Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and iPWR-SMRs

1st Edition - March 3, 2025
Imprint: Academic Press
Editor: Christophe Herer
Language: English
Paperback ISBN:
9 7 8 - 0 - 3 2 3 - 9 0 4 9 4 - 0
eBook ISBN:
9 7 8 - 0 - 3 2 3 - 9 0 4 9 5 - 7

Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and SMRs presents key phenomena, models, advantages, and drawbacks of current methods. The book guides the re… Read more

Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and iPWR-SMRs

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Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and SMRs presents key phenomena, models, advantages, and drawbacks of current methods. The book guides the reader through the preparation and review of the thermal-hydraulic part of a safety analysis report and equips them with the knowledge to perform thermal-hydraulic studies with confidence. Starting with an introduction to thermal-hydraulics and two-phase flows, the book covers key models such as the Homogeneous Equilibrium Model and Drift Flux, Main Phenomena and associated models, including critical flow, heat transfer and void fraction, and then moves onto cover nuclear safety analyses and code.

It contains fundamental tools to help readers understand complicated phenomena that can happen in various accidental conditions, along with key principles to help readers when using advanced simulation tools. This book is suitable for a broad audience, including non-specialized readers seeking independent advice and technicians or engineers working in nuclear facilities. It will provide students in engineering disciplines with a solid understanding of the thermal-hydraulics of nuclear reactors and safety, which will enable them to work safely and efficiently and drive research forward.

Title of Book
Cover image
Title page
Table of Contents
Copyright
Contributors
Preface
Acknowledgment
Chapter 1. Introduction: Thermal-hydraulics and two-phase flows
1.1 A tentative definition of thermal-hydraulics
1.2 Thermal-hydraulics challenges
1.3 Thermal-hydraulics applications and new perspectives
1.4 About this book
Chapter 2. Key definitions
2.1 Single-phase flow variables
2.1.1 Space and time averages
2.1.2 Flow parameters and transport properties
2.1.3 Characteristics values, dimensionless numbers, and hydraulic diameter
2.2 Thermodynamic relations
2.2.1 Evaluation of the energy
2.2.2 Enthalpy balance
2.2.2.1 Energy contribution
2.2.2.2 Energy transfer
2.2.3 Phase change
2.2.4 Thermodynamic quality
2.3 Two-phase flow variables
2.3.1 Void fraction and slip ratio
2.3.2 Other variables and drift flux parameters
2.3.3 Flow regimes
Chapter 3. Key models for two-phase flows
3.1 Two-phase average fluid properties
3.2 Homogeneous equilibrium model
3.3 Separated flow model
3.4 Two-fluid model
3.5 Two-fluid model with drift flux
Chapter 4. Main phenomena and associated models
4.1 Void fraction
4.1.1 Void fraction in saturated two-phase flow
4.1.1.1 Models with slip ratio
4.1.1.2 Models with drift flux
4.1.2 Void fraction in subcooled regime
4.2 Pressure and flow rate
4.2.1 Head losses
4.2.1.1 Friction or regular head loss
4.2.1.2 Singular head loss
4.2.2 Reversible pressure changes
4.2.3 Flow rate
4.2.4 Pumping power
4.2.5 Pump cavitation
4.3 Heat transfer
4.3.1 Heat transfer from single-phase to two-phase flows
4.3.1.1 Single-phase heat transfer in laminar flow
4.3.1.2 Heat transfer in subcooled flow boiling
4.3.1.3 Saturated flow boiling heat transfer
4.3.2 Temperature distribution in a PWR fuel rod
4.3.2.1 Temperature distribution in the fuel pellet
4.3.2.2 Temperature distribution in the gap and the cladding
4.3.2.3 Temperature distribution in rod
4.4 Critical flow
4.4.1 Single-phase critical flow for an ideal gas
4.4.2 Critical two-phase flow
4.4.2.1 Upstream saturated conditions
4.4.2.2 Upstream subcooled conditions
4.4.3 Other considerations on critical flow
4.5 Countercurrent flow
4.5.1 Prediction of flooding
4.5.2 Prediction of flow reversal
4.5.3 CCFL in complex geometries
4.6 Condensation
4.6.1 Principles
4.6.1.1 Safety condenser
4.6.1.2 Condensation in containment
4.6.2 Models
4.6.2.1 Condensation of pure vapor
4.6.2.2 Condensation in the presence of non-condensable gas
4.7 Natural circulation
4.7.1 Principles
4.7.2 Models for natural circulation (steady state)
4.7.2.1 Buoyancy
4.7.2.2 Resulting mass flow rate
4.8 Some definitions and phenomena specific to transient situations
4.8.1 Residual power
4.8.2 Steam binding
4.8.3 Stagnation point
4.8.4 Reflux condensation
4.8.5 Loop seal
4.8.6 Chimney effect
4.8.7 Nonequilibrium effect
Chapter 5. General principles of nuclear reactor safety analysis
5.1 Introduction
5.1.1 Requirements and guides on safety analysis
5.1.2 Order of magnitude of thermal-hydraulic parameters in PWR and LW-SMR
5.2 Nuclear safety objectives and some safety concepts
5.3 Methodology for deterministic thermal-hydraulic analyses and BEPU
5.3.1 Deterministic safety analysis process
5.3.1.1 Deterministic safety analysis process
5.3.1.2 Identification of postulated initiating events (PIEs) and design-basis events (DBEs)
5.3.1.3 Definition of acceptance criteria
5.3.1.4 Selection and validation of calculation tools
5.3.1.5 Choice of DSA approaches
5.3.1.6 Evaluation of accident analysis results to quantify margins
5.3.2 The combined DSA approach
5.3.3 Best estimate plus uncertainty DSA approach
5.3.4 Realistic DSA approach
5.3.5 Extended BEPU or integrated DSA and PSA approach (IPDSA)
5.4 Calculation tools and overall validation
5.4.1 Thermal-hydraulic system codes
5.4.2 Subchannel analysis codes
5.4.3 Overall validation of calculation tools
5.4.3.1 Overall validation for passive systems and SMRs
5.5 Conclusion
Chapter 6. Innovative passive systems
6.1 Description of innovative passive systems
6.2 Specificities of innovative passive systems
6.3 Models for passive systems (steady state)
Chapter 7. Departure from nucleate boiling (DNB) analyses
7.1 Boiling crisis
7.2 CHF correlations
7.2.1 CHF correlations for flow inside a round tube
7.2.1.1 Forms of the correlations
7.2.1.2 Variables of the correlations
7.2.1.3 Examples of CHF correlations in tubes
7.2.1.4 Application of CHF correlations in tubes
7.2.2 CHF correlations for PWR
7.2.2.1 Uniform axial flux shape
7.2.2.2 Nonuniform axial flux shape
7.2.3 CHF correlations for SMR
7.2.4 Analytical models and novel approaches for boiling crisis
7.3 DNB analyses
7.3.1 Requirements for the CHF correlation
7.3.2 Applications of the correlation
Chapter 8. LOCA analyses and associated safety demonstration
8.1 Large break LOCA
8.1.1 Course of events
8.1.1.1 Blowdown
8.1.1.2 Refill
8.1.1.3 Reflood
8.2 Intermediate and small break LOCA
8.2.1 Course of events
8.2.2 Prevailing parameters
8.2.2.1 Break position
8.2.2.2 Break size
8.2.3 Plant design
8.2.3.1 Safety injection flow rate
8.2.3.2 Pump trip
8.2.4 Importance of the SB/IB-LOCA analyses on the reactor design and operation
8.3 Steam generator tube rupture
Chapter 9. Computational fluid dynamics applications and other transients
9.1 General approach for computational fluid dynamics (CFD)
9.1.1 Domain mesh
9.1.2 Closure models
9.1.3 Numerical solution and convergence
9.1.4 Verification and validation
9.2 Typical CFD studies for LWR and SMR applications
9.3 Pressurized thermal shock
9.4 Boron dilution
Chapter 10. Specificities of PWR-SMRs
10.1 Reactor coolant system in SMRs
10.2 LOCA
10.2.1 LOCA in SMRs
10.2.2 Specificity of the reactor core power
10.2.3 Specific features of the design of the main volume
10.2.4 Active or passive mode for a LOCA strategy
10.2.5 Typical LOCA transient scenario for an integral SMR
10.2.6 Passive residual heat removal strategy
10.3 Steam generator tube rupture
Chapter 11. Conclusion
Chapter 12. Applications
12.1 Identification of parameters
12.2 Hydraulics
12.2.1 Average velocities
12.2.2 Reynolds number in a fuel assembly
12.2.3 Abrupt change of geometry
12.2.4 Flow rate out of a reservoir
12.3 Thermodynamics
12.3.1 Evaluation of energy
12.3.2 Equilibrium thermodynamic quality in a pipe
12.3.3 Equilibrium thermodynamic quality in a steam generator
12.3.4 Water needs for electricity production
12.4 Two-phase flows
12.4.1 Evaluation of void fraction
12.4.2 Evaluation of flow parameters
12.4.3 Comparison of void fraction models
12.4.4 Application of drift flux model
12.5 Natural circulation
12.5.1 Flow rate in an SMR
12.6 Loss of coolant
12.6.1 Decay heat
12.6.2 Simplified small beak LOCA in an SMR
Chapter 13. Glossary
13.1 Some definitions
13.1.1 Best estimate
13.1.2 Bulk
13.1.3 Collapsed level
13.1.4 Conservatism
13.1.5 Enthalpy balance or heat balance
13.1.6 Entry length (entrance length)
13.1.7 Feed and Bleed
13.1.8 Figure of merit
13.1.9 Mechanistic model
13.1.10 Parameter of interest
13.1.11 Swell level
13.1.12 Ultimate heat sink
13.2 Acronyms and abbreviations
Chapter 14. Units and symbols
14.1 Notation : Latin letters
14.2 Notation : Subscripts and superscripts
14.3 Notation : Greek letters
14.4 Dimensionless numbers
Chapter 15. Steam tables
15.1 Saturated values at fixed pressures
15.1.1 Liquid values
15.1.2 Vapor values
15.2 Saturated values at fixed temperatures
15.2.1 Liquid values
15.2.2 Vapor values
Index

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Thermal-Hydraulic Principles and Safety Analysis Guidelines of PWRs and iPWR-SMRs

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