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Book Probabilistic Risk Assessment Standard for Advanced Non LWR Nuclear Power Plants

Download or read book Probabilistic Risk Assessment Standard for Advanced Non LWR Nuclear Power Plants written by ASME/ANS Joint Committee on Nuclear Risk Management and published by . This book was released on 2013 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt: ANS RA-S-1.4-2013 establishes requirements for a probabilistic risk assessment (PRA) for advanced non-light water reactor (LWR) nuclear power plants. The requirements in this standard were developed for a broad range of PRA scopes that may include the following: (a) Different sources of radioactive material both within and outside the reactor core but within the boundaries of the plant whose risks are to be determined in the PRA scope selected by the user. The technical requirements in this trial-use version of the standard are limited to sources of radioactive material within the reactor coolant system (RCS) pressure boundary (RCPB). For pool-type reactors with no RCPB, the scope includes sources within the RCS. Technical requirements for other sources of radioactive material such as the spent fuel system are deferred to future editions of this standard; (b) Different plant operating states including various levels of power operation and shutdown modes; (c) Initiating events caused by internal hazards, such as internal events, internal fires, and internal floods, and external hazards such as seismic events, high winds, and external flooding; (d) Different event sequence end states, including core or plant damage states (PDSs), and release categories that are sufficient to characterize mechanistic source terms, including releases from event sequences involving two or more reactor units or modules for PRAs on multireactor or multiunit plants; (e) Evaluation of different risk metrics including the frequencies of modeled core and PDSs, release categories, risks of off-site radiological exposures and health effects, and the integrated risk of the multiunit plant if that is within the selected PRA scope. The risk metrics supported by this standard are established metrics used in existing LWR Level 3 PRAs such as frequency of radiological consequences (e.g., dose, health effects) that are inherently technology neutral. Surrogate risk metrics used in LWR PRAs such as core damage frequency and large early release frequency are not used as they may not be applicable to non-LWR PRAs; (f) Quantification of the event sequence frequencies, mechanistic source terms, off-site radiological consequences, risk metrics, and associated uncertainties, and using this information in a manner consistent with the scope and applications PRA.

Book ASME ANS RA S 1 4 2013  Probabilistic Risk Assessment Standard for Advanced Non LWR Nuclear Power Plants

Download or read book ASME ANS RA S 1 4 2013 Probabilistic Risk Assessment Standard for Advanced Non LWR Nuclear Power Plants written by American Nuclear Society and published by . This book was released on 2013 with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt: This trial-use draft standard establishes requirements for a probabilistic risk assessment (PRA) for advanced non-light water reactor (LWR) nuclear power plants. Following a 36-month period for trial use and comment, it is expected that this draft standard, revised as necessary will be submitted to the American National Standards Institute (ANSI) for approval as an American National Standard.

Book Advanced Concepts In Nuclear Energy Risk Assessment And Management

Download or read book Advanced Concepts In Nuclear Energy Risk Assessment And Management written by Tunc Aldemir and published by World Scientific. This book was released on 2018-04-25 with total page 554 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Probabilistic Risk Assessment  PRA

Download or read book Probabilistic Risk Assessment PRA written by U.S. Nuclear Regulatory Commission. Division of Risk Analysis and published by . This book was released on 1984 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Probabilistic Risk Assessment

Download or read book Probabilistic Risk Assessment written by United States. General Accounting Office and published by . This book was released on 1985 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Selected Topics in Probabilistic Safety Assessment

Download or read book Selected Topics in Probabilistic Safety Assessment written by Dan Serbanescu and published by Springer Nature. This book was released on 2020-02-19 with total page 179 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications

Download or read book Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications written by American Society of Mechanical Engineers. ASME. and published by . This book was released on 2002 with total page 96 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 American National Standard

Download or read book American National Standard written by American Nuclear Society. Standards Committee Working Group ANS-58.21 and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of this standard1! are to set forth requirements for external-events probabilistic risk assessments ~PRAs! used to support riskinformed decisions for commercial light water reactor nuclear power plants and to prescribe a method for applying these requirements for specific applications. Additional or revised requirements may be needed for other reactor designs.

Book Risk Importance Measures in the Design and Operation of Nuclear Power Plants

Download or read book Risk Importance Measures in the Design and Operation of Nuclear Power Plants written by Ivan Vrbanic and published by . This book was released on 2017 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt: In using risk-informed approaches for ensuring safety of operating nuclear power plants (NPPs), risk importance measures obtained from probabilistic risk assessments (PRAs) of the plants are integral elements of consideration in many cases. Obtaining these measures in appropriate forms is helpful for decision makers and can facilitate the use of risk information.

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 American National Standard

Download or read book American National Standard written by American Nuclear Society. Standards Committee Working Group ANS-58.23 and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This standard sets forth requirements for fire probabilistic risk assessments (Fire PRAs) used to support risk-informed decisions for commercial light water reactor nuclear power plants and prescribes general requirements for Fire PRA practice intended to suit a wide range of applications. This standard covers fires occurring within the plant. The American National Standard External-Events PRA Methodology, ANSI/ANS-58.21-2007, covers fires occurring outside the plant.

Book ASME RA Sb 2005

Download or read book ASME RA Sb 2005 written by and published by . This book was released on with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety

Download or read book The Role of Probabilistic Safety Assessment and Probabilistic Safety Criteria in Nuclear Power Plant Safety written by International Atomic Energy Agency and published by . This book was released on 1992 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Probabilistic Risk Assessment

Download or read book Probabilistic Risk Assessment written by and published by . This book was released on 2000 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt: Contains references to documents in the NASA Scientific and Technical (STI) Database.