Nuclear Systems Volume II (2nd Ed.) Elements of Thermal Hydraulic Design
Auteurs : Todreas Neil E., Kazimi Mujid S., Massoud Mahmoud
This book provides advanced coverage of a wide variety of thermal fluid systems and technologies in nuclear power plants, including discussions of the latest reactor designs and their thermal/fluid technologies. Beyond the thermal hydraulic design and analysis of the core of a nuclear reactor, the book covers other components of nuclear power plants, such as the pressurizer, containment, and the entire primary coolant system.
Placing more emphasis on the appropriate models for small-scale resolution of the velocity and temperature fields through computational fluid mechanics, the book shows how this enhances the accuracy of predicted operating conditions in nuclear plants. It introduces considerations of the laws of scaling and uncertainty analysis, along with a wider coverage of the phenomena encountered during accidents.
FEATURES
- Discusses fundamental ideas for various modeling approaches for the macro- and microscale flow conditions in reactors
- Covers specific design considerations, such as natural convection and core reliability
- Enables readers to better understand the importance of safety considerations in thermal engineering and analysis of modern nuclear plants
- Features end-of-chapter problems
- Includes a solutions manual for adopting instructors
This book serves as a textbook for advanced undergraduate and graduate students taking courses in nuclear engineering and studying thermal/hydraulic systems in nuclear power plants.
1. Formulation of the Reactor Thermal Hydraulic Design Problem 2. Scaling of Two-Phase Flows in Complex Nuclear Reactor Systems 3. Single, Heated Channel Transient Analysis 4. Multiple Heated Channels Connected Only at Plena 5. Analysis of Interacting Channels by the Porous Media Approach 6. Analysis of Interacting Channels by the Subchannel Approach 7. Flow Loops 8. Steady State and Transient Analysis of Centrifugal Pumps 9. Thermal Analysis of Pressurizers 10. Thermal Analysis of Containments 11. Thermal Analysis of Steam Generators and Condensers 12. Fundamentals of Reactor Transient Simulation 13. Treatment of Uncertainties in Reactor Thermal Analysis
Date de parution : 12-2021
17.8x25.4 cm
Thèmes de Nuclear Systems Volume II :
Mots-clés :
Heat Transfer Coefficient; Mass Flow Rate; plant operation; Heated Channel; plant safety analysis; Large Break Locus; thermal hydraulic design; Hl; two phase flow; RCP; containment; Steam Generator; core design; Axial Mass Flux; uncertainty analysis; Energy Equations; Containment Sump; Decay Heat; Qt; Containment Spray System; Cold Leg; Safety Injection; Reynolds Transport Theorem; Momentum Equation; Mass Flux Profile; RCS Depressurization; Average Tube Length; Inlet Mass Flux; RCS Pressure; Condensation Heat Transfer Coefficient; Single Phase Laminar Flow