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Design Of A Gas Test Loop Facility For The Advanced Test Reactor
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Book Synopsis Design of a Gas Test Loop Facility for the Advanced Test Reactor by : C. A. Wemple
Download or read book Design of a Gas Test Loop Facility for the Advanced Test Reactor written by C. A. Wemple and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Office of Nuclear Energy within the U.S. Department of Energy (DOE-NE) has identified the need for irradiation testing of nuclear fuels and materials, primarily in support of the Generation IV (Gen-IV) and Advanced Fuel Cycle Initiative (AFCI) programs. These fuel development programs require a unique environment to test and qualify potential reactor fuel forms. This environment should combine a high fast neutron flux with a hard neutron spectrum and high irradiation temperature. An effort is presently underway at the Idaho National Laboratory (INL) to modify a large flux trap in the Advanced Test Reactor (ATR) to accommodate such a test facility [1,2]. The Gas Test Loop (GTL) Project Conceptual Design was initiated to determine basic feasibility of designing, constructing, and installing in a host irradiation facility, an experimental vehicle that can replicate with reasonable fidelity the fast-flux test environment needed for fuels and materials irradiation testing for advanced reactor concepts. Such a capability will be needed if programs such as the AFCI, Gen-IV, the Next Generation Nuclear Plant (NGNP), and space nuclear propulsion are to meet development objectives and schedules. These programs are beginning some irradiations now, but many call for fast flux testing within this decade.
Book Synopsis Designing a Gas Test Loop for the Advanced Test Reactor by : James R. Parry
Download or read book Designing a Gas Test Loop for the Advanced Test Reactor written by James R. Parry and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Reactor Program and the Advanced Fuel Cycle Initiative are investigating some new reactor concepts which require extensive materials and fuels testing in a fast neutron spectrum. The capability to test materials and fuels in a fast neutron flux in the United States is very limited to non-existent. It has been proposed to install a gas test loop (GTL) in one of the lobes of the Advanced Test Reactor (ATR) at the Idaho National Laboratory and harden the spectrum to provide some fast neutron flux testing capabilities in the United States. This paper describes the neutronics investigation into the design of the GTL for the ATR.
Book Synopsis Testing of Gas Reactor Materials and Fuel in the Advanced Test Reactor by : Blaine S. Grover
Download or read book Testing of Gas Reactor Materials and Fuel in the Advanced Test Reactor written by Blaine S. Grover and published by . This book was released on 2004 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: "The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has developed facilities well suited for providing the right conditions and environment for gas reactor tests. This paper discusses the different types of irradiation hardware that have been utilized in past ATR irradiation tests of gas reactor materials. The new Gas Test Loop facility currently being developed for the ATR is discussed and the different approaches being considered in the design of the facility. The different options for an irradiation experiment such as active versus passive temperature control, neutron spectrum tailoring, and different types of lead experiment sweep gas monitors are also discussed. The paper is then concluded with examples of different past and present gas reactor material and fuel irradiations" -- Page [1].
Book Synopsis TESTING OF GAS REACTOR MATERIALS AND FUEL IN THE ADVANCED TEST REACTOR. by : S. B. Grover
Download or read book TESTING OF GAS REACTOR MATERIALS AND FUEL IN THE ADVANCED TEST REACTOR. written by S. B. Grover and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has developed facilities well suited for providing the right conditions and environment for gas reactor tests. This paper discusses the different types of irradiation hardware that have been utilized in past ATR irradiation tests of gas reactor materials. The new Gas Test Loop facility currently being developed for the ATR is discussed and the different approaches being considered in the design of the facility. The different options for an irradiation experiment such as active versus passive temperature control, neutron spectrum tailoring, and different types of lead experiment sweep gas monitors are also discussed. The paper is then concluded with examples of different past and present gas reactor material and fuel irradiations.
Book Synopsis Testing of Gas Reactor Materials and Fuel in the Advanced Test Reactor by :
Download or read book Testing of Gas Reactor Materials and Fuel in the Advanced Test Reactor written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has developed facilities well suited for providing the right conditions and environment for gas reactor tests. This paper discusses the different types of irradiation hardware that have been utilized in past ATR irradiation tests of gas reactor materials. The new Gas Test Loop facility currently being developed for the ATR is discussed and the different approaches being considered in the design of the facility. The different options for an irradiation experiment such as active versus passive temperature control, neutron spectrum tailoring, and different types of lead experiment sweep gas monitors are also discussed. The paper is then concluded with examples of different past and present gas reactor material and fuel irradiations.
Book Synopsis Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor by : Babcock & Wilcox Company
Download or read book Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor written by Babcock & Wilcox Company and published by . This book was released on 1962 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Gas Test Loop Facilities Alternatives Assessment Report Rev 1 by : William J. Skerjanc
Download or read book Gas Test Loop Facilities Alternatives Assessment Report Rev 1 written by William J. Skerjanc and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An important task in the Gas Test Loop (GTL) conceptual design was to determine the best facility to serve as host for this apparatus, which will allow fast-flux neutron testing in an existing nuclear facility. A survey was undertaken of domestic and foreign nuclear reactors and accelerator facilities to arrive at that determination. Two major research reactors in the U.S. were considered in detail, the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), each with sufficient power to attain the required neutron fluxes. HFIR routinely operates near its design power limit of 100 MW. ATR has traditionally operated at less than half its design power limit of 250 MW. Both of these reactors should be available for at least the next 30 years. The other major U.S. research reactor, the Missouri University Research Reactor, does not have sufficient power to reach the required neutron flux nor do the smaller research reactors. Of the foreign reactors investigated, BOR-60 is perhaps the most attractive. Monju and BN 600 are power reactors for their respective electrical grids. Although the Joyo reactor is vigorously campaigning for customers, local laws regarding transport of radioactive material mean it would be very difficult to retrieve test articles from either Japanese reactor for post irradiation examination. PHENIX is scheduled to close in 2008 and is fully booked until then. FBTR is limited to domestic (Indian) users only. Data quality is often suspect in Russia. The only accelerator seriously considered was the Fuel and Material Test Station (FMTS) currently proposed for operation at Los Alamos National Laboratory. The neutron spectrum in FMTS is similar to that found in a fast reactor, but it has a pronounced high-energy tail that is atypical of fast fission reactor spectra. First irradiation in the FMTS is being contemplated for 2008. Detailed review of these facilities resulted in the recommendation that the ATR would be the best host for the GTL.
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:
Book Synopsis Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility by :
Download or read book Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) conditions to support clad corrosion and related reactor material testing. Further it will accommodate power ramping tests of candidate high burn-up fuels and fuel pins/rods for the commercial BWR utilities. The BWTL will be much like the pressurized water loops already in service in 5 of the 9 "flux traps" (region of enhanced neutron flux) in the ATR. The loop coolant will be isolated from the primary coolant system so that the loop's temperature, pressure, flow rate, and water chemistry can be independently controlled. This paper presents the proposed general design of the in-core and auxiliary BWTL systems; the preliminary results of the neutronics and thermal hydraulics analyses; and the preliminary hazard analysis for safe normal and transient BWTL and ATR operation.
Book Synopsis Assessment of Available Fast Neutron Irradiation Facilities and the Validation of PLATE 2.0 to Support the Conceptual Design of a Gas Test Loop in the Advanced Test Reactor by : William Frances Skerjanc
Download or read book Assessment of Available Fast Neutron Irradiation Facilities and the Validation of PLATE 2.0 to Support the Conceptual Design of a Gas Test Loop in the Advanced Test Reactor written by William Frances Skerjanc and published by . This book was released on 2005 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: Current research and development programs being conducted in the United States for advanced fuels and materials to support the Advanced Fuel Cycle Initiative (AFCI), Generation-IV reactors (GEN-IV), and space nuclear programs require an irradiation testing facility capable of simulating anticipated operating environments. The lack of domestic irradiation facilities to meet these programmatic goals has led to a proposed Gas Test Loop (GTL) for fuel and material irradiation to be installed in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The GTL will utilize highly enriched U2́3Si2́2 fuel plates to increase the fast neutron flux density to simulate actual fast reactor conditions. The INL has chosen the computer code PLATE 2.0 (Plate Lifetime Accurate Thermal Evaluation, version 2.0) to model the steady-state thermal properties of the fuel plates. The INL requires all new computer software used in modeling applications to undergo qualification before it can be used for safety analysis. The qualification plan specified by the INL requires a user's manual be developed for PLATE 2.0 along with verification and validation (V & V) of the output results against benchmark data. This thesis presents a study of foreign and domestic fast neutron irradiation facilities, a description of PLATE 2.0 and its user's manual, and the results from the V & V of PLATE 2.0 for U2́3Si2́2 fuel plates.
Book Synopsis Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor by : Babcock & Wilcox Company
Download or read book Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor written by Babcock & Wilcox Company and published by . This book was released on 1963 with total page 194 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design of the Advanced Gas Reactor Fuel Experiments for Irradiation in the Advanced Test Reactor by : S. Blaine Grover
Download or read book Design of the Advanced Gas Reactor Fuel Experiments for Irradiation in the Advanced Test Reactor written by S. Blaine Grover and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The United States Department of Energy's Advanced Gas Reactor (AGR) Fuel Development and Qualification Program will be irradiating eight particle fuel tests in the Advanced Test Reactor (ATR) located at the newly formed Idaho National Laboratory (INL) to support development of the next generation Very High Temperature Reactor (VHTR) in the United States. The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy's lead laboratory for nuclear energy development. These AGR fuel experiments will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The experiments will be irradiated in an inert sweep gas atmosphere with on-line temperature monitoring and control combined with on-line fission product monitoring of the sweep gas. The final design phase has just been completed on the first experiment (AGR-1) in this series and the support systems and fission product monitoring system that will monitor and control the experiment during irradiation. This paper discusses the development of the experimental hardware and support system designs and the status of the experiment.
Book Synopsis Advanced Test Reactor by : J. O. Howard
Download or read book Advanced Test Reactor written by J. O. Howard and published by . This book was released on 1963 with total page 206 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development Publisher : ISBN 13 : Total Pages :1616 pages Book Rating :4.:/5 (319 download)
Book Synopsis Energy and Water Development Appropriations for 2007 by : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Download or read book Energy and Water Development Appropriations for 2007 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2006 with total page 1616 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Author :United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development Publisher : ISBN 13 : Total Pages :1304 pages Book Rating :4.0/5 (14 download)
Book Synopsis Energy and Water Development Appropriations for 2006 by : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Download or read book Energy and Water Development Appropriations for 2006 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 2005 with total page 1304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor by : Babcock & Wilcox Company. Atomic Energy Division, Lynchburg
Download or read book Design Criteria for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor written by Babcock & Wilcox Company. Atomic Energy Division, Lynchburg and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
