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Facility Configuration Study Of The High Temperature Gas Cooled Reactor Component Test Facility
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Book Synopsis Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility by :
Download or read book Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: Identifies pre-conceptual design requirements Develops test loop equipment schematics and layout Identifies space allocations for each of the facility functions, as required Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems Identifies pre-conceptual utility and support system needs Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.
Book Synopsis High Temperature Gas-cooled Reactors by : Tetsuaki Takeda
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 Synopsis THE COMPONENT TEST FACILITY - A NATIONAL USER FACILITY FOR TESTING OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR) COMPONENTS AND SYSTEMS. by :
Download or read book THE COMPONENT TEST FACILITY - A NATIONAL USER FACILITY FOR TESTING OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR) COMPONENTS AND SYSTEMS. written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Next Generation Nuclear Plant (NGNP) and other High-Temperature Gas-cooled Reactor (HTGR) Projects require research, development, design, construction, and operation of a nuclear plant intended for both high-efficiency electricity production and high-temperature industrial applications, including hydrogen production. During the life cycle stages of an HTGR, plant systems, structures and components (SSCs) will be developed to support this reactor technology. To mitigate technical, schedule, and project risk associated with development of these SSCs, a large-scale test facility is required to support design verification and qualification prior to operational implementation. As a full-scale helium test facility, the Component Test facility (CTF) will provide prototype testing and qualification of heat transfer system components (e.g., Intermediate Heat Exchanger, valves, hot gas ducts), reactor internals, and hydrogen generation processing. It will perform confirmation tests for large-scale effects, validate component performance requirements, perform transient effects tests, and provide production demonstration of hydrogen and other high-temperature applications. Sponsored wholly or in part by the U.S. Department of Energy, the CTF will support NGNP and will also act as a National User Facility to support worldwide development of High-Temperature Gas-cooled Reactor technologies.
Book Synopsis Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor by :
Download or read book Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Oregon State University (OSU) High Temperature Test Facility (HTTF) is an integral experimental facility that will be constructed on the OSU campus in Corvallis, Oregon. The HTTF project was initiated, by the U.S. Nuclear Regulatory Commission (NRC), on September 5, 2008 as Task 4 of the 5-year High Temperature Gas Reactor Cooperative Agreement via NRC Contract 04-08-138. Until August, 2010, when a DOE contract was initiated to fund additional capabilities for the HTTF project, all of the funding support for the HTTF was provided by the NRC via their cooperative agreement. The U.S. Department of Energy (DOE) began their involvement with the HTTF project in late 2009 via the Next Generation Nuclear Plant (NGNP) project. Because the NRC's interests in HTTF experiments were only centered on the depressurized conduction cooldown (DCC) scenario, NGNP involvement focused on expanding the experimental envelope of the HTTF to include steady-state operations and also the pressurized conduction cooldown (PCC).
Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
Book Synopsis IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY. by :
Download or read book IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY. written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Paper presented at American Nuclear Society Meeting, June I8-21, 1962, Boston, Mass. Design and operating problems of unclad and ceramic gas-cooled reactor fuels in high temperature circulating gas systems will be studied using a test facility now nearing completion at the Oak Ridge Research Reactor. A shielded air-tight cell houses a closed circuit gas system equipped for dealing with fission products circulating in the gas. Experiments can be conducted on fuel element performance and stability, fission product deposition, gas clean up, activity levels, component and system performance and shielding, and decontamination and maintenance of system hardware. (auth).
Author :General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science Publisher : ISBN 13 : Total Pages :246 pages Book Rating :4.3/5 (243 download)
Book Synopsis Design Study Report for TARGET by : General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science
Download or read book Design Study Report for TARGET written by General Dynamics Corporation. General Atomic Division. John Jay Hopkins Laboratory for Pure and Applied Science and published by . This book was released on 1964 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Gas-cooled Reactors written by and published by . This book was released on 1959 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Preliminary Study of a Fast Reactor Core Test Facility by : D. B. Hall
Download or read book A Preliminary Study of a Fast Reactor Core Test Facility written by D. B. Hall and published by . This book was released on 1959 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scaling Analysis of the OSU High Temperature Test Facility During a Pressurized Conduction Cooldown Event Using RELAP5-3D by : Juan A. Castañeda
Download or read book Scaling Analysis of the OSU High Temperature Test Facility During a Pressurized Conduction Cooldown Event Using RELAP5-3D written by Juan A. Castañeda and published by . This book was released on 2014 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt: In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear Plant (NGNP) would be the VHTR. The VHTR was chosen because it has the capability to produce electricity, hydrogen and may be used for other high-temperature process heat applications. In support of licensing and validation of the VHTR, Oregon State University was tasked to develop a high temperature apparatus that will be able to capture the thermal fluids phenomena of the VHTR and perform integral effects tests for validation of existing safety codes. The design has been called the High Temperature Test Facility (HTTF), which is a scaled design of the Modular High Temperature Gas-Cooled Reactor (MHTGR). The objective of this study was to investigate the ability of the HTTF to simulate the Pressurized Conduction Cooldown (PCC) Event during the natural circulation phase in the MHTGR. This was achieved with the aid of a thermal hydraulic systems code, RELAP5-3D.
Book Synopsis Thermal Hydraulic Analysis of a Reduced Scale High Temperature Gas-Cooled Reactor Test Facility and Its Prototype with MELCOR by : Bradley Aaron Beeny
Download or read book Thermal Hydraulic Analysis of a Reduced Scale High Temperature Gas-Cooled Reactor Test Facility and Its Prototype with MELCOR written by Bradley Aaron Beeny and published by . This book was released on 2013 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pursuant to the energy policy act of 2005, the High Temperature Gas-Cooled Reactor (HTGR) has been selected as the Very High Temperature Reactor (VHTR) that will become the Next Generation Nuclear Plant (NGNP). Although plans to build a demonstration plant at Idaho National Laboratories (INL) are currently on hold, a cooperative agreement on HTGR research between the U.S. Nuclear Regulatory Commission (NRC) and several academic investigators remains in place. One component of this agreement relates to validation of systems-level computer code modeling capabilities in anticipation of the eventual need to perform HTGR licensing analyses. Because the NRC has used MELCOR for LWR licensing in the past and because MELCOR was recently updated to include gas-cooled reactor physics models, MELCOR is among the system codes of interest in the cooperative agreement. The impetus for this thesis was a code-to-experiment validation study wherein MELCOR computer code predictions were to be benchmarked against experimental data from a reduced-scale HTGR testing apparatus called the High Temperature Test Facility (HTTF). For various reasons, HTTF data is not yet available from facility designers at Oregon State University, and hence the scope of this thesis was narrowed to include only computational studies of the HTTF and its prototype, General Atomics' Modular High Temperature Gas-Cooled Reactor (MHTGR). Using the most complete literature references available for MHTGR design and using preliminary design information on the HTTF, MELCOR input decks for both systems were developed. Normal and off-normal system operating conditions were modeled via implementation of appropriate boundary and inititial conditions. MELCOR Predictions of system response for steady-state, pressurized conduction cool-down (PCC), and depressurized conduction cool-down (DCC) conditions were checked against nominal design parameters, physical intuition, and some computational results available from previous RELAP5-3D analyses at INL. All MELCOR input decks were successfully built and all scenarios were successfully modeled under certain assumptions. Given that the HTTF input deck is preliminary and was based on dated references, the results were altogether imperfect but encouraging since no indications of as yet unknown deficiencies in MELCOR modeling capability were observed. Researchers at TAMU are in a good position to revise the MELCOR models upon receipt of new information and to move forward with MELCOR-to-HTTF benchmarking when and if test data becomes available. The electronic version of this dissertation is accessible from http://hdl.handle.net/1969.1/148182
Book Synopsis An Evaluation of High-temperature Gas-cooled Reactors by : Oak Ridge National Laboratory
Download or read book An Evaluation of High-temperature Gas-cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design of Gas-cooled Test Loop for NASA PLUM Brook Reactor Facility by :
Download or read book Design of Gas-cooled Test Loop for NASA PLUM Brook Reactor Facility written by and published by . This book was released on 1967 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-02 with total page 722 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Progress Report written by E. R. Astley and published by . This book was released on 1965 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993-10 with total page 578 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation Publisher : ISBN 13 : Total Pages :574 pages Book Rating :4.F/5 ( download)
Book Synopsis AEC Authorizing Legislation, Fiscal Year 1965 by : United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation
Download or read book AEC Authorizing Legislation, Fiscal Year 1965 written by United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation and published by . This book was released on 1964 with total page 574 pages. Available in PDF, EPUB and Kindle. Book excerpt:
