The Nuclear Fuel Of Pressurized Water Reactors And Fast Neutron Reactors

This text discusses the design, manufacture and behaviour of nuclear fuel in pressurized water reactors (PWR) and fast reactors (FR). It reflects the knowledge of the French Agency for Nuclear Power (CEA) and other specialized companies in the field.

Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.

This book is intended to provide an introduction to the basic principles of nuclear fission reactors for advanced undergraduate or graduate students of physics and engineering. The presentation is also suitable for physicists or engineers who are entering the nuclear power field without previous experience with nuclear reactors. No background knowledge is required beyond that typically acquired in the first two years of an undergraduate program in physics or engineering. Throughout, the emphasis is on explaining why particular reactor systems have evolved in the way they have, without going into great detail about reactor physics or methods of design analysis, which are already covered in a number of excellent specialist texts. The first two chapters serve as an introduction to the basic physics of the atom and the nucleus and to nuclear fission and the nuclear chain reaction. Chapter 3 deals with the fundamentals of nuclear reactor theory, covering neutron slowing down and the spatial dependence of the neutron flux in the reactor, based on the solution of the diffusion equations. The chapter includes a major section on reactor kinetics and control, including'tempera ture and void coefficients and xenon poisoning effects in power reactors. Chapter 4 describes various aspects offuel management and fuel cycles, while Chapter 5 considers materials problems for fuel and other constituents of the reactor. The processes of heat generation and removal are covered in Chapter 6.

Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations. Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions. Cover image: Kaiga Atomic Power Station Units 1 - 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India. Includes methods for solving neutron transport problems, nuclear cross-section data and solutions of transport theory Dedicates a chapter to reactor safety that covers mitigation, probabilistic safety assessment and uncertainty analysis Covers experimental and operational physics with details on noise analysis and failed fuel detection

What Is Generation IV Reactor The Generation IV International Forum is doing research on the commercial viability of a number of different nuclear reactor designs that fall under the umbrella term "generation IV reactors."They are driven by many different purposes, some of which include increased safety, enhanced sustainability, increased efficiency, and reduced costs. How You Will Benefit (I) Insights, and validations about the following topics: Chapter 1: Generation IV reactor Chapter 2: Nuclear reactor Chapter 3: Breeder reactor Chapter 4: Fast-neutron reactor Chapter 5: Integral fast reactor Chapter 6: Molten salt reactor Chapter 7: Nuclear fuel Chapter 8: Supercritical water reactor Chapter 9: High-temperature gas reactor Chapter 10: Lead-cooled fast reactor Chapter 11: Sodium-cooled fast reactor Chapter 12: Thorium fuel cycle Chapter 13: Liquid metal cooled reactor Chapter 14: Online refuelling Chapter 15: Liquid fluoride thorium reactor Chapter 16: Traveling wave reactor Chapter 17: List of small modular reactor designs Chapter 18: TerraPower Chapter 19: BN-1200 reactor Chapter 20: Integral Molten Salt Reactor Chapter 21: BREST (reactor) (II) Answering the public top questions about generation iv reactor. (III) Real world examples for the usage of generation iv reactor in many fields. (IV) 17 appendices to explain, briefly, 266 emerging technologies in each industry to have 360-degree full understanding of generation iv reactor' technologies. Who This Book Is For Professionals, undergraduate and graduate students, enthusiasts, hobbyists, and those who want to go beyond basic knowledge or information for any kind of generation iv reactor.

Provides a detailed introduction to nuclear reactors, describing the four commercial types and discussing uranium resources, fuel cycles, advanced reactor systems, and issues and problems concerning the use of nuclear power