UNT Libraries Government Documents Department - 290 Matching Results

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[3D Viewer]

Description: Black cardboard viewer with plastic lenses, "for printed stereo photographs." It has scored portions and instructions for folding the cardboard to create a standing viewer to look through the lenses and keep the image at a distance.
Date: 1965
Creator: Stereo Magniscope, Inc.
Item Type: Refine your search to only Physical Object
open access

Additional Miscellaneous Tools in the HRT Core

Description: This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.
Date: September 26, 1960
Creator: Holz, P. P.
Item Type: Refine your search to only Report
open access

After Shutdown Heating in the HFIR

Description: After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanen… more
Date: December 29, 1960
Creator: McLain, H. A.
Item Type: Refine your search to only Report
open access

Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents

Description: The ORNL analog computer was used to examine one aspect of a safety system for the EGCR. The thermal behavior of the fuel as a result of increases in reactivity at various power levels and gas flows was examined. Safety actions initiated by wither a flux-minus-flow signal or a reactor outlet gas temperature signal were included in simulation.
Date: December 16, 1960
Creator: Pierce, R. M.
Item Type: Refine your search to only Report
open access

Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR

Description: An analog simulation is made of the HRP in-pile slurry loop in the LITR. The radiolytic gas pressure in the pressurizer is determined. This pressure is a result of the generation of radiolytic gas in the loop core. A graphical result is obtained showing the effect of catalyst activity and pressurizer flow rate on the pressure rise from radiolytic gas. The thermal behavior of the system is studied, and the response to various controller settings is predicted. Controller settings very near optimu… more
Date: November 28, 1960
Creator: Hinton, D. B.
Item Type: Refine your search to only Report
open access

Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Item Type: Refine your search to only Report
open access

Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium

Description: Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of … more
Date: December 27, 1960
Creator: Gaitanis, M. J.
Item Type: Refine your search to only Report
open access

Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964

Description: Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date: January 1965
Creator: Kelley, M. T.; Susano, C. D. & Fisher, D. J.
Item Type: Refine your search to only Report
open access

Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Item Type: Refine your search to only Report
open access

An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology

Description: From the questions which have been asked, I gather that I am expected to bring you the news of the latest exciting developments in desalination at the Oak Ridge National Laboratory. However, the agenda for this meeting does not include reports of unfinished investigations; moreover, although there are some new ideas afoot at Oak Ridge, they are aimed toward the very large stations which are somewhat beyond the scope of the more current interests represented here. So instead of presenting new de… more
Date: April 1964
Creator: Hammond, R. Philip
Item Type: Refine your search to only Report
open access

Chemical Development Section C Progress Report for October-November 1960

Description: Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain r… more
Date: March 3, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
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