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Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977

Description: Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the… more
Date: February 1, 1978
Creator: Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Partner: UNT Libraries Government Documents Department
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Energy Measurements in Oxygen-Induced Reactions at 60 A GeV and 200 A GeV

Description: In an effort to isolate characteristic features of nucleus-nucleus collisions (e.g., collective phenomena) from those that may be expected on the basis of a linear superposition of nuelceon-nucleon collisions, we will compare measured quantities with calculations that reproduce data from nucleon-induced reactions and that make predictions for nucleus-nucleus reactions. While several models are available for this procedure, none has yet been demonstrated to have clear advantages over the others.… more
Date: January 1, 1988
Creator: Awes, T. C.; Albrecht, R.; Baktash, C.; Beckmann, P.; Berger, F.; Bock, R. et al.
Partner: UNT Libraries Government Documents Department
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Development of a Laser Optically Pumped Polarized Target for Use in Heavy-Ion Physics

Description: Important micro- and macroscopic details of heavy-ion reactions may be explicitly determined when nuclear spin aligned (polarized) targets are used. For deformed nuclei, the orientation of the symmetry axis of the nuclear density distribution is determined by the nuclear spin orientation. Polarized targets would thus allow experiments to be performed as a function of the orientation of the symmetry axis of the nuclear density distribution. A polarized target of /sup 151/ /sup 153/Eu is being de… more
Date: January 1, 1982
Creator: Shivakumar, B.; Beene, J.R.; Bemis, C.E. Jr.; Erb, K.A.; Ford, J.L.C. Jr. & Shapira, D.
Partner: UNT Libraries Government Documents Department
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MHD Activity in the ISX-B Tokamak: Experimental Results and Theoretical Interpretation

Description: The observed spectrum of MHD fluctuations in the ISX-B tokamak is clearly dominated by the n=1 mode when the q=1 surface is in the plasma. This fact agrees well with theoretical predictions based on 3-D resistive MHD calculations. They show that the (m=1; n=1) mode is then the dominant instability. It drives other n=1 modes through toroidal coupling and n>1 modes through nonlinear couplings. These theoretically predicted mode structures have been compared in detail with the experimentally measu… more
Date: January 1, 1982
Creator: Carreras, B. A.; Dunlap, J. L.; Bell, J. D.; Charlton, L. A.; Cooper, W. A.; Dory, R. A. et al.
Partner: UNT Libraries Government Documents Department
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Reevaluation of 1999 Health-Based Environmental Screening Levels (HBESLs) for Chemical Warfare Agents

Description: This report evaluates whether new information and updated scientific models require that changes be made to previously published health-based environmental soil screening levels (HBESLs) and associated environmental fate/breakdown information for chemical warfare agents (USACHPPM 1999). Specifically, the present evaluation describes and compares changes that have been made since 1999 to U.S. Environmental Protection Agency (EPA) risk assessment models, EPA exposure assumptions, as well as to sp… more
Date: May 1, 2007
Creator: Watson, Annetta Paule & Dolislager, Fredrick G
Partner: UNT Libraries Government Documents Department
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Data Compilation for AGR-3/4 Designed-to-Fail (DTF) Fuel Particle Batch LEU04-02DTF

Description: This document is a compilation of coating and characterization data for the AGR-3/4 designed-to-fail (DTF) particles. The DTF coating is a high density, high anisotropy pyrocarbon coating of nominal 20 {micro}m thickness that is deposited directly on the kernel. The purpose of this coating is to fail early in the irradiation, resulting in a controlled release of fission products which can be analyzed to provide data on fission product transport. A small number of DTF particles will be included … more
Date: October 1, 2008
Creator: Hunn, John D & Miller, James Henry
Partner: UNT Libraries Government Documents Department
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Summary Report for the Initiation of Compact Development for Particles with 425-micron Kernels

Description: The purpose of this research was the initiation of overcoating TRISO particles with 425 {micro}m kernels. In the AGR-1 task, the overcoating process was optimized for particles with an outer diameter (OD) of 780 {micro}m and a 350 {micro}m kernel. Therefore it needed to be determined how well the overcoating process used to fabricate AGR-1 compacts would perform on particles with an 855 {micro}m OD and a 425 {micro}m kernel. The matrix properties and overcoating procedures were altered from the… more
Date: September 1, 2007
Creator: Pappano, Peter J
Partner: UNT Libraries Government Documents Department
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Airborne Radioactivity Survey of the Red Desert Region, Sweetwater County, Wyoming

Description: From abstract: An airborne radioactivity survey of a selected area in the Red Desert, Sweetwater County, Wyoming, containing outcrops of radioactive lignites and shales of known surface extent and uranium content, was flown on flight lines at three levels, respectively 250, 500, and 1,000 feet above the ground and spaced at one-quarter mile intervals. Measurements from three identical dual-channel radiation detectors were simultaneously recorded to obtain data at various distances from natural … more
Date: July 1951
Creator: Nelson, R. A.; Sharp, William N. & Stead, Frank W.
Partner: UNT Libraries Government Documents Department
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Evaluation of the District of Columbia Energy Office Residential Conservation Assistance Program for Natural Gas-Heated Single-Family Homes

Description: At the request of the U.S. Department of Energy (DOE), Oak Ridge National Laboratory (ORNL), with assistance from the District of Columbia Energy Office (DCEO) performed an evaluation of part of the DCEO Residential Conservation Assistance Program (RCAP). The primary objective of the evaluation was to evaluate the effectiveness of the DCEO weatherization program. Because Weatherization Assistance Program (WAP) funds are used primarily for weatherization of single-family homes and because evalua… more
Date: March 1, 2007
Creator: McCold, Lance Neil & Schmoyer, Richard L
Partner: UNT Libraries Government Documents Department
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Current Renewable Energy Technologies and Future Projections

Description: The generally acknowledged sources of renewable energy are wind, geothermal, biomass, solar, hydropower, and hydrogen. Renewable energy technologies are crucial to the production and utilization of energy from these regenerative and virtually inexhaustible sources. Furthermore, renewable energy technologies provide benefits beyond the establishment of sustainable energy resources. For example, these technologies produce negligible amounts of greenhouse gases and other pollutants in providing en… more
Date: May 1, 2007
Creator: Allison, Stephen W.; Lapsa, Melissa Voss; Ward, Christina D.; Smith, Barton; Grubb, Kimberly R. & Lee, Russell
Partner: UNT Libraries Government Documents Department
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PWR Facility Dose Modeling Using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology

Description: The feasibility of modeling a pressurized-water-reactor (PWR) facility and calculating dose rates at all locations within the containment and adjoining structures using MCNP5 with mesh tallies is presented. Calculations of dose rates resulting from neutron and photon sources from the reactor (operating and shut down for various periods) and the spent fuel pool, as well as for the photon source from the primary coolant loop, were all of interest. Identification of the PWR facility, development o… more
Date: September 1, 2007
Creator: Blakeman, Edward D; Peplow, Douglas E.; Wagner, John C; Murphy, Brian D & Mueller, Don
Partner: UNT Libraries Government Documents Department
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Note on Graphite Oxidation by Oxygen and Moisture

Description: Simplified equations of graphite oxidation are reviewed for semi-infinite slab, finite slab, and cylinder geometries, using the principal assumptions of linearized oxidation kinetics and quasi-steady state oxidation profile. All equations are coupled to a general surface mass transfer boundary condition. The equations include those for oxidant concentration distribution, surface oxidation rate, burnoff profile, and oxidation efficiency. This review also covers some areas that may not be well re… more
Date: February 1, 2009
Creator: Wichner, Robert; Burchell, Timothy D & Contescu, Cristian I
Partner: UNT Libraries Government Documents Department
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Evaluation of the French Haut Taux de Combustion (HTC) Critical Experiment Data

Description: In the 1980s, a series of critical experiments referred to as the Haut Taux de Combustion (HTC) experiments was conducted by the Institut de Radioprotection et de Surete Nucleaire (IRSN) at the experimental criticality facility in Valduc, France. The plutonium-to- uranium ratio and the isotopic compositions of both the uranium and plutonium used in the simulated fuel rods were designed to be similar to what would be found in a typical pressurized-water reactor fuel assembly that initially had a… more
Date: September 1, 2008
Creator: Mueller, Don; Elam, Karla Riggle & Fox, Patricia B
Partner: UNT Libraries Government Documents Department
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Determination of Suitable Insulation for a 1-5/16" Helium Filled Annulus in the ORR Helium In-Pile Loop, Design No. 4

Description: Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1… more
Date: August 17, 1959
Creator: Knight, R. B. & Helms, R. E.
Partner: UNT Libraries Government Documents Department
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Shut-Down Cooling of ORR

Description: The purpose of this memo is to present information which may be used in estimating the magnitude of the shut-down cooling problem in the ORR at various power levels. Using previously estimated data for the MTR (IDO-16443), a rough estimate of the space distribution of heat release after shut-down is presented.
Date: August 14, 1959
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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Surface-Exchange Method for Determination of Surface Area of UO2 Powder

Description: Applicability of the surface-exchange method of determination of surface area of UO2 powder has been investigated. Preliminary results indicate that the method offers a rapid and easy determination of surface area with a precision of ~ 10%.
Date: August 6, 1959
Creator: Ferguson, R. L. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Measurement of the "Active Deposit" of Thoron

Description: A description is given of the properties of the nuclides included in the "active deposit" of thoron. A method is presented for obtaining a quantitative measurement of the activity of the transient-equilibrium mixture.
Date: August 17, 1959
Creator: Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
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Phase Stability of Homogenous Reactor Hot Fuel Solutions

Description: Portions of two samples of HRT fuel solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined.This report gives the results of these observations.
Date: August 18, 1959
Creator: Barton, C. J.; Gill, J. S.; Hebert, G. M.; Marshall, W. L. & Moore, R. E.
Partner: UNT Libraries Government Documents Department
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: The Fluoride Volatility Process was developed to recover uranium from fused salt reactor fuels. After two testing runs had been completed processing was interrupted because of a UF6 leak. After all faulty connections and seals had been made gas-tight, processing of the ARE fuel was resumed and carried to completion. This report covers processing of the ARE fuel through the last four runs plus a summary of the entire ARE reprocessing program.
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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Temperature Transients Due to Density Changes on Changing Power Level in the HRT

Description: Changing the power level in the HRT leads to small average density changes in the high pressure system which produce noticeable changes in the nuclear average temperature. It is calculated that taking the reactor from zero power to 5Mw in one-half hour will lead to a temperature rise of about 0.7 degrees C, followed by a gradual fall over a two-hour period to about 1.3 degrees C below the temperature at zero power.
Date: April 6, 1961
Creator: Tobias, M.L. & Vondy, D.R.
Partner: UNT Libraries Government Documents Department
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Evaluation of Electroless Nickel Brazed Tube Bundles

Description: Two arrays of stainless steel tubes and ferrules which had been electroless nickel brazed were submitted for metallographic evaluation. These represented the first and second attempts of Ferrotherm of Cleveland to fabricate fuel bundles using the procedures outlined by Westinghouse Atomic Power Department for the Yankee Power Reactor.
Date: April 26, 1961
Creator: Crouse, R.S.
Partner: UNT Libraries Government Documents Department
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Preparation and Specifications of Miniature Fermi Reactor Core B Fuel Specimens for Irradiation Testing

Description: The preparation of miniature plate specimens containing dispersions of 33.2 wt % UO2 in type 347 stainless steel for irradiation testing is described. These plates stimulate the prototype roll-bonded stainless steel clad composite plates intended for the Core B fuel element of the Enrico Fermi sodium-cooled reactor. The significant characteristics of the fabricated irradiation specimens are tabulated. The samples will be used to determine the irradation behavior of 33.2 wt % UO2 at temperatur… more
Date: April 21, 1961
Creator: Cherubini, J.H. & Williams, R.C.
Partner: UNT Libraries Government Documents Department
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Some Temperature Aspects of the HFIR Control Plate System

Description: This study examines the effects of water flow rate through the control region on local bulk water temperature and on control plate surface temperature, radial thermal expansion, and thermal stress. Flow rates of 1200, 800 and 400 gpm are considered for each of three control plate positions typical of startup, mid-cycle, and end-of-cycle. Based on the factors investigated in this study, the calculations indicate that a flow rate as low as 400 gpm may be reasonable.
Date: April 18, 1961
Creator: Haack, L.A.
Partner: UNT Libraries Government Documents Department
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Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, had operated for the bulk of the test programs in the temperature range 1000-1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-inch), the location of damaged areas varying with impeller geometry.
Date: April 10, 1961
Creator: DeVan, J.H.
Partner: UNT Libraries Government Documents Department
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