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Probabilistic Risk Assessment Pra

Probabilistic Risk Assessment  PRA  PDF
Author: U.S. Nuclear Regulatory Commission. Division of Risk Analysis
Publisher:
ISBN:
Size: 77.13 MB
Format: PDF, Kindle
Category : Nuclear facilities
Languages : en
Pages :
View: 2533

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Probabilistic Risk Assessment Procedures Guide For Nasa Managers And Practitioners

Probabilistic Risk Assessment Procedures Guide for NASA Managers and Practitioners PDF
Author: National Aeronautics Administration
Publisher: CreateSpace
ISBN: 9781503235298
Size: 68.15 MB
Format: PDF, ePub, Docs
Category :
Languages : en
Pages : 430
View: 444

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Probabilistic Risk Assessment (PRA) is a comprehensive, structured, and logical analysis method aimed at identifying and assessing risks in complex technological systems for the purpose of cost-effectively improving their safety and performance. NASA's objective is to better understand and effectively manage risk, and thus more effectively ensure mission and programmatic success, and to achieve and maintain high safety standards at NASA. NASA intends to use risk assessment in its programs and projects to support optimal management decision making for the improvement of safety and program performance. In addition to using quantitative/probabilistic risk assessment to improve safety and enhance the safety decision process, NASA has incorporated quantitative risk assessment into its system safety assessment process, which until now has relied primarily on a qualitative representation of risk. Also, NASA has recently adopted the Risk-Informed Decision Making (RIDM) process. Over the years, NASA has been a leader in most of the technologies it has employed in its programs. One would think that PRA should be no exception. In fact, it would be natural for NASA to be a leader in PRA because, as a technology pioneer, NASA uses risk assessment and management implicitly or explicitly on a daily basis. NASA has probabilistic safety requirements (thresholds and goals) for crew transportation system missions to the International Space Station (ISS). NASA intends to have probabilistic requirements for any new human spaceflight transportation system acquisition.as a valuable addition to supplement existing deterministic and experience-based engineering methods and tools. During the past several decades, much has been written on PRA methods and applications. Several university and practitioner textbooks and sourcebooks currently exist, but they focus on applications of PRA to industries other than aerospace. Although some of the techniques used in PRA originated in work for aerospace and military applications, no comprehensive reference currently exists for PRA applications to aerospace systems. This PRA Procedures Guide, in the present second edition, is neither a textbook nor an exhaustive sourcebook of PRA methods and techniques. It provides a set of recommended procedures, based on the experience of the authors, that are applicable to different levels and types of PRA that are performed for aerospace applications. It therefore serves two purposes, to: 1. Complement the training material taught in the NASA PRA course for practitioners, and together with the Fault Tree Handbook, the Risk-Informed Decision Making Handbook, the Bayesian Inference handbook, the Risk Management Handbook, and the System Safety Handbook to provide quantitative risk methodology documentation, and to provide aerospace PRA practitioners in selecting an analysis approach that is best suited for their applications.

Probabilistic Risk Assessment Pra

Probabilistic Risk Assessment  PRA  PDF
Author:
Publisher:
ISBN:
Size: 17.52 MB
Format: PDF, Kindle
Category :
Languages : en
Pages :
View: 1309

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This document describes the current status of the methodologies used in probabilistic risk assessment (PRA) and provides guidance for the application of the results of PRAs to the nuclear reactor regulatory process. The PRA studies that have been completed or are underway are reviewed. The levels of maturity of the methodologies used in a PRA are discussed. Insights derived from PRAs are listed. The potential uses of PRA results for regulatory purposes are discussed.

Space Systems Probabilistic Risk Assessment Pra

Space Systems  Probabilistic Risk Assessment  PRA  PDF
Author: British Standards Institute Staff
Publisher:
ISBN: 9780580663826
Size: 20.32 MB
Format: PDF, Kindle
Category :
Languages : en
Pages : 28
View: 6086

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Space technology, Risk analysis, Risk assessment, Safety engineering, Hazards, Estimation, Probability calculations, Management, Management techniques, Management operations, Spacecraft, Space transport, Nuclear power

Probabilistic Risk Assessment Pra

Probabilistic Risk Assessment  PRA  PDF
Author: U.S. Nuclear Regulatory Commission. Office of Personnel Organization Development and Training
Publisher:
ISBN:
Size: 17.18 MB
Format: PDF, Kindle
Category : Nuclear industry
Languages : en
Pages : 17
View: 6085

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Demonstrate Ames Laboratory Capability In Probabilistic Risk Assessment Pra

Demonstrate Ames Laboratory Capability in Probabilistic Risk Assessment  PRA   PDF
Author:
Publisher:
ISBN:
Size: 77.74 MB
Format: PDF, Docs
Category :
Languages : en
Pages : 55
View: 5754

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In response to the damage which occurred during the Three Mile Island nuclear accident, the Nuclear Regulatory Commission (NRC) has implemented a Probabilistic Risk Assessment (PRA) program to evaluate the safety of nuclear power facilities during events with a low probability of occurrence. The PRA can be defined as a mathematical technique to identify and rank the importance of event sequences that can lead to a severe nuclear accident. Another PRA application is the evaluation of nuclear containment buildings due to earthquakes. In order to perform a seismic PRA, the two conditional probabilities of ground motion and of structural failure of the different components given a specific earthquake are first studied. The first of these is termed probability of exceedance and the second as seismic fragility analysis. The seismic fragility analysis is then related to the ground motion measured in terms of ''g'' to obtain a plant level fragility curve.

Use Of Probabilistic Risk Assessment In Expert System Usage For Nuclear Power Plant Safety

Use of Probabilistic Risk Assessment in Expert System Usage for Nuclear Power Plant Safety PDF
Author:
Publisher:
ISBN:
Size: 65.83 MB
Format: PDF
Category :
Languages : en
Pages :
View: 5097

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The introduction of probability risk assessments (PRA's) to nuclear power plants in the Rasmussen Report (WASH-1400) gave us a means of evaluating the risk to the public associated with the operation of nuclear power plants, at least on a relative basis. While the choice of the ''source term'' and methodology in a PRA significantly influence the absolute probability and the consequences of core melt, comparison of two PRA calculations for two configurations of the same plant, carried out on a consistent basis, can be readily identify the increase in risk associated with going from one configuration of a plant to another by removing components or systems from service. This ratio of core melt probabilities (assuming no recovery of failed systems) obtained from two PRA calculations for different configurations was the criterion (called ''risk factor'') chosen as a basis for making a decision in an expert system as to what mitigating action, if any, would be taken to avoid a trip situation from developing. PRISIM was developed by JBF Associates of Knoxville under the sponsorship of the NRC as a system for Resident Inspectors at nuclear power plants to provide them with a relative safety status of the plant under all configurations. PRISIM calculated the risk factor--the ration of core melt probabilities of the plant under the current configuration relative to the normal configuration with all systems functioning--using an algorithm that emulates the results of the original PRA. It also presents time and core melt (assuming no recovery of systems or components).

Satisfying Safety Goals By Probabilistic Risk Assessment

Satisfying Safety Goals by Probabilistic Risk Assessment PDF
Author: Hiromitsu Kumamoto
Publisher: Springer Science & Business Media
ISBN: 1846286824
Size: 55.38 MB
Format: PDF, ePub, Mobi
Category : Technology & Engineering
Languages : en
Pages : 253
View: 243

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This book is a methodological approach to the goal-based safety design procedure that will soon be an international requirement. This is the first single volume book to describe how to satisfy safety goals by modern reliability engineering. Its focus is on the quantitative aspects of the international standards using a methodological approach. Case studies illustrate the methodologies presented.

Oconee Pra

Oconee PRA PDF
Author: Nuclear Safety Analysis Center
Publisher:
ISBN:
Size: 24.56 MB
Format: PDF, Kindle
Category : Nuclear power plants
Languages : en
Pages : 69
View: 1870

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Probabilistic Risk Assessment In The Nuclear Power Industry

Probabilistic Risk Assessment in the Nuclear Power Industry PDF
Author: R. R. Fullwood
Publisher: Pergamon
ISBN:
Size: 70.89 MB
Format: PDF
Category : Social Science
Languages : en
Pages : 318
View: 3980

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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.

Probabilistic Risk Assessment Standard For Advanced Non Lwr Nuclear Power Plants

Probabilistic Risk Assessment Standard for Advanced Non LWR Nuclear Power Plants PDF
Author: ASME/ANS Joint Committee on Nuclear Risk Management
Publisher:
ISBN:
Size: 20.12 MB
Format: PDF, ePub, Docs
Category : Nuclear power plants
Languages : en
Pages : 490
View: 479

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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.