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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

Status Report Number Three on Clinch River Study

Description: Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.
Date: December 6, 1962
Creator: Morton, R. J.
Item Type: Refine your search to only Report
open access

Air Scattering of Co60 Gamma Rays: Theory Versus Experiment

Description: For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Date: April 17, 1958
Creator: Moran, Rubert S.
Item Type: Refine your search to only Report
open access

Disassembly and Postoperative Examination of the Aircraft Reactor Experiment

Description: The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much… more
Date: April 15, 1958
Creator: Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
Item Type: Refine your search to only Report
open access

Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R. J. & Wischow, R. P.
Item Type: Refine your search to only Report
open access

A Fluoride Fuel In-Pile Loop Experiment

Description: An inconel loop circulating fluoride fuel (62 1/2 make [unintelligible] NaF, 12 1/2 make [unintelligible] ZrF4, 25 make [unintelligible] UF4, 92 [unintelligible] enriched) was operated at 1485°F with a temperature difference of about 35°F in the Low Intensity Test Reactor for 645 hr. For 475 hr of this time the reactor was at full power, and fission power generation in the loop was 2.7 kw, with a max length power density of 0.4 kw/cc. The total volume of fuel was 1290 cc (5.o kg [unintelligible… more
Date: January 29, 1957
Creator: Sisman, Q; Brundage, W. E.; Parkinson, W. W.; Boumann, C. D.; Correll, R. M; Morgen, J. G. et al.
Item Type: Refine your search to only Report
open access

High-Thermal-Conductivity Fin Material for Radiators

Description: This report is the result of a study to develop heat-resistant fin materials possessing a high thermal conductivity for air radiators. Since an economical and commercially feasible product was desired, the investigation was restricted primarily to a study of electroplated copper, clad copper, and copper alloys. Sheet material 0.008 to 0.010 in. thick was evaluated for fabricability and for metallurgical stability and thermal conductivity at 1500°F. From the results of the rests it was concluded… more
Date: January 24, 1957
Creator: Inouye, H.
Item Type: Refine your search to only Report
open access

Analysis of Thorex Pilot Plant Radiation Exposures During 1955

Description: The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equi… more
Date: November 16, 1956
Creator: McCarley W. T.
Item Type: Refine your search to only Report
open access

An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

Description: The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed … more
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
Item Type: Refine your search to only Report
open access

Metallurgy Division Semiannual Progress Report for Period Ending April 10, 1956

Description: Progress report of the Oak Ridge National Laboratory Metallurgy Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output and summaries of general corrosion, dynamic corrosion, mechanical properties, nondestructive testing, welding and brazing, fabrication, physical chemistry of corrosion, HRP metallurgy, the package power reactor program, APPR absorber, metallurgical materials and processing, metallography, ceramics, fundam… more
Date: November 2, 1956
Creator: Frye, J. H., Jr.; Manly, W. D. & Cunningham, J. E.
Item Type: Refine your search to only Report
open access

Basic Gamma-Ray Data for ART Heat Deposition Calculations

Description: In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the he… more
Date: October 3, 1956
Creator: Bertini, H. W.; Copenhaver, C. M.; Perry, A. M. & Stevenson, R. B.
Item Type: Refine your search to only Report
open access

Operation of the ORNL Graphite Reactor and the Low-Intensity Test Reactor — 1955 LITR Flux Traverses

Description: The ORNL Graphite Reactor operated very well during 1955. The downtime was low, only 8.6%. The fuel in the bonded slugs did not perform as well in 1955 as in 1954. Much of the trouble was undoubtedly due to growth of slugs which were not beta-transformed. It is known that some slugs had grown over 1/2 in. The automatic central system installed in 1954 continued to operate satisfactorily. The cooling system gave minor trouble when one of the 900-hp fan meters had to be replaced because of shorts… more
Date: September 10, 1956
Creator: Rupp, A. F. & Cox, J. A.
Item Type: Refine your search to only Report
open access

A Physical Property Summary for Fluoride Mixtures

Description: This report presents a summary of certain physical properties that have been determined experimentally on the fluoride mixture that have been formulated at ORNL (Rers. 1, 2). These properties include the density, enthalpy, heat capacity, heat of fusion, thermal conductivity, viscosity, Prandtl number, electrical conductivity and surface tension. In addition to the experimental data, values have been predicted for the heat capacity and density of the other mixtures from the correlations of these… more
Date: September 5, 1956
Creator: Cohen, S. I.; Povers, W. D. & Greene, N. D.
Item Type: Refine your search to only Report
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, S. J.; Miller, A. J. & Savelainen, A. W.
Item Type: Refine your search to only Report
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Secret Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cromer, S. J.; Miller, A. J. & Savelainen, A. W.
Item Type: Refine your search to only Report
open access

HRP Radiation Corrosion Studies

Description: A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zirca… more
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
Item Type: Refine your search to only Report
open access

HRT Reactor Hazards

Description: Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed.… more
Date: August 3, 1956
Creator: Miller, E. C.
Item Type: Refine your search to only Report
open access

Analytical Chemistry Division Semiannual Progress Report for Period Ending April 20, 1954

Description: Progress report of the Oak Ridge National Laboratory Analytical Chemistry Division providing updates on various projects, experiments, and other work in ionic analyses, analytical instrumentation, radiochemical analyses, activation analyses, spectrochemical analyses, inorganic preparations, optical and electron microscopy.
Date: July 5, 1956
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
Item Type: Refine your search to only Report
open access

Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field

Description: In some recent experiments the ion density in a plasma was measured as a function of radial distance from a d-c arc source of ions for the magnetic field intensities from 2500 to 14000 oersted. The diffusion coefficient appeared to very inversely as the square of the magnetic field strength, D~1/H2. The absolute value of D was shown to be approximately that which would be predicted by the collision diffusion theory when account is taken of the shorting effect of the end walls. The purpose of th… more
Date: June 15, 1956
Creator: Reidigh, Rodger V.
Item Type: Refine your search to only Report
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1956

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and ether ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research.
Date: June 13, 1956
Creator: Jordan, W. H.; Cromer, S. J. & Miller, A. J.
Item Type: Refine your search to only Report
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