantitative risk methodology documentation for PSA.
Consideration of External Hazards in Probabilistic Safety Assessment for Single Unit and Multi-Unit Nuclear Power Plants by International Atomic Energy Agency Pdf
This publication outlines the generic methodology for probabilistic safety assessment (PSA) of nuclear power plants (NPPs) against external hazards. It integrates design, procedural, operational, human factors and both protection and mitigation aspects that are essential to model a NPP response to an external hazard and to assess the associated risk. It specifically addresses the identification and screening of external hazards considering the multi-unit impact.
Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants by International Atomic Energy Agency Pdf
Presents a practical approach for incorporating human reliability analysis (HRA) into probabilistic safety assessment (PSA). This document describes the steps needed and the documentation that should be provided both to support the PSA itself and to ensure effective communication of important information arising from the studies.
Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants by International Atomic Energy Agency Pdf
The objective of this Safety Guide is to provide recommendations for meeting the requirements of GSR Part 4 (Rev. 1) in the development and application of Level 1 Probabilistic Safety Assessments (PSAs) for nuclear power plants (NPPs). The recommendations provided in this publication promoting technical consistency among Level 1 PSA studies, in order to provide reliable support for applications of PSAs and risk informed decision making, particularly to support the design of NPPs and decision making during plant commissioning and operation. The revised Safety Guide's scope encompasses the main methodological aspects of PSA and in particular has been updated to reflect developments in specific areas, such as passive systems reliability, computer based systems reliability, combinations of hazards, human reliability analysis and to expand the scope of PSA to include site level risk considerations such as multi-unit and spent fuel pool PSA.
Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units by International Atomic Energy Agency Pdf
The technical approach described in this publication builds on the use of a single unit probabilistic safety assessment (PSA) and identifies considerations that are needed from the multi-unit perspective. This is the first attempt to expand the current PSA process to take account of multi-unit issues, and has been done by distilling lessons learned from the Fukushima Daiichi accident and other multi-unit events, and by reviewing previous PSAs and supporting research that have addressed the risks of multi-unit accidents. The publication provides a roadmap and methodology for performing a multi-unit PSA, proposes a set of site level risk metrics, and presents examples of approaches to resolve specific issues.
Risk and Safety Analysis of Nuclear Systems by John C. Lee,Norman J. McCormick Pdf
The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear applications, although there is an emphasis placed on the analysis of nuclear systems. The second half of the book covers the safety analysis of nuclear energy systems, an analysis of major accidents and incidents that occurred in commercial nuclear plants, applications of PRA techniques to the safety analysis of nuclear power plants (focusing on a major PRA study for five nuclear power plants), practical PRA examples, and emerging techniques in the structure of dynamic event trees and fault trees that can provide a more realistic representation of complex sequences of events. The book concludes with a discussion on passive safety features of advanced nuclear energy systems under development and approaches taken for risk-informed regulations for nuclear plants.
Probabilistic Safety Assessment for Optimum Nuclear Power Plant Life Management (PLiM) by Gennadij V Arkadov,Alexander F Getman,Andrei N Rodionov Pdf
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. 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
The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety by International Atomic Energy Agency Pdf
This safety report establishes guidelines on the role that probabilistic safety assessment can play as part of an overall safety assurance programme in nuclear power plants. It also describes a framework for probabilistic safety criteria (PSC) and provides guidance for the establishment of PSC values.
Probabilistic Safety Assessment in the Chemical and Nuclear Industries by Ralph Fullwood Pdf
In addition to presenting methodology, it shows how to identify accident vulnerability in the two industries. It reviews the causes of the two major nuclear accidents and many fatal accidents in the chemical industry, including Bhopal. Many examples of applications of PSA to both industries are presented."--BOOK JACKET. "Problems are included at the end of many chapters with answers at the back of the book."--Jacket.
Probabilistic Safety Assessment of WWER440 Reactors by Zoltan Kovacs Pdf
The aim of this book is to summarize probabilistic safety assessment (PSA) of nuclear power plants with WWER440 reactors and demonstrate that the plants are safe enough for producing energy even in light of the Fukushima accident. The book examines level 1 and 2 full power, low power and shutdown PSA, and summarizes the author’s experience gained during the last 35 years in this area. It provides useful examples taken from PSA training courses the author has lectured and organized by the International Atomic Energy Agency. Such training courses were organised in Argonne National Laboratory (Chicago, IL, USA), Abdus Salaam International Centre for Theoretical Physics (Trieste, Italy), Malaysia, Vietnam and Jordan to support experts from developing countries. The role of PSA for the plants is an estimation of the risks in absolute terms and in comparison with other risks of the technical and the natural world. Plant-specific PSAs are being prepared for the plants and being applied for detection of weaknesses, design improvement and backfitting, incident analysis, accident management, emergency preparedness, prioritization of research and development and to support the regulatory activities. There are three levels of PSA, being performed for full power and low power operation and shutdown operating modes of the plants: level 1, 2 and 3 PSA. The nuclear regulatory authorities do not require the level 3 PSA for the plants in the member countries of the European Union. This means that only a limited number of NPPs in Europe have the level 3 PSA available. However, in the light of the Fukushima accident the performance of such analyses is strongly recommended in the future. This book is intended for professionals working in the nuclear industry, researchers and students interested in safety of operational plants.
Advanced Concepts In Nuclear Energy Risk Assessment And Management by Aldemir Tunc Pdf
Over the past 30 years, numerous concerns have been raised in the literature regarding the capability of static modeling approaches such as the event-tree (ET)/fault-tree (FT) methodology to adequately account for the impact of process/hardware/software/firmware/human interactions on nuclear power plant safety assessment, and methodologies to augment the ET/FT approach have been proposed. Often referred to as dynamic probabilistic risk/safety assessment (DPRA/DPSA) methodologies, which use a time-dependent phenomenological model of system evolution along with a model of its stochastic behavior to model for possible dependencies among failure events. The book contains a collection of papers that describe at existing plant level applicable DPRA/DPSA tools, as well as techniques that can be used to augment the ET/FT approach when needed. Contents: Shutdown Probabilistic Safety Assessment (Marko Čepin) Dynamic Probabilistic Risk Assessment Model Validation and Application -- Experience with ADS-IDAC, Version 2.0 (Kevin Coyne and Ali Mosleh) MCDET: A Tool for Integrated Deterministic Probabilistic Safety Analyses (Martina Kloos, Nadine Berner, Joerg Peschke and Josef Scheuer) Why Sequence Dynamics Matters in PSA: Checking Consistency of Probabilistic and Deterministic Analyses (J M Izquierdo, J Hortal, M Sánchez and E Meléndez) Level 2 Probabilistic Risk Assessment Using Dynamic Event Tree Analysis (Douglas M Osborn, Tunc Aldemir, Richard S Denning and Diego Mandelli) EDF Experience in Integrated Deterministic Probabilistic Safety Analysis for Risk Assessment (Valentin Rychkov) Offsite Power Reliability Assessment for Nuclear Power Plants: An Application of Dynamic Reliability to Power Systems (Pierre Henneaux and Pierre-Etienne Labeau) Stochastic Differential Equations in Dynamic Reliability (Vytis Kopustinskas, Henrikas Pragarauskas and Juozas Augutis) Dynamic Event Tree Modeling of a Reactor Coolant Pump Seal LOCA (Kyle Metzroth, Richard Denning and Tunc Aldemir) Markov/Cell-to-Cell Mapping Technique for Stochastic Modeling of Dynamic Systems (Tunc Aldemir) Dynamic Flowgraph Methodology (DFM) Modeling of Nuclear and Advanced Technology System Risk and Reliability Scenarios (Sergio Guarro and Michael Yau) Dynamic Behavior of Nuclear Power Plant State Under Severe Accident Conditions: Analysis by the GO-FLOW Methodology and the Consideration of Loop Structures (Takeshi Matsuoka) Dynamic Accident Scenario Generation, Modeling and Post-Processing for the Integrated Deterministic and Probabilistic Safety Analysis of Nuclear Power Plants (Francesco Di Maio and Enrico Zio) Software Behavior Modeling for Dynamic Probabilistic Risk Assessment: Perspectives (C S Smidts) Readership: Graduate students, researchers and professionals in the field of nuclear engineering, risk analysis and reliability engineering. Keywords: Probabilistic Risk Assessment;Nuclear Energy;Nuclear Plant Reliability and SafetyReview: Key Features: Except for PSAM, ESREL and PSA conference proceedings which may contain some relevant papers, the most recent review publication on similar topics is Proceedings of the International Workshop on Dynamic Reliability, C Smidts, T Aldemir (Eds.), The Center for Risk and Reliability, University of Maryland, USA (2007) In addition to capturing more recent developments, the proposed publication differs from 2007 publication by concentrating on nuclear energy and also containing papers on risk management The book is a compilation of papers by almost all prominent researchers active in the field of dynamic probabilistic safety/ris
Probabilistic Safety Assessment Benchmarks of Multi-Unit, Multi-reactor Sites by IAEA. Pdf
The Coordinated Research Project on Probabilistic Safety Assessment Benchmarks for Multiunit Multi Reactor Sites (2018-2022) brought together the experts from the IAEA Member States with mainly water-cooled reactor technologies to utilize, test and further develop their current or planned probabilistic safety assessments methods and assumptions by conducting and comparing results of meaningful multiunit multi reactor type probabilistic safety assessment (MUPSA) benchmark exercises. The objective was to share national expertise and participate in shared benchmark calculations. These calculations involved the development of MUPSA, based on single unit probabilistic safety assessments available in Member States. This publication is intended for nuclear engineers, researchers, code developers, experimentalists in nuclear energy fields, reactor vendors and developers, university professors and students, regulatory experts, and nuclear power plant planners.
