95 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Uranium Dioxide"  
Results: 1 - 24 next
open access

Some Scoping Experiments for a Space Reactor

Description: Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failur… more
Date: July 7, 1983
Creator: Alexander, C. A. & Ogden, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CHARACTERIZATION OF UO$sup 2$ POWDERS. Progress Report No. 8, May and June 1961

Description: Correlation of a number of physical and chemical properties of 12 different UO/sub 2/ powders was continued. The UO/sub 2/ powders were studied by means of infrared absorption measurements, oxidation temperatures as determined by hot stage microscopy techniques, and B. E. T. surface area measurements. Additional pellets were prepared to study ceramic performance. (M.C.G.)
Date: July 19, 1961
Creator: Carpenter, J.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Selection of Core Design No. 1 for Type 5 Replacement Cores in SM-1 and SM-1A

Description: Nuclear and thermal analyses were performed to determine the characteristics of the Type 5 core in the SM-1 and SM-1A reactor plants as a function of geometry and composition. The following nuclear properties were investigated: core energy release, maximum midlife reactivity, average fuel burnup fraction, B-10 reactivity coefficient, and power distribution. Thermal parameter surveys determined the effects of channel thickness and power distribution upon the DNBR, nominal and hot channel thermal… more
Date: July 1, 1962
Creator: Davidson, S. L. & Paluszkiewicz, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of fill gas composition and pellet eccentricity. [BWR]

Description: Data and an analysis are presented showing that when the operating pellet-cladding gap size of contemporary UO/sub 2/ fuel rods is carefully considered, the gap conductances are closely proportional to the thermal conductivities of the fill gases. Pellet-cladding gap eccentricity is shown to raise the gap conductance appreciably in cases of high thermal gradients across the gap. Ignoring the azimuthal heat flow can lead to an underestimation of the thermal time constant of the rod, resulting in… more
Date: July 1, 1977
Creator: Williford, R.E. & Hann, C.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gas-cooled reactor programs: High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual progress report for period ending December 31, 1979

Description: Progress in HTGR studies is reported in the following areas: HTGR chemistry; fueled graphite development; prestressed concrete pressure vessel development; structural materials; HTGR graphite studies; and evaluation of the pebble-bed HTR.
Date: July 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Leaching Action of EJ-13 Water on Unirradiated UO₂ Surfaces under Unsaturated Conditions at 90 C : Interim Report

Description: A set of experiments, based on the application of the Unsaturated Test method to the reaction of uranium dioxide with EJ-13 water, has been conducted over a period of 182.5 weeks. One half of the experiments have been terminated, while one half are still ongoing. Solutions that have dripped from uranium dioxide specimens have been analyzed for all experiments, while the reacted uranium dioxide surfaces have been examined for only the terminated experiments. A pulse of uranium release from the u… more
Date: July 1991
Creator: Wronkiewicz, D. J.; Bates, John K.; Gerding, Thomas J.; Veleckis, Ewald; Tani, B. & Hoh, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTGR Fuel Technology Program. Semiannual report for the period ending March 31, 1983

Description: This document reports the technical accomplishments of the HTGR Fuel Technology Program at GA Technologies Inc. during the first half of FY 83. The activities include the fuel process, fuel materials, fuel cycle, fission product transport, core component verification, and core technology transfer tasks necessary to support the design and development of a steam cycle/cogeneration (SC/C) version of the HTGR.
Date: July 1, 1983
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fission-product SiC reaction in HTGR fuel

Description: The primary barrier to release of fission product from any of the fuel types into the primary circuit of the HTGR are the coatings on the fuel particles. Both pyrolytic carbon and silicon carbide coatings are very effective in retaining fission gases under normal operating conditions. One of the possible performance limitations which has been observed in irradiation tests of TRISO fuel is chemical interaction of the SiC layer with fission products. This reaction reduces the thickness of the SiC… more
Date: July 13, 1981
Creator: Montgomery, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Breeder reactor fuel fabrication system development

Description: Significant progress has been made in the design and development of remotely operated breeder reactor fuel fabrication and support systems (e.g., analytical chemistry). These activities are focused by the Secure Automated Fabrication (SAF) Program sponsored by the Department of Energy to provide: a reliable supply of fuel pins to support US liquid metal cooled breeder reactors and at the same time demonstrate the fabrication of mixed uranium/plutonium fuel by remotely operated and automated met… more
Date: July 16, 1981
Creator: Bennett, D.W.; Fritz, R.L.; McLemore, D.R. & Yatabe, J.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Post-irradiation examination of Oconee 1 fuel - cycle 1 destructive test phase

Description: Standard B and W Mark-B (15 x 15) pressurized water reactor fuel rods were destructively examined after one cycle of irradiation in the Oconee 1 reactor. Fuel rod average burnup ranged from 10,603 to 11,270 MWd/mtU for the rods examined. Data obtained included fuel rod extraction loads, rod dimensional changes, cladding tensile properties, fuel pellet gap length, fission product distribution, fission gas and crud composition, fuel densification, chemical burnup analysis, and fuel and cladding m… more
Date: July 1, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Equilibrium oxygen potential-composition relations in hypostoichiometric plutonia

Description: The oxygen potential of hypostoichiometric plutonia at temperatures from 1000 to 1200/sup 0/C has been measured as a function of the oxygen-to-plutonium ratio by a thermogravimetric procedure. These data have been used to calculate activity coefficients for plutonia dissolved in urania and in thoria.
Date: July 16, 1979
Creator: Woodley, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Chemical flowsheet conditions for preparing urania spheres by internal gelation

Description: Small, ceramic urania spheres can be prepared for use as nuclear fuel by internal chemical gelation of uranyl nitrate solution droplets. Decomposition of hexamethylenetetramine (HMTA) dissolved in the uranyl nitrate solution releases ammonia to precipitate hydrated UO/sub 3/. Previously established flowsheet conditions have been improved and modified at ORNL and have been applied to prepare dense UO/sub 2/ spheres with average diameters of 1200, 300, and 30 ..mu..m.
Date: July 1, 1979
Creator: Haas, P.A.; Begovich, J.M.; Ryon, A.D. & Vavruska, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Roll compaction and granulation system for nuclear fuel material

Description: A roll compaction and roll granulation system has been designed and fabricated to replace conventional preslugging and crushing operations typically used in the fabrication of mixed oxide nuclear fuel pellets. This equipment will be of maintenance advantage with only the compaction and granulation rolls inside containment. The prototype is being tested and the results will be reported within a year.
Date: July 29, 1981
Creator: Goldmann, L.H. Jr. & Holley, C.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experimental determinations of the pre- and postirradiation thermal transport and thermal expansion properties of simulated fuel rods for an HTGR

Description: The thermal conductivity, electrical resistivity, coefficient of thermal expansion, volume, and Seebeck coefficient of simulated fuel rods for a high-temperature gas-cooled reactor (HTGR) were measured before and after neutron irradiations to 13.5 x 10/sup 25/ neutrons/m/sup 2/ at nominal irradiation temperatures of 1220 K. These measurements were made as functions of volume percent particle loading, temperature, and neutron fluence. The thermal conductivities decrease with increasing particle … more
Date: July 1, 1978
Creator: Moore, J. P.; Godfrey, T. G.; Graves, R. S.; Eatherly, W. P.; Long, E. L. Jr. & Weaver, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Space nuclear safety program: Progress report, April-June 1987

Description: This quarterly report describes studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems, carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed are ongoing; the results and conclusions described may change as the work progresses.
Date: July 1, 1988
Creator: George, T.G. (comp.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories monthly activities report, June 1963

Description: This is the monthly report for the Hanford Laboratories Operation, June 1963. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 15, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation Monthly Activities Report: June 1962

Description: This is the monthly report for the Hanford Laboratories Operation June 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: July 16, 1962
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Validation of criticality safety calculational methods for U-AVLIS plant project

Description: The objectives of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) are to develop, demonstrate, and deploy a laser-based process to enrich natural uranium in the U-235 isotope to levels useful as fuel in commercial light-water power reactors. Current U-AVLIS production plant criteria call for uranium product enriched in {sup 235}U up to 5 wt%. Development of the U-AVLIS technology is in an advanced stage, and demonstration of the integrated enrichment process is currently in progress… more
Date: July 14, 1993
Creator: Lewis, K. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Determination of fission product and heavy metals inventories in FTE-4 fuel rods by a grind-burn-leach flowsheet

Description: Experiments using High-Temperature Gas-Cooled Reactor (HTGR) fuel material, TRISO-coated (2.75 Th/U)C/sub 2/--TRISO-coated ThC/sub 2/ and TRISO-coated UO/sub 2/--BISO-coated ThO/sub 2/, were performed in Building 4507 (the High-Level Chemical Development Facility) to determine the inventory and transport behavior of fission products and heavy metals from a grind-burn-leach process flowsheet. In addition, values calculated by the ORNL Isotope Generation and Depletion Code (ORIGEN, a computer pro… more
Date: July 1, 1977
Creator: Fitzgerald, C. L.; Vaughen, V. C. A. & Lamb, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PuO/sub 2/ dissolution problem for LWR plutonium recycle and LMFBR fuels: fabrication and reprocessing problems and their resolution

Description: A survey was made of the information reported to date for laboratory-scale dissolution experiments on PuO/sub 2/-UO/sub 2/ fuels, of reprocessing plant problems that might be encountered with these fuels, and of the fabrication methods for producing these fuels. The possibility of producing fuels that will be highly soluble in pure nitric acid without resorting to the use of corrosive fluorides for complete dissolution is examined. The report concludes that production of highly soluble fuel is … more
Date: July 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparative analysis of pellet-cladding interaction from IFA-431 and IFA-432 Halden reactor tests. [BWR]

Description: Two test assemblies containing a total of 12 instrumented fuel rods were irradiated in the HBWR to obtain well-characterized data for fuel operating in the linear heat ranges of commercial nuclear power plants. These data are needed for verification of GAPCON-THERMAL and FRAP computer codes and will provide a series of benchmarks for indexing other thermal performance codes used for reactor safety analysis. Two essentially identical test assemblies, IFA-431 and IFA-432, each containing six inst… more
Date: July 1, 1977
Creator: Hann, C. R. & Marshall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation Monthly Activities Report: June 1961

Description: The monthly report for the Hanford Laboratories Operation, June 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.
Date: July 15, 1961
Creator: Hanford Laboratories
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen