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Book Probabilistic Assessment of Common Cause Failures in Nuclear Power Plants

Download or read book Probabilistic Assessment of Common Cause Failures in Nuclear Power Plants written by Shuo Yu and published by . This book was released on 2013 with total page 91 pages. Available in PDF, EPUB and Kindle. Book excerpt: Common cause failures (CCF) are a significant contributor to risk in complex technological systems, such as nuclear power plants. Many probabilistic parametric models have been developed to quantify the systems subject to the CCF. Existing models include the beta factor model, the multiple Greek letter model, the basic parameter model, the alpha factor model and the binomial failure rate model. These models are often only capable of providing a point estimate, when there are limited CCF data available. Some recent studies have proposed a Bayesian approach to quantify the uncertainties in CCF modeling, but they are limited in addressing the uncertainty in the common failure factors only. This thesis presents a multivariate Poisson model for CCF modeling, which combines the modeling of individual and common cause failures into one process. The key idea of the approach is that failures in a common cause component group of n components are decomposed into superposition of k (>n) independent Poisson processes. Empirical Bayes method is utilized for simultaneously estimating the independent and common cause failure rates which are mutually exclusive. In addition, the conventional CCF parameters can be evaluated using the outcomes of the new approach. Moreover, the uncertainties in the CCF modeling can also be addressed in an integrated manner. The failure rate is estimated as the mean value of the posterior density function while the variance of the posterior represents the variation of the estimate. A MATLAB program of the Monte Carlo simulation was developed to check the behavior of the proposed multivariate Poisson (MVP) model. Superiority over the traditional CCF models has been illustrated. Furthermore, due to the rarity of the CCF data observed at one nuclear power plant, data of the target plant alone are insufficient to produce reliable estimates of the failure rates. Data mapping has been developed to make use of the data from source plants of different sizes. In this thesis, data mapping is combined with EB approach to partially assimilate information from source plants and also respect the data of the target plant. Two case studies are presented using different database. The results are compared to the empirical values provided by the United States Nuclear Regulatory Commission (USNRC).

Book Reactor Safety Study

Download or read book Reactor Safety Study written by U.S. Atomic Energy Commission and published by . This book was released on 1974 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book NUREG CR

    Book Details:
  • Author : U.S. Nuclear Regulatory Commission
  • Publisher :
  • Release : 1977
  • ISBN :
  • Pages : 48 pages

Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Common Cause Failure Analysis in Event Assessment

Download or read book Common Cause Failure Analysis in Event Assessment written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the approach taken by the U.S. Nuclear Regulatory Commission to the treatment of common-cause failure in probabilistic risk assessment of operational events. The approach is based upon the Basic Parameter Model for common-cause failure, and examples are illustrated using the alpha-factor parameterization, the approach adopted by the NRC in their Standardized Plant Analysis Risk (SPAR) models. The cases of a failed component (with and without shared common-cause failure potential) and a component being unavailable due to preventive maintenance or testing are addressed. The treatment of two related failure modes (e.g., failure to start and failure to run) is a new feature of this paper. These methods are being applied by the NRC in assessing the risk significance of operational events for the Significance Determination Process (SDP) and the Accident Sequence Precursor (ASP) program.

Book Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants  level 1

Download or read book Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants level 1 written by International Atomic Energy Agency and published by . This book was released on 1992 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides guidance on conducting a Level 1 PSA for internal events in nuclear power plants. The main emphasis is on the procedural steps of the PSA rather than the details of the corresponding methods. The report is intended to assist technical persons managing or performing PSAs.

Book Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants

Download or read book Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 1995 with total page 116 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Determining the Quality of Probabilistic Safety Assessment  PSA  for Applications in Nuclear Power Plants

Download or read book Determining the Quality of Probabilistic Safety Assessment PSA for Applications in Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 194 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides an approach for achieving the technical consistency of probabilistic safety assessments (PSAs) needed to support various PSA applications. The approach involves the consideration of a set of technical features, called attributes, of the major PSA elements relevant for various applications.

Book Risk and Safety Analysis of Nuclear Systems

Download or read book Risk and Safety Analysis of Nuclear Systems written by John C. Lee and published by John Wiley & Sons. This book was released on 2012-01-12 with total page 504 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Advanced Seminar on Common Cause Failure Analysis in Probabilistic Safety Assessment

Download or read book Advanced Seminar on Common Cause Failure Analysis in Probabilistic Safety Assessment written by Aniello Amendola and published by Springer Science & Business Media. This book was released on 2013-03-14 with total page 345 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the Ispra Course held at the Joint Research Centre, Ispra, Italy, November 16-19, 1987

Book Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants

Download or read book Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants written by IAEA and published by International Atomic Energy Agency. This book was released on 2024-03-15 with total page 289 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Reliability and Risk Analysis

Download or read book Reliability and Risk Analysis written by Norman J. McCormick and published by Academic Press. This book was released on 1981-07-28 with total page 462 pages. Available in PDF, EPUB and Kindle. Book excerpt: A prior knowledge of probability theory would be helpful for the material in Part I; likewise, a previous introduction to the engineered safety features of a nuclear reactor makes portions of Part II easier to understand. For those without this background, introductory material is provided in Chapter 2 and the appendixes.

Book Proceedings of the International ANS ENS Topical Meeting on Probabilistic Risk Assessment  September 20 24  1981  Port Chester  New York

Download or read book Proceedings of the International ANS ENS Topical Meeting on Probabilistic Risk Assessment September 20 24 1981 Port Chester New York written by and published by . This book was released on 1982 with total page 578 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Systems Reliability Engineering and Risk Assessment

Download or read book Nuclear Systems Reliability Engineering and Risk Assessment written by Jerry B. Fussell and published by SIAM. This book was released on 1977-01-01 with total page 884 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Probabilistic Risk Assessment in the Nuclear Power Industry

Download or read book Probabilistic Risk Assessment in the Nuclear Power Industry written by R. R. Fullwood and published by Pergamon. This book was released on 1988 with total page 354 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes a number of the more important improvements in risk assessment methodology in the nuclear industry, developed over the last decade. It presents them in an instructive way so as to be suitable for those wishing to understand the techniques. The methodology of modern probabilistic risk assessment (PRA) is discussed in detail. This book is divided into six parts. Part I, Protecting the Public Health and Safety provides an overview of risk analysis including results presentation, safety goals, emergency planning, and public perception. Part II, the Mathematics, which is necessary to understand the text. Part III, safety Aspects of Light Water Reactors describes the types of plants and goes on to discuss accident initiator selection and frequencies. Part IV, PRA, describes system modelling, human factors analysis, data bases, codes, system interactions, external events, core melt physics, and the transport of radionuclides to the public. Part V discusses 34 types of applications of PRA. Part VI, Resources, provides a glossary, references, and an index. Problems are provided at the end of each part to both stimulate understanding and introduce additional material. This book would be a very valuable addition to the reference library of practitioners in the risk assessment business. It is also a useful instructional text for graduate and undergraduate nuclear engineering students as well as newcomers to the field.

Book Reliability and Probabilistic Safety Assessment in Multi Unit Nuclear Power Plants

Download or read book Reliability and Probabilistic Safety Assessment in Multi Unit Nuclear Power Plants written by Senthil C. Kumar and published by Academic Press. This book was released on 2023-02-09 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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