Thermal-Hydraulic Analysis of Nuclear Reactors

Thermal-Hydraulic Analysis of Nuclear Reactors
Author: Bahman Zohuri
Publisher: Springer
Total Pages: 845
Release: 2017-05-23
Genre: Technology & Engineering
ISBN: 3319538292

This revised text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. The book begins with fundamental definitions of units and dimensions, thermodynamic variables and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors.

Thermodynamics In Nuclear Power Plant Systems

Thermodynamics In Nuclear Power Plant Systems
Author: Bahman Zohuri
Publisher: Springer
Total Pages: 735
Release: 2015-04-20
Genre: Technology & Engineering
ISBN: 3319134191

This book covers the fundamentals of thermodynamics required to understand electrical power generation systems, honing in on the application of these principles to nuclear reactor power systems. It includes all the necessary information regarding the fundamental laws to gain a complete understanding and apply them specifically to the challenges of operating nuclear plants. Beginning with definitions of thermodynamic variables such as temperature, pressure and specific volume, the book then explains the laws in detail, focusing on pivotal concepts such as enthalpy and entropy, irreversibility, availability, and Maxwell relations. Specific applications of the fundamentals to Brayton and Rankine cycles for power generation are considered in-depth, in support of the book’s core goal- providing an examination of how the thermodynamic principles are applied to the design, operation and safety analysis of current and projected reactor systems. Detailed appendices cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties, and nuclear reactor system descriptions.

Heat Transfer and Fluid Flow in Nuclear Systems

Heat Transfer and Fluid Flow in Nuclear Systems
Author: Henri Fenech
Publisher: Elsevier
Total Pages: 591
Release: 2013-10-22
Genre: Science
ISBN: 148315078X

Heat Transfer and Fluid in Flow Nuclear Systems discusses topics that bridge the gap between the fundamental principles and the designed practices. The book is comprised of six chapters that cover analysis of the predicting thermal-hydraulics performance of large nuclear reactors and associated heat-exchangers or steam generators of various nuclear systems. Chapter 1 tackles the general considerations on thermal design and performance requirements of nuclear reactor cores. The second chapter deals with pressurized subcooled light water systems, and the third chapter covers boiling water reactor systems. Chapter 4 tackles liquid metal cooled systems, while Chapter 5 discusses helium cooled systems. The last chapter deals with heat-exchangers and steam generators. The book will be of great help to engineers, scientists, and graduate students concerned with thermal and hydraulic problems.

Nuclear Thermal Hydraulic and Two-Phase Flow

Nuclear Thermal Hydraulic and Two-Phase Flow
Author: Jun Wang
Publisher: Frontiers Media SA
Total Pages: 120
Release: 2018-10-11
Genre:
ISBN: 2889456129

Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.

Nuclear Reactor Thermal Hydraulics

Nuclear Reactor Thermal Hydraulics
Author: Robert E. Masterson
Publisher: CRC Press
Total Pages: 2352
Release: 2019-08-21
Genre: Science
ISBN: 1351849514

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.

Nuclear Thermal Hydraulics

Nuclear Thermal Hydraulics
Author: Hajime Akimoto
Publisher: Springer
Total Pages: 464
Release: 2016-11-10
Genre: Technology & Engineering
ISBN: 4431556036

This volume provides fundamentals of nuclear thermal–hydraulics for reactor design and safety assessment. It also describes the basis for assessing cooling performance of nuclear reactors under accidental conditions. The descriptions in this book are virtually self-contained, beyond the assumption that readers are familiar with the introductory levels of nuclear engineering. This book helps readers understand the processes for nuclear reactor plant design and the most important factors in nuclear thermal-hydraulics.

Nuclear Reactor Thermal Hydraulics

Nuclear Reactor Thermal Hydraulics
Author: Robert Masterson
Publisher:
Total Pages: 1354
Release: 2019
Genre: Nuclear reactors
ISBN: 9781138035379

The nuclear power industry in the world today -- The pressurized water reactor -- The boiling water reactor -- Fast reactors, gas reactors, and military reactors -- Thermal energy production in nuclear power plants -- The laws of thermodynamics -- Thermodynamic properties and equations of state -- The nuclear steam supply system -- Reactor thermal cycles -- The laws of heat transfer -- Heat removal from nuclear fuel rods -- Time dependent nuclear heat transfer -- Nuclear reactor fluid mechanics -- Fluid statics and fluid dynamics -- The conservation equations of fluid mechanics -- Single phase flow in nuclear power plants -- Laminar and turbulent flow with friction -- Core and fuel assembly fluid flow -- Reactor coolants, coolant pumps, and power turbines -- Single phase nuclear heat transfer -- Correlations for single phase nuclear heat transfer -- Natural convection in nuclear power plants -- Fundamentals of two phase flow in nuclear power plants -- Two phase nuclear heat transfer -- Heat transfer correlations for advanced two phase nuclear heat transfer -- Core temperature fields -- Nuclear hot channel factors, the critical heat flux, and the dnbr -- Thermal design limits, operating limits, and safety limits -- Equilibrium and non-equilibrium flows, critical flow, and choke flow -- Reactor accidents, dbas, and locas -- Flow oscillations, density waves, and hydrodynamic instabilities -- Containment buildings and their function -- particle transport and entrainment during reactor accidents -- Response of a containment building to a reactor LOCA.