Technical Report Archive & Image Library (TRAIL) - 405 Matching Results

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APPR-1 Type Absorber Rod Irradiation Test -- Irradiation Request ORNL MTR-29

Description: In order to evaluate the behavior of an APPR type absorber rod, an irradiation test program has been established. Approximately 21 more samples are planned for testing under this request. The request proposes testing a full size APPR-1 type control rod in the MTR. The objective of the test is to better evaluate the neutron absorbing material proposed for the APPR-1 control rod.
Date: January 4, 1957
Creator: Gross, E. E. & Schaffter, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aqueous Uranium Slurry Studies

Description: A summary of the laboratory development program on aqueous uranium slurry fuels for the Homogenous Reactor Project during the period April 1951 through March 1953 is presented. These investigations were devoted primarily to a study of the uranium oxides in aqueous suspensions. It was concluded that U(VI) was most likely to be the stable valence state in such slurry fuels and it was shown that β-UO3·H2O platelet crystals were the stable modification at 250°C. Very pure slurries of β-UO3·H2O pla… more
Date: October 20, 1955
Creator: Blomeke, J. O.; Bamberg, J. L.; Blomeke, J. O.; Bruce, F. R.; Fulmer, J. M.; McBride, J. P. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Bellows Failure in Solids Separation Loop of the HRT Mockup

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion and crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conditions for stress corrosion to occur. Crevice corrosion occurred probably due to he… more
Date: February 5, 1957
Creator: Kegler, T. M., Jr. & Hammond, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Beryllium

Description: The information concerning beryllium assembled herein has been selected primarily to provide information that might be pertinent to the design of the ART. The creep-rupture data in the literature have been obtained from vacuum cast and extruded beryllium, rather than from the hot-pressed beryllium which will be used in the ART. A research program is being conducted by the Brush Beryllium Company, under contract to the Oak Ridge National Laboratory, which will eventually provide the design engi… more
Date: March 21, 1957
Creator: Whitman, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bibliography of ORNL-BSF Reports Pertinent to Swimming Pool Type Reactor Design (Revised)

Description: Much of the shielding work carried out with the Bulk Shielding Reactor (BSR) has yielded data of particular interest for the design of swimming pool type reactors, However, it is often difficult for a reactor designer to locate such data since it may be recorded in a report primarily concerned with shielding problems. Therefore, this memorandum presents a bibliography of reports from the Bulk Shielding Facility arranged according to the application of data to the various aspects of reactor desi… more
Date: April 13, 1956
Creator: Maienschein, F. C. & Johnson, E. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Biology Division Semiannual Progress Report for Period Ending February 15, 1956

Description: Progress report of the Oak Ridge National Laboratory Biology Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the division and departmental activities in cytology and genetics, mammalian genetics and development, microbial protection and recovery, mammalian recovery, pathology and physiology, general physiology, biochemistry, enzymology and photosynthesis, microbiology, plant biochemistry, and biophysics.
Date: April 20, 1956
Creator: Hollaender, Alexander & Carson, Stanley F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Biology Progress Report for Period Ending August 15, 1955

Description: Progress report of the Oak Ridge National Laboratory Biology Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the division and departmental activities in: cytology and genetics, microbial protection and recovery, mammalian recovery, mammalian genetics and development, pathology and physiology, microbiology, biochemistry, enzymology and photosynthesis, plant biochemistry, general physiology, and biophysics.
Date: December 12, 1955
Creator: Hollaender, Alexander; Carson, Stanley F. & Sleughter, E. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bremsstrahlung Absorption Measurements from Sr^90 TiO3

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of … more
Date: May 25, 1959
Creator: Alexander, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bulk ThO2, a Reactor Material

Description: Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processin… more
Date: May 24, 1956
Creator: Johnson, J. R. & Warde, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Shield Induced Gamma Radiation Escaping Through Openings in a Biological Shield -- Application to the HRT

Description: A method was developed for calculating shield induced gamma radiation escaping through openings in a biological shield. The method was applied to the HRT and the results indicated that the contribution to the dose from induced activity in the HRT shield was around 0.1 r/hr and was insignificant in comparison to to other mechanisms contributing to the escape of gamma rays through shield openings.
Date: January 11, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Transport Cross Sections

Description: Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Wall-Scattered Gamma Radiation Escaping through a Shield Opening - Application to the HRT

Description: A simplified method was developed for calculating wall-scatter gamma radiation escaping through a shield opening. The method was applied to the HRT and the results showed that next to the line of sight contribution, scattering of the wall of the shield opening was the main contribution to the dose at the rear edge of the shield. Design charts were prepared that give the dose as a function of the gamma source location with the reactor cell.
Date: February 19, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculations for Irradiation of Natural UO2-ThO2

Description: Calculations are given for eighteen stainless steel clad helium bonded specimens of UO2-ThO2 containing normal U to be placed in 6 holes in a holder in a position of the ORR not to exceed a peak unperturbed flux of 4 x 10^14 n.cm^2/sec and irradiated to a peak nvt of 1.96 x 10^21 neutrons/cm^2
Date: June 8, 1959
Creator: Ullmann, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Capillary Flowmeter

Description: The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method… more
Date: February 20, 1957
Creator: Hise, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbon Steel in High Temperature Water

Description: Resistance of carbon steel to corrosion in oxygenated high-temperature (250C) water was unexpectedly good at high oxygen concentration. Pertinent literature, critically examined, and toroid experiments indicted that at low oxygen concentration attack did increase with concentration, but as oxygen concentration was sufficiently increased, more protective films were formed on the metal. Some corrosion factors in the application of carbon steel to nuclear reactors systems are discussed.
Date: January 31, 1957
Creator: Moore, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries

Description: Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date: January 29, 1957
Creator: Morse, L. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems

Description: A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date: June 5, 1957
Creator: McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report August 1959

Description: Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date: September 8, 1959
Creator: Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report July 1959

Description: Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Progress Report for December 1960 and January 1961

Description: Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nit… more
Date: June 2, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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