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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Description: Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
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Analytical Chemistry Division Quarterly Progress Report for Period Ending September 10, 1951

Description: Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radio-chemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses for the period ending September 10, 1951. Studies and happenings took place on the Analytical Chemistry Division's X-10 … more
Date: February 26, 1952
Creator: Kelley, M. T. & Susano, C. D.
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Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

Description: The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million … more
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
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Chemistry Division Quarterly Progress Report for Period Ending June 30, 1951

Description: Quarterly technical report including reports on chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation of the Chemistry Division of the Oak Ridge National Laboratory (ORNL). [From Abstract]
Date: February 14, 1952
Creator: Lind, S. C.; Boyd, G. E. & Bredig, M. A.
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The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Description: Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
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Determination of Trivalent Uranium in Fluoride Salt Mixtures by the Modified Hydrogen Evolution Method

Description: The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium… more
Date: February 26, 1956
Creator: White, J. C.; Meyer, A. S., Jr.; Vaughan, W. F.; Ross, W. J. & Manning, D. L.
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Development of a Cubic Oxide Protective Film on Zirconium

Description: Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient… more
Date: February 21, 1956
Creator: Johnson, J. R.
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Dynamics of the Supercritical Water Reactor

Description: From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
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Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Description: The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations … more
Date: February 1, 1956
Creator: Powers, W. D. & Blalock, G. C.
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Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Description: From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
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Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
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Homogeneous Reactor Project Quarterly Progress Report: August-October 1956

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 19, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
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Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
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A Low Cost Experimental Neutron Chain Reactor Part 2

Description: Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
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Metallurgy Division Quarterly Progress Report for Period Ending July 31, 1951

Description: Technical report outlining the effect of strain rate on the tensile properties of thorium. It has been found that the yield strength increases slightly with increasing strain rate, and that tensile strength increases but to a less extent. Studies on the fabrication of thorium by extrusion and drawing have continued, as have studies on the extrusion cladding of thorium and uranium with zirconium. [From Summary}
Date: February 6, 1952
Creator: Miller, E. C. & Bridges, W. H.
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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
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Molten-Salt Reactor Program Quarterly Progress Report: October 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.
Date: February 21, 1958
Creator: MacPherson, H. G.
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A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
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