[3D Viewer]

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.
Object Type: Physical Object
System: The UNT Digital Library
Additional Miscellaneous Tools in the HRT Core (open access)

Additional Miscellaneous Tools in the HRT Core

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.
Object Type: Report
System: The UNT Digital Library
After Shutdown Heating in the HFIR (open access)

After Shutdown Heating in the HFIR

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 permanent beryllium reflector.
Date: December 29, 1960
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
Aircraft Reactor Test Removal and Disassembly (open access)

Aircraft Reactor Test Removal and Disassembly

Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Object Type: Report
System: The UNT Digital Library
Analog Computer Analysis of the Thermal Behavior of the EDCR Due to Reactivity Accidents (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR (open access)

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

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 optimum for the actual process were recommended from the analog study,
Date: November 28, 1960
Creator: Hinton, D. B.
Object Type: Report
System: The UNT Digital Library
Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1 (open access)

Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1

A stimulation study of the deign as of June 1960 of the gas-cooled ORR Loop No. 1 was made using the ORNL analog computer. The proposed method of temperature control is evaluated, and the dynamic behavior of the loop for accidents and component failures is presented in graphical form.
Date: November 8, 1960
Creator: Ball, S. J.
Object Type: Report
System: The UNT Digital Library
Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed (open access)

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

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 points up the reactor and there may be continuous or intermittent addition of fresh fuel and removal of residue ash.
Date: August 13, 1964
Creator: Scott, Charles D.
Object Type: Report
System: The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium (open access)

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

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 preparing wafers for analysis are discussed; the data are tabulated.
Date: December 27, 1960
Creator: Gaitanis, M. J.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report, December 31, 1960 (open access)

Analytical Chemistry Division Annual Progress Report, December 31, 1960

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date: 1961
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964 (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report, September 30, 1968 (open access)

Analytical Chemistry Division Annual Progress Report, September 30, 1968

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
Date: 1964-12~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
Object Type: Report
System: The UNT Digital Library
Applied Health Physics Annual Report for 1963 (open access)

Applied Health Physics Annual Report for 1963

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.
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1964 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1964

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date: July 1964
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962 (open access)

Army Reactors Program Annual Progress Report: 1962

Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date: April 10, 1963
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor (open access)

Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date: December 23, 1960
Creator: Wick, E. A. & Heestand, R. L.
Object Type: Report
System: The UNT Digital Library
An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology (open access)

An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology

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 developments, I would like today to talk about where to look for them--to give you some purely analytical considerations that assess the incentives we have to seed certain improvements in this or that portion of the equipment in a dual-purpose station.
Date: April 1964
Creator: Hammond, R. Philip
Object Type: Report
System: The UNT Digital Library
Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation (open access)

Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation

From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."
Date: September 1, 1960
Creator: U.S. Atomic Energy Commission
Object Type: Report
System: The UNT Digital Library
The Biocoenetic Process in an Estuarine Phytoplankton Community (open access)

The Biocoenetic Process in an Estuarine Phytoplankton Community

Report discussing "[a]n ecological theory of adaptation at the community level of organization" focused around an estuary and its resident life forms.
Date: October 1966
Creator: Patten, Bernard C.
Object Type: Report
System: The UNT Digital Library
Biology Division Semi-Annual Progress Report for Period Ending February 15, 1964 (open access)

Biology Division Semi-Annual Progress Report for Period Ending February 15, 1964

Technical report on the activities of the Oak Ridge National Laboratory Biology Division for the report period including a list of 346 publication and lectures and 205 short articles by members of the division on their research and activities.
Date: May 1964
Creator: Hollaender, Alexander, 1898-1986 & Carson, Stanley F.
Object Type: Report
System: The UNT Digital Library
Bremsstrahlung Absorption Measurements from Sr^90 TiO3 (open access)

Bremsstrahlung Absorption Measurements from Sr^90 TiO3

The absorption in lead of Bremsstrahlung X radiation from a Sr^90 TiO3 pellet in the proximity of Hastelloy "C" was measured. The tenth value layer of the more energetic components of the X-ray continuum was determined to be 1.60 inches.
Date: January 13, 1961
Creator: Butler, T. A. & Pierce, E. E.
Object Type: Report
System: The UNT Digital Library
Calculation of Suspension Peptization (open access)

Calculation of Suspension Peptization

Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
Date: 1960
Creator: Sweeton, F. H.
Object Type: Report
System: The UNT Digital Library
Chemical Development Section C Progress Report for October-November 1960 (open access)

Chemical Development Section C Progress Report for October-November 1960

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 rapid and efficient dissolution of the soluble thorium fraction. The cost of treating granite was estimated at $3.50-5.20 per ton, variations within this range being dependent primarily on differences in acid consumption for different granites. Estimated costs per pound of thorium plus uranium recovered ranged $30-500.
Date: March 3, 1961
Creator: Brown, K. B.
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, August 31, 1960 (open access)

Chemical Technology Division Annual Progress Report, August 31, 1960

Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date: 1960
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Object Type: Report
System: The UNT Digital Library