This publication provides a comprehensive summary of the status of liquid coolant technology development for fast reactors with regard to basic data, main technological challenges and the various fast reactor concepts and designs that are being investigated, with a special emphasis on the choice of coolant. The chapters are divided as follows: (1) Introduction; (2) Short History of Nuclear Power Development; (3) Physical and Chemical Properties of Coolants (Sodium, Lead and Lead-Bismuth Alloy); (4) Comparison of Different Sodium and Lead Coolant Technologies; (5) Thermohydraulics of Reactor Core; (6) Coolant Radioactivity; (7) Liquid Metal Cooled Fast Reactor Technology Development; (8) Modular Lead-Bismuth Cooled Small Size Fast Reactors; (9) Liquid Lead Cooled Fast Reactors

The choice of the coolant is one of the main technical issues concerning fast reactors design, since it determines design approach as well as safety, technical and economic characteristics of the system. This publication provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors, with regard to basic data and main technological challenges. It starts with historical remarks on the nuclear power development, provides a complete survey of physical and chemical properties of liquid metals and discusses the coolant quality control and thermal-hydraulics studies for both sodium and lead alloys systems. Other chapters elaborate on radioactivity of coolants and describe past experiences as well as current projects. Finally, design objectives, main research and technology development challenges of innovative fast reactor concepts, currently under investigation in Russia, having sodium, lead-bismuth eutectic, and lead as coolant, as well as the status of the respective research and development activities are summarized.

Nuclear power (NP) can bring great benefits to humanity by generating energy without emitting carbon into the environment. To solve the problem of global climate change, the number of nuclear power plants (NPPs) in the world must be much larger than it currently is. However, due to accidents at NPPs, people are in disbelief of NP, which has led to the closure of NPPs in some countries and a slowdown in the development of NP across the world. This tendency can be overcome by creating NPPs with reactors with a high level of inherent self-protection, in which the causes of the most severe accidents are excluded by the laws of nature. These reactors include those with a lead-bismuth eutectic, in which there is no high pressure and no explosive hydrogen is formed. This book brings together articles and reports from Russian specialists devoted to such reactors. It will be of interest to both specialists working in nuclear power engineering and university students.

Science and Technology of Liquid Metal Coolants in Nuclear Engineering is a comprehensive consolidation of the latest research and knowledge on liquid metal coolants. Over the last decades, various new technologies have been developed for the liquid metal coolants of fast breeder and fusion reactors and accelerator driven systems. Details of pumps and instrumentation used in these coolants and their operating principles are included to provide the reader with a well-rounded understanding of the topic and to guide on the operation of different liquid metal coolant systems. Methods for the safe handling and control of impurity levels in these coolants are clearly discussed, along with alkali metal fires and their management, including methods for safe disposal of sodium waste. - Discusses the thermophysical and chemical properties of liquid metals described with their microscopic origin - Includes methods for the safe handling of liquid metal coolants and their purification and management - Discusses pumps and instrumentation principles and design

Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area

Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.