Fluid Fuel Reactors


Book Description




Molten Salt Reactors and Thorium Energy


Book Description

Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe










Immiscible-liquid-cooled, Fluid-fuel Reactor


Book Description

A central station power fluid fuel reactor has been designed in which heat is removed by direct contact of the fuel with an immiscible coolant. Object of this design is to minimize fuel holdup outside the reactor core by utilizing the excellent heat transfer characteristics of direct contact cooling.




Structural Materials for Generation IV Nuclear Reactors


Book Description

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




FLUID FUEL REACTORS


Book Description

Landmark book written at Oak Ridge National Laboratory under the auspices of the Atomic Energy Commission as part of its Atoms for Peace program. FLUID FUEL REACTORS approaches to the subject of nuclear power from a chemical standpoint, rather than from the point of view of mechanical engineering. Today, the value of this approach has (finally) been recognized by venture capitalists such as Peter Thiel, philanthropists such as Bill Gates, and policy makers in Washington who have recently been passing advanced-reactor friendly legislation year after year. China's Navy is funding the Chinese Academy of Science Thorium Molten Salt Reactor program. The DoE (through GAIN) has funded essential Molten Salt research in the United States. Canada has funded Molten Salt research, and is currently conducting a pre-licensing vendor review. Dr. Anil Kokodkar, the former-head of India's nuclear program has stated, given a do-over he'd have pursued a liquid fuel (as opposed to a conventional solid fuel) approach to advanced nuclear. Molten Salt Reactor startups are flourishing, and typically, a single copy of FLUID FUEL REACTORS can be found in their head-office. The founders of these startups are driven to provide clean energy to developing nations, and replace today's polluting energy options which power western industry and prosperity. First printed in 1958, FLUID FUEL REACTORS continues to be cited as a useful reference by ORNL engineers, MSR startup employees, and those in academia. Alvin Weinberg suggested people should re-examine "dusty old books" such as FLUID FUEL REACTORS in his last recorded public interview (2 years before his death) at the University of Tennessee on 2004. Used physical copies have sold online for well over $1,000. 60 years after FLUID FUEL REACTORS was first published, it can now, for the first time, be enjoyed on digital reading devices, in a manner that supports adjustable font sizes and easy-to-read formatting... as opposed to looking at a series of bitmap images of words, like an animal.




High Temperature Gas-cooled Reactors


Book Description

High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant. The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection. This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.




Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors


Book Description

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




Fluid Fuel Reactors with Uranium-Bismuth


Book Description

Uranium bismuth solutions or dispersions of USn3 in liquid bismuth- lead-tin are proposed as fluid fuels for a power breeder or converter. These fuels offer advantages of high specific power, unlimited burn up, good neutron economy, and low over all operating costs which might lead to truly economical nuclear power. A simple and effective chemical process based on the extraction of liquid metal with fused salts will remove fission products in a concentrated form for use or storage. A process for the continuous separation of U233 from thorium in the blanket is described. Several design possibilities are discussed.