Advances In Nuclear Safety Analysis Methodology - Energy and Power Textbooks

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Advances In Nuclear Safety Analysis Methodology

John Luxat

Price: USD: 250.00
ISBN: 978-0-08-102365-5

Copyright date: Dec 01, 2029
Pages: 608
Not Yet Published
Elsevier Science & Technology

This book belongs to the following Subject Areas:
Energy and Power

Key Features

Provides a comprehensive description of the analysis methods for Design Basis Accident (DBA) and Beyond Design Basis Accident (BDBA) events

Gives practical, yet high level insight into nuclear safety analysis, explaining how it is carried out and why it is performed in a particular way

Consolidates essential information on the nuclear safety analysis methodology that currently exists only in research journal papers

About the Book

Advances in Nuclear Safety Analysis Methodology provides a unique exposition on leading-edge safety analysis techniques applied in nuclear reactor licensing. Chapters discuss accidents with major significance to nuclear safety, governing safety design objectives, analysis methods used to quantify the behavior of the reactor, and associated safety-related systems. After sections on both Design Basis Accidents (DBA) and Beyond Design Basis Accidents (BDBA), the equally important topic of analysis relevant to accident management and emergency response is also addressed. This book will provide researchers, safety analysis and nuclear operational staff with a practical, highly authoritative and consolidated guide on the state-of-the-art.

Readership

Scientists and engineers in academia and industry working on nuclear power plant safety; Graduate students or senior level undergraduate students at universities with nuclear engineering programs and their teachers; Specialists working for nuclear regulatory bodies of technical safety organisations. Technical staff at nuclear power utilities who need to upgrade their knowledge and skills in modern nuclear safety analysis

Content

1. Introduction/Overview

SECTION 1: ANALYSIS OF DESIGN BASIS ACCIDENTS
2. Review of International Best Estimate and Uncertainty Analysis Methodologies
3. Analysis of Loss of Coolant Accidents in PWR to support limiting LOCA accident redefinition and safety margins
4. Analysis of Reactivity Initiated Accidents (RIA) in LWR to quantify margins to coolable core geometry
5. Analysis of Steam Line Break accidents in LWR
6. Analysis of Loss of Coolant Accidents with ECCS impairments in PHWR reactors
7. Coupled physics and thermal hydraulic analysis using TRACE/PARCS computer codes

SECTION 2: ANALYSIS OF BEYOND DESIGN BASIS ACCIDENTS
8. Analysis of Station Blackout (SBO) sequences in LWR and PHWR leading to core cooling degradation
9. High Temperature materials behaviour and uncertainties during core degradation in LWR and PHWR severe accidents
10. Analysis of hydrogen generation, transport and combustion phenomena in severe accidents
11. Analysis of fission product release and transport phenomena from degraded cores and molten corium pools
12. Analysis of containment integrity under thermal hydraulic and hydrogen combustion loadings
13. Level 2 Probabilistic Safety Analysis of Severe Accidents.

SECTION 3: SUPPORTING ACCIDENT MANAGEMENT AND EMERGENCY RESPONSE
14. Level 3 Probabilistic Safety Analysis of off-site fission product release to the environment during severe accidents
15. Assessment of the effectiveness of Severe Accident Management Guidelines (SAMG) in PWR, BWR and PHWR reactors