Thermal-Hydraulics of Water Cooled Nuclear Reactors
Coordonnateur : D'Auria Francesco
Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes.
The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis.
This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability.
- Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors
- Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis)
- Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes
- Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
. 1. Introduction
. 2. A Historical Perspective
. 3. The Definitions
. 4. Needs from NPP Technology - Design and Safety
Part II - Thermal-Hydraulics Connections: The Principles Of Thermodynamics & Nuclear Systems
. 5. The Balance Equations for Two-Phase Fluids
. 6. The Target Phenomena
Part III - Nuclear Thermal-Hydraulics Modeling
. 7. Heat Transfer and Modeling
. 8. Pressure Drops and Modeling
. 9. The Constitutive Equations
. 10. The Special Models
. 11. The (Structure of) System Thermal-Hydraulic (SYS TH) Code
. 12. The (Structure of) Computational Fluid-Dynamics (CFD) Code
Part IV - Applications Of Thermal Hydraulics In Nuclear Technology
. 13. The V&V and the Uncertainty in SYS TH Codes
. 14. The Best-Estimate Plus Uncertainty (Bepu) Approach
. 15. Selected Applications of Sys TH Codes to Design and Accident Analysis
. 16. The Thermal-Hydraulic Aspects of Key Nuclear Accidents
Date de parution : 05-2017
Ouvrage de 1178 p.
Disponible chez l'éditeur (délai d'approvisionnement : 14 jours).
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