Advanced Concepts in Nuclear Energy Risk Assessment and Management - Original PDF

دانلود کتاب Advanced Concepts in Nuclear Energy Risk Assessment and Management - Original PDF

Author: Tunc Aldemir

توضیحات کتاب :

Advanced Concepts in Nuclear Energy Risk Assessment and Management (Modern Nuclear Energy Analysis Methods)

سرچ در وردکت | سرچ در گودریدز | سرچ در اب بوکز | سرچ در آمازون | سرچ در گوگل بوک

ضمانت بازگشت

ضمانت بازگشت

فایل های تست شده

فایل های تست شده

پرداخت آنلاین

پرداخت آنلاین

تضمین کیفیت

تضمین کیفیت

دانلود فوری

دانلود فوری

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.

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Ebook details:
عنوان: Advanced Concepts in Nuclear Energy Risk Assessment and Management (Modern Nuclear Energy Analysis Methods)
نویسنده: Aldemir, Tunc
ناشر: World Scientific Publishing Company (April 25, 2018)
زبان: English
شابک: 9813225602, 978-9813225602

 

9789813225619 9813225610 9789813225626 9813225629


حجم: 26 Mb
فرمت: Original PDF

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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

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