Probabilistic Risk Assessment (PRA) Insights
Author: R. Fitzpatrick
Publisher:
Published: 1987
Total Pages: 142
ISBN-13:
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Author: R. Fitzpatrick
Publisher:
Published: 1987
Total Pages: 142
ISBN-13:
DOWNLOAD EBOOKAuthor:
Publisher:
Published: 1987
Total Pages:
ISBN-13:
DOWNLOAD EBOOKAuthor: U.S. Nuclear Regulatory Commission. Division of Risk Analysis
Publisher:
Published: 1984
Total Pages: 360
ISBN-13:
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Publisher:
Published: 1984
Total Pages:
ISBN-13:
DOWNLOAD EBOOKThis 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.
Author: Mohammad Modarres
Publisher: CRC Press
Published: 2016-04-27
Total Pages: 408
ISBN-13: 1420003496
DOWNLOAD EBOOKBased on the author's 20 years of teaching, Risk Analysis in Engineering: Techniques, Tools, and Trends presents an engineering approach to probabilistic risk analysis (PRA). It emphasizes methods for comprehensive PRA studies, including techniques for risk management. The author assumes little or no prior knowledge of risk analysis on the p
Author:
Publisher:
Published: 1989
Total Pages: 8
ISBN-13:
DOWNLOAD EBOOKProbabilistic risk assessment (PRA) has proven to be an important tool in the safety assessment of nuclear reactors throughout the world. Decision making with regard to many safety issues has been facilitated by both general insights from and direct application of this technology. Key uses of PRA are discussed and some examples of successful applications are cited. The benefits and limitations of PRA are also discussed as well as the broader outlook for applications of PRA. 9 refs.
Author: Tunc Aldemir
Publisher: World Scientific
Published: 2018-04-25
Total Pages: 554
ISBN-13: 9813225629
DOWNLOAD EBOOKOver 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.
Author:
Publisher:
Published: 1990
Total Pages: 106
ISBN-13:
DOWNLOAD EBOOKThe discipline of probabilistic risk analysis (PRA) has become so mature in recent years that it is now being used routinely to assist decision-making throughout the nuclear industry. This includes decision-making that affects design, construction, operation, maintenance, and regulation. Unfortunately, not all sub-areas within the larger discipline of PRA are equally mature, '' and therefore the many different types of engineering insights from PRA are not all equally reliable. 93 refs., 4 figs., 1 tab.
Author: Tim Bedford
Publisher: Cambridge University Press
Published: 2001-04-30
Total Pages: 228
ISBN-13: 9780521773201
DOWNLOAD EBOOKA graduate level textbook on probabilistic risk analysis, aimed at statisticians, operations researchers and engineers.
Author:
Publisher:
Published: 1993
Total Pages: 8
ISBN-13:
DOWNLOAD EBOOKThis paper summarizes the results from the recently completed EBR-II Probabilistic Risk Assessment (PRA) and provides an analysis of the source of risk of the operation of EBR-II from both internal and external initiating events. The EBR-II PRA explicitly accounts for the role of reactivity feedbacks in reducing fuel damage. The results show that the expected core damage frequency from internal initiating events at EBR-II is very low, 1. 6 10−6 yr−1, even with a wide definition of core damage (essentially that of exceeding Technical Specification limits). The probability of damage, primarily due to liquid metal fires, from externally initiated events (excluding earthquake) is 3.6 10−6 yr−1. overall these results are considerably better than results for other research reactors and the nuclear industry in general and stem from three main sources: low likelihood of loss of coolant due to low system pressure and top entry double, vessels; low likelihood of loss of decay heat removal due to reliance on passive means; and low likelihood of power/flow mismatch due to both passive feedbacks and reliability of rod scram capability.