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Advanced concepts in nuclear energy risk assessment and management

Author: Tunc Aldemir
Publisher: Singapore : World Scientific Publishing Co. Pte. Ltd., [2018]
Series: Modern nuclear energy analysis methods, vol. 1
Edition/Format:   eBook : Document : EnglishView all editions and formats
Summary:
"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  Read more...
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Genre/Form: Electronic books
Additional Physical Format: Print version:
Advanced concepts in nuclear energy risk assessment and management.
Singapore : World Scientific Publishing Co. Pte. Ltd., [2018]
(OCoLC)990429521
Material Type: Document, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: Tunc Aldemir
ISBN: 9789813225619 9813225610 9789813225626 9813225629
OCLC Number: 1034562184
Description: 1 online resource.
Contents: Intro; Contents; Preface; List of Contributors; 1. Shutdown Probabilistic Safety Assessment; 1.1. Introduction; 1.1.1. Objective; 1.1.2. State-of-the-Art; 1.2. Shutdown PSA Methods; 1.2.1. Definition of Representative POS Groups; 1.2.2. Definition and Analysis of Initiating Events; 1.2.3. Accident Sequence Development and Analysis; 1.2.3.1. Mathematical Model of Event Tree; 1.2.3.2. Damage States; 1.2.4. Success Criteria Analysis; 1.2.5. System Analysis; 1.2.6. Human Reliability Analysis; 1.2.6.1. Reliability Model; 1.2.6.2. Performance Shaping Factors; 1.2.6.3. Dependency 1.2.6.4. Human Reliability Analysis in Shutdown PSA; 1.2.7. Parameter Estimation Analysis; 1.2.7.1. CCF Analysis; 1.2.8. Quantification and Interpretation of Results; 1.3. Results; 1.4. Conclusion; References; 2. Dynamic Probabilistic Risk Assessment Model Validation and Application --
Experience with ADS-IDAC, Version 2.0; 2.1. Introduction; 2.2. Overview of the ADS-IDAC, Version 2.0, Platform; 2.2.1. Nuclear Power Plant Model; 2.2.2. Crew Modeling; 2.2.3. Dynamic Event Tree Scheduler; 2.3. Calibration and Validation; 2.3.1. Crew Behavior Observations 2.3.2. Generalization of Observed Operator Behaviors; 2.3.3. Identification of Simulation Branching Rules; 2.3.4. Validation and Verification; 2.3.4.1. Predicted Crew Behaviors Using ADS-IDAC; 2.3.4.2. Comparison of ADS-IDAC Predicted Behavior to Empirical Data; 2.4. Risk Assessment Applications of ADS-IDAC, Version 2.0; 2.4.1. Knowledge-Based Actions for SG Tube Rupture; 2.4.2. Information Filtering --
The TMI Scenario; 2.4.3. Accident Precursor Analysis; 2.4.3.1. Risk Assessment Using Traditional Analysis; 2.4.3.2. Dynamic Assessment Using ADS-IDAC; 2.5. Conclusions; References 3. MCDET: A Tool for Integrated Deterministic Probabilistic Safety Analyses; 3.1. Introduction; 3.2. MCDET Methods; 3.2.1. Aleatory Uncertainty Analysis; 3.2.1.1. MC simulation; 3.2.1.2. Dynamic Event Tree (DET) simulation; 3.2.1.3. Combination of MC and DET simulation; 3.2.1.4. Efficient estimators; 3.2.2. Epistemic Uncertainty Analysis; 3.3. Simulation Control; 3.3.1. Principles of the Scheduling Approach; 3.3.2. Requirements for Simulation Codes; 3.3.3. Architecture of the Generic Scheduling; 3.4. Crew Module; 3.5. Applications; 3.5.1. SBO Scenario with Power Supply Recovery 3.5.1.1. Scenario characteristics and aleatory uncertainties; 3.5.1.2. Results; 3.5.2. EOP "Secondary Side Bleed and Feed"; 3.5.2.1. Human actions and aleatory uncertainties; 3.5.2.2. Results; 3.5.3. Fire Scenario with Fire-Fighting Means; 3.5.3.1. Fire event, fire-fighting means and uncertainties; 3.5.3.2. Analysis steps and selected results; 3.6. Conclusions; References; 4. Why Sequence Dynamics Matters in PSA: Checking Consistency of Probabilistic and Deterministic Analyses; 4.1. Introduction; 4.2. Main Concepts in PSA and DSA; 4.2.1. Plant and Safety Systems
Series Title: Modern nuclear energy analysis methods, vol. 1
Responsibility: edited by Tunc Aldemir.

Abstract:

"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."--Publisher's website.

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