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GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961

Description: Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced… more
Date: February 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, May 1961

Description: The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engi… more
Date: December 26, 1961
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production of Pebble-Type Fuel Elements

Description: A capillary-drop method of producing spherical shapes of brittle materials less than 0.l00 inch in diameter was developed. It appears to be a feasible means for producing large numbers of pebble-tyne fuel element cores. Coating of pebble-type fuel element cores by the coating-pan technique, though not adequately developed, showed promise. (auth)
Date: June 1, 1955
Creator: Brassfield, H.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report

Description: >The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces an… more
Date: April 30, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL CYCLES FOR AN 800 Mw(t) PEBBLE-BED REACTOR

Description: Reactivity lifetime calculations were made for an 800Mw(t) pebble-bed reactor on the basis of a batch-fueling cycle, a once-through equilibrium cycle, and a gradedexposure equilibrium cycle. The maximum lifetime, obtained with the graded-exposure equilibrium cycle, was 1.41 fissions per initial fissionable atom. In this case the conversion ratio was 0.62 and the neutron leakage from the core was 0.078. The same fuel composition gave 1.29 fissions per initial fissionable atom on a once-through e… more
Date: August 1, 1962
Creator: Carlsmith, R.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HTR-PROTEUS Pebble Bed Experimental Program Cores 1, 1A, 2, and 3: Hexagonal Close Packing with a 1:2 Moderator-to-Fuel Pebble Ratio

Description: In its deployment as a pebble bed reactor (PBR) critical facility from 1992 to 1996, the PROTEUS facility was designated as HTR-PROTEUS. This experimental program was performed as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on the Validation of Safety Related Physics Calculations for Low Enriched HTGRs. Within this project, critical experiments were conducted for graphite moderated LEU systems to determine core reactivity, flux and power profiles, rea… more
Date: March 1, 2013
Creator: Bess, John D.; Dolphin, Barbara H.; Sterbentz, James W.; Snoj, Luka; Lengar, Igor & Köberl, Oliver
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Safeguards Considerations For The Pebble Bed Modular Reactor (PBMR)

Description: High temperature reactors (HTRs) have been considered since the 1940s, and have been constructed and demonstrated in the United Kingdom (Dragon), United States (Peach Bottom and Fort Saint Vrain), Japan (HTTR), Germany (AVR and THTR-300), and have been the subject of conceptual studies in Russia (VGM). The attraction to these reactors is that they can use a variety of reactor fuels, including abundant thorium, which upon reprocessing of the spent fuel can produce fissile U-233. Hence, they coul… more
Date: October 1, 2009
Creator: Durst, Phillip Casey; Beddingfield, David; Boyer, Brian; Bean, Robert; Collins, Michael; Ehinger, Michael et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report on Utilization of TRU TRISO Fuel as Applied to HTR Systems Part I: Pebble Bed Reactors

Description: The Deep-Burn (DB) concept [ ] focuses on the destruction of transuranic nuclides from used light water reactor (LWR) fuel. These transuranic nuclides are incorporated into tri-isotopic (TRISO) coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes bet… more
Date: March 1, 2011
Creator: Boer, Brian & Ougouag, Abderrafi M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multiscale Analysis of Pebble Bed Reactors

Description: – The PEBBED code was developed at the Idaho National Laboratory for design and analysis of pebble-bed high temperature reactors. The diffusion-depletion-pebble-mixing algorithm of the original PEBBED code was enhanced through coupling with the THERMIX-KONVEK code for thermal fluid analysis and by the COMBINE code for online cross section generation. The COMBINE code solves the B-1 or B-3 approximations to the transport equation for neutron slowing down and resonance interactions in a homogeneo… more
Date: October 1, 2010
Creator: Gougar, Hans; Yoon, Woo & Ougouag, Abderrafi
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Thermo-Mechanical Analysis of Coated Particle Fuel Experiencing a Fast Control Rod Ejection Transient

Description: A rapid increase of the temperature and the mechanical stress is expected in TRISO coated particle fuel that experiences a fast Total Control Rod Ejection (CRE) transient event. During this event the reactor power in the pebble bed core increases significantly for a short time interval. The power is deposited instantly and locally in the fuel kernel. This could result in a rapid increase of the pressure in the buffer layer of the coated fuel particle and, consequently, in an increase of the coa… more
Date: October 1, 2010
Creator: Ortensi, J.; Boer, Brian & Ougouag, Abderrafi M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Review of S and P 1963, the Pebble Bed Reactor

Description: Sanderson and Perter, under contract to the AEC, prepared a design feasibility study for a pebble-bed reactor steam power plant of 125-Mw(e) capacity. The design problems, economic considerations, and required research and development programs were reviewed by ORNL. It is concluded that the design shows promise of being economically competitive if the following conditions are met: (1) U/sup 233/ could be made available for use as a burner rather than as a breeder; (2) the contamination problems… more
Date: July 17, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Description: Originally issued as S and P 1963A, Parts I and II. A design and feasibility study of a pebble bed reactorsteam power plant is presented, The reactor design which evolved from this study is a 125 Mwe heliumcooled two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam gene… more
Date: May 1, 1958
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GAS COOLED PEBBLE BED REACTOR FOR A LARGE CENTRAL STATION. Reactor Design and Feasibility Study

Description: An optimum econonic design for a high temperature, helium cooled, central station reactor power plant of about 400 Mw of electric power was determined. The core consists of a randomly packed bed of unclad graphite spheres, approximately one in. in diameter, impregnated with U/sup 233/ and thorium such that a conversion ratio of near unity is achieved. The high temperature helium permits steam conditions, at the turbine throttle, of 1000 deg F and 1450 psia. (auth)
Date: August 1, 1957
Creator: Schock, A.; Bruley, D.F.; Culver, H.N.; Ianni, P.W.; Kaufman, W.F.; Schmidt, R.A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GAS-COOLED REACTOR PROGRAM. Semiannual Progress Report for Period Ending September 30, 1962

Description: Investigations carried out in support of the Experimental Gas-cooled Reactor included: performance analysis, structural studies, component development and testing, materials development, irradiation testing of components and materials, and development of experimental facilities. Design and development studies, system analyses, and determination of heat transfer anf fiuid fiow in packed sphere beds were carried out for the Pebble-Bed Reactor Experiment. Progress is also reported on investigation… more
Date: February 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CONCEPTUAL DESIGN OF THE PEBBLE BED REACTOR EXPERIMENT

Description: The Pebble-Bed Reactor Experiment (PBRE) was designed to advance the pebble-bed concept by providing a test of characteristic features and make contriliutions to the general development of all-ceramic gas-cooled reactors. The following objectives were established for the reactor experiment: to investigate key features of the pebble-bed concept, including on-stream fuel handling, movement of fuel through bed, and performance of core; to obtain operation and maintenance experience with a system c… more
Date: May 17, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Phase II Summary Report, November 1, 1959 to October 31, 1960

Description: Coatings on the fuel element surface and coatings on individual fuel particles are being investigated for retaining fission products in fuel for the Pebble Bed Reacter. Ten fuel element specimens with surface coatings were subjected to varying amounts of high level irradiation. Cracks or pinholes were found in 6 of the coatings. Evidence indicated that the graphite matrix contributed to most of the failures. Release factors of the order of 10/sup -9/ for the Si--SiC coating under high-level irr… more
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 9 & 10: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:1 MODERATOR-TO-FUEL PEBBLE RATIO

Description: PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PR… more
Date: March 1, 2013
Creator: Bess, John D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTR-PROTEUS PEBBLE BED EXPERIMENTAL PROGRAM CORES 5, 6, 7, & 8: COLUMNAR HEXAGONAL POINT-ON-POINT PACKING WITH A 1:2 MODERATOR-TO-FUEL PEBBLE RATIO

Description: PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cylindrical cavity. The graphite annulus remains basically the same for all experimental programs, but the contents of the central cavity are changed according to the type of reactor being investigated. Through most of its service history, PROTEUS has represented light-water reactors, but from 1992 to 1996 PROTEUS was configured as a pebble-bed reactor (PBR) critical facility and designated as HTR-PR… more
Date: March 1, 2013
Creator: Bess, John D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTR-PROTEUS Pebble Bed Experimental Program Cores 1, 1A, 2, and 3: Hexagonal Close Packing with a 1:2 Moderator-to-Fuel Pebble Ratio

Description: In its deployment as a pebble bed reactor (PBR) critical facility from 1992 to 1996, the PROTEUS facility was designated as HTR-PROTEUS. This experimental program was performed as part of an International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) on the Validation of Safety Related Physics Calculations for Low Enriched HTGRs. Within this project, critical experiments were conducted for graphite moderated LEU systems to determine core reactivity, flux and power profiles, rea… more
Date: March 1, 2012
Creator: Bess, John D.; Dolphin, Barbara H.; Sterbentz, James W.; Snoj, Luka; Lengar, Igor & Köberl, Oliver
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. A Topical Report on SUB-SURFACE COATINGS FOR FUELED GRAPHITE SPHERES

Description: An exploratory program on subsurface coatin8s for graphite fuel elements is summarized. A number of coatings with various melting points which could be located beneath the surface of a fueled graphite sphere were investigated. Of the materials with lower melting points. nickel and a special glass compound appeared to form continuous coatings when a hot-pressing technique was employed. Several materials with high melting points. such as Ti, Cr, and MoSi/sub 2/, showed some promise, even though p… more
Date: June 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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