This book covers the processes of energy (heat) generation in nuclear processes, the transport of that energy by the reactor coolant to the power cycle, and the limitations imposed by the transport mechanism on the design of nuclear reactor cores. Homework problems are presented at the end of each chapter.

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.

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.

Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. - Presents the latest information on one of the deliverables of the SESAME H2020 project - Provides an overview on the design and history of liquid metal cooled fast reactors worldwide - Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors - Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly - Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications

Advances in Heat Transfer is designed to fill the information gap between regularly scheduled journals and university level textbooks by providing in-depth review articles over a broader scope than is allowablein either journals or texts. Volume 29 is a special volume devoted to nuclear reactor safety.

This project by the Thermal Hydraulics Research Laboratory at U.C. Berkeley Studied advanced high-temperature heat transport and power conversion technology, in support of the Nuclear Hydrogen Initiative and Generation IV.

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.

Offers a comprehensive treatment of heat transfer. In addition to the standard topics usually covered, it also includes a number of modern state-of-the-art topics including: radiative properties of particles, generation of P-N approximation and collimated irradiation.

The ultimate heat sink and its directly associated heat transport systems addressed in this guide are required to remove residual heat from the core after reactor shutdown, and during and after appropriate operational states and accident conditions.