Download or read book A Preliminary Gas cooled Breeder Reactor Design Code written by Edward Bruce Parlette and published by . This book was released on 1980 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Download or read book CONUP written by and published by . This book was released on 1991 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Compendium of Computer Codes for the Safety Analysis of Fast Breeder Reactors written by United States. Department of Energy. Division of Reactor Research and Demonstration and published by . This book was released on 1977 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Reactors written by Chad L. Pope and published by BoD – Books on Demand. This book was released on 2022-09-14 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt: Worldwide interest in nuclear reactors continues to increase and significant focus has been placed on advanced nuclear reactors intended to produce electricity and process heat. However, there is limited literature on the importance of research reactors and certain specialized reactor analysis topics. Thus, this book addresses these topics over three sections: “Nuclear Reactors for Spacecraft Propulsion”, “Research Reactors”, and “Select Reactor Analysis Techniques”. It provides detailed information on the use of nuclear reactors for spacecraft propulsion, presents research conducted on reactors in Idaho, USA, and discusses reactor analysis topics such as cyber-informed engineering for nuclear reactor digital instrumentation and control, the effect of plenum gas on fuel temperature, and more.
Download or read book The Future of Nuclear Power written by John N Lillington and published by Elsevier. This book was released on 2004-10-27 with total page 414 pages. Available in PDF, EPUB and Kindle. Book excerpt: During the last century, nuclear power has been established as a reliable source of energy in the major industrialised countries. It has recently enjoyed a revival in attention and research due to the environmental concerns surrounding current conventional energy sources. Issues of regulation and safety are at the forefront of all discussions involving nuclear power, and will govern its place in the future. The Future of Nuclear Power takes a technical and comprehensive look at the current and future status of nuclear power throughout the world. The 17 chapters are divided into two main sections: a review of all current generation plants, and concepts for new advanced reactor design and safety. The broad-ranging topics covered by this publication, coupled with the current revival of interest in nuclear energy, make it a timely reference for all nuclear scientists. Reviews the issues surrounding the future operation of existing commercial nuclear plants Several chapters dedicated to the extensive research programs in place concerning safe and reliable operation Compares nuclear and non-nuclear options for energy needs in the future; evaluating the benefits and risks of both
Download or read book Army Gas cooled Reactor Systems Program written by G. A. Linenberger and published by . This book was released on 1960 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Technology written by and published by . This book was released on 1970 with total page 460 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Thermal hydraulic Code Selection for Modular High Temperature Gas cooled Reactors written by E. M. J. Komen and published by . This book was released on 1995 with total page 49 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor and Fuel processing Technology written by and published by . This book was released on 1967 with total page 650 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Download or read book Power Reactor Technology and Reactor Fuel Processing written by and published by . This book was released on 1962 with total page 506 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development of a Detailed Core Flow Analysis Code for Prismatic Fuel Reactors written by and published by . This book was released on 1990 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of a computer code for the analysis of the detailed flow of helium in prismatic fuel reactors is reported. The code, called BYPASS, solves, a finite difference control volume formulation of the compressible, steady state fluid flow in highly cross-connected flow paths typical of the Modular High-Temperature Gas Cooled Reactor (MHTGR). The discretization of the flow in a core region typically considers the main coolant flow paths, the bypass gap flow paths, and the crossflow connections between them. 16 refs., 5 figs.
Download or read book International Conference on the Physics of Reactors 2008 PHYSOR 2008 written by Rakesh Chawla and published by . This book was released on 2008 with total page 3389 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dismantling the Bomb and Managing the Nuclear Materials written by États-Unis. Congress. Office of Technology Assessment and published by DIANE Publishing. This book was released on 1993 with total page 202 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book CALIOP written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: CALIOP is a design code for fluid-cooled reactors composed of parallel fuel tubes in hexagonal or cylindrical ducts. It may be used with gaseous or liquid coolants. It has been used chiefly for design of a helium-cooled fast breeder reactor and has built-in cross section information to permit calculations of fuel loading, breeding ratio, and doubling time. Optional cross-section input allows the code to be used with moderated cores and with other fuels.
Download or read book High Temperature Gas Reactors written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Current interest expressed by industry in HTGR plants, particularly modular plants with power up to about 600 MW(e) per unit, has prompted NRC to task PNNL with assessing the currently available literature related to codes and standards applicable to HTGR plants, the operating history of past and present HTGR plants, and with evaluating the proposed designs of RPV and associated piping for future plants. Considering these topics in the order they are arranged in the text, first the operational histories of five shut-down and two currently operating HTGR plants are reviewed, leading the authors to conclude that while small, simple prototype HTGR plants operated reliably, some of the larger plants, particularly Fort St. Vrain, had poor availability. Safety and radiological performance of these plants has been considerably better than LWR plants. Petroleum processing plants provide some applicable experience with materials similar to those proposed for HTGR piping and vessels. At least one currently operating plant - HTR-10 - has performed and documented a leak before break analysis that appears to be applicable to proposed future US HTGR designs. Current codes and standards cover some HTGR materials, but not all materials are covered to the high temperatures envisioned for HTGR use. Codes and standards, particularly ASME Codes, are under development for proposed future US HTGR designs. A 'roadmap' document has been prepared for ASME Code development; a new subsection to section III of the ASME Code, ASME BPVC III-5, is scheduled to be published in October 2011. The question of terminology for the cross-duct structure between the RPV and power conversion vessel is discussed, considering the differences in regulatory requirements that apply depending on whether this structure is designated as a 'vessel' or as a 'pipe'. We conclude that designing this component as a 'pipe' is the more appropriate choice, but that the ASME BPVC allows the owner of the facility to select the preferred designation, and that either designation can be acceptable.
