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Book The Design of Gas cooled Graphite moderated Reactors  Edited by D  R  Poulter   With Plates

Download or read book The Design of Gas cooled Graphite moderated Reactors Edited by D R Poulter With Plates written by Dennis Ross POULTER and published by . This book was released on 1963 with total page 692 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Design of Gas cooled Graphite moderated Reactors

Download or read book The Design of Gas cooled Graphite moderated Reactors written by D. R. Poulter and published by . This book was released on 1963 with total page 724 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Fission Reactors

Download or read book Nuclear Fission Reactors written by I. R. Cameron and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 389 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book High Temperature Gas cooled Reactors

Download or read book High Temperature Gas cooled Reactors written by Tetsuaki Takeda and published by Academic Press. This book was released on 2021-02-24 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Technical Aspects of the Report on the Gas cooled  Graphite moderated Reactor

Download or read book Technical Aspects of the Report on the Gas cooled Graphite moderated Reactor written by United States. Congress. Joint Committee on Atomic Energy and published by . This book was released on 1958 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Design Study for a Graphite moderated Gas cooled Reactor Using Partially Enriched Uranium

Download or read book Design Study for a Graphite moderated Gas cooled Reactor Using Partially Enriched Uranium written by and published by . This book was released on 1958 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Prepared for the Second U.N. International Conference on the Peaceful Uses of Atomic Energy, 1958. A summary is presented of the research and development aspects of the U.S. program for graphite-moderated, gas-cooled reactors using partially enriched uranium. The availability of helium and enriched uranium in the United States presents a large degree of design freedom. On the basis of the study, it is concluded that such a reactor will produce power cheaper than a reactor using natural uranium. At the present time gas-cooled reactors are technologically and economically competitive with the best available pressurized-water reactors. (J.S.R.).

Book Gas Cooled Reactor Design and Safety

Download or read book Gas Cooled Reactor Design and Safety written by International Atomic Energy Agency and published by . This book was released on 1990 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present publication is an update of IAEA Technical Reports Series No. 235, Status of and Prospects for Gas-Cooled Reactors, published in 1984. It is a compilation of information based on submissions from Member States and is considered current as of the beginning of 1989. It describes the status of gas cooled reactors with specific emphasis on the design and safety characteristics of the various concepts that are either incorporated in operating reactors or in reactors being designed and considered for future construction and operation.

Book Securing the Safe Performance of Graphite Reactor Cores

Download or read book Securing the Safe Performance of Graphite Reactor Cores written by Gareth B Neighbour and published by Royal Society of Chemistry. This book was released on 2010-06-11 with total page 273 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear power currently contributes some 20% of the electricity needs of the UK and is rising rapidly on the political agenda due to environmental and economic factors, and yet all but one of the UK's existing nuclear reactors is expected to close by 2023. The increasing emphasis towards nuclear power rests on security of supply and reducing carbon emissions. This comprehensive book provides an account of the recent advances in securing safe performance of graphite-moderated nuclear reactors both within the UK and abroad which underpin life extension whilst maintaining high levels of plant performance. These reactors rely on graphite as a moderator in the form of layers of interlocked graphite bricks which undergo complex changes when exposed over long periods to the effects of neutron irradiation and radiolytic oxidation. The objective of this book is to outline the current approaches in terms of assessment methodologies, surveillance and test methods, performance prediction, graphite reactor decommissioning, regulatory requirements and the relevance to future reactor designs. The book is a sequel to the successful RSC publication "Managing of Ageing Processes in Graphite Reactor Cores", but with the emphasis on the challenges for the future safe performance. It is hoped that the contributed papers will also help in the design, construction, operation and eventual decommissioning of the new generation of graphite-moderated reactors. Papers presented in the book represent contributions from the most eminent specialists in the field and reflect the UK's contribution over the past 50 years to graphite reactor technology that will remain significant for years to come, especially in the development of Generation IV designs. This seminal book is written in a way that takes the reader from fundamental knowledge to reactor operation in a straight forward and understandable manner - ideal for non-specialist as well as a unique reference for the specialist. It is fully illustrated to aid understanding and is relevant to a wide range of readers from policy makers to reactor operators.

Book Civilian Power Reactor Program

Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Management of Ageing in Graphite Reactor Cores

Download or read book Management of Ageing in Graphite Reactor Cores written by Gareth B. Neighbour and published by Royal Society of Chemistry. This book was released on 2007 with total page 313 pages. Available in PDF, EPUB and Kindle. Book excerpt: This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity. This product is not available separately, it is only sold as part of a set. There are 750 products in the set and these are all sold as one entity.

Book Modelling and Measuring Reactor Core Graphite Properties and Performance

Download or read book Modelling and Measuring Reactor Core Graphite Properties and Performance written by Gareth B. Neighbour and published by Royal Society of Chemistry. This book was released on 2012 with total page 227 pages. Available in PDF, EPUB and Kindle. Book excerpt: Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during service posing a threat to the functionality of the core, and potentially, the safe operation of the reactor. Thus, the importance of modelling and measuring reactor core graphite properties and performance increases especially as continued use beyond the designed life time becomes significant. This book captures the proceedings from the third in a series of meetings addressing the extensive research and analysis performed to ensure the continuing safe performance of the graphite cores. Covering four broad themes: mechanistic; statistical; empirical; and, plant performance, this book should appeal to a broad range of readers from engineers and reactor operators to policy makers.

Book TID

Download or read book TID written by and published by . This book was released on 1960 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Power Reactor Designs

Download or read book Nuclear Power Reactor Designs written by Jun Wang and published by Elsevier. This book was released on 2023-12-15 with total page 465 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Power Reactor Designs: From History to Advances analyzes nuclear designs throughout history and explains how each of those has helped to shape and inform the nuclear reactor designs of today and the future. Focused on the structure, systems and relevant components of each reactor design, this book provides the readers with answers to key questions to help them understand the benefits of each design. Each reactor design is introduced, their origin defined, and the relevant research presented before an analysis of its successes, what was learned, and how research and technology advanced as a result are presented. Students, researchers and early career engineers will gain a solid understanding of how nuclear designs have evolved, and how they will continue to develop in the future. Presents reactor designs through history to present day, focusing on key structures, systems and components Provides readers with quick answers about various design principles and rationales Includes new approaches such as the micro-reactor and small-modular reactors

Book The HGCR 1  a Design Study of a Nuclear Power Station Employing a High temperature Gas cooled Reactor with Graphite UO2 Fuel Elements

Download or read book The HGCR 1 a Design Study of a Nuclear Power Station Employing a High temperature Gas cooled Reactor with Graphite UO2 Fuel Elements written by and published by . This book was released on 1959 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt: The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO2 fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr. (auth).

Book Civilian Power Reactor Program

Download or read book Civilian Power Reactor Program written by U.S. Atomic Energy Commission and published by . This book was released on 1960 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Structural Materials for Generation IV Nuclear Reactors

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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