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Reverse Osmosis for Water Desalination

Description: Report issued by the Office of Saline Water over studies conducted on the reverse-osmosis program. The methods of desalination through osmosis are discussed. This report includes tables, illustrations, and photographs.
Date: May 22, 1964
Creator: Lonsdale, H. K.; Merten, U.; Riley, R. L.; Vos, K. D. & Westmoreland, J. C.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Quarterly Progress Report: July 1960

Description: Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: December 22, 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Pyrophoricity of Uranium in Reactor Environments

Description: Report discussing information relative to the pyrophoricity of uranium for the purpose of reactor core fire safety. The report includes physical and chemical properties of uranium.
Date: January 22, 1960
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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Dosimetry investigation of the recuplex accident

Description: At 10:59 AM (PST), Saturday, April 7, 1962 a criticality accident occurred in a plutonium waste chemical recovery facility at the Hanford Atomic Products Operation, operated for the Atomic Energy Commission by the General Electric Company. Four men were hospitalized but were released after medical observation and after estimates of the radiation doses received were available. This report describes the dosimetry investigation that was made following the accident. This investigation was facilitat… more
Date: August 22, 1962
Creator: Roesch, W. C.; Gamertsfelder, C. C.; Larson, H. V.; Watson, E. C. & Nielsen, J. M.
Partner: UNT Libraries Government Documents Department
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Pike event - EG&G report

Description: Pre event data and post event data are provided for aerial radiological monitoring associated with the Pike Event, which was reported to have resulted in an immediate venting.
Date: June 22, 1964
Partner: UNT Libraries Government Documents Department
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Tory II-C off-design performance

Description: This memorandum reports the performance of TORY II-C at off-design altitudes and Mach numbers. Inlet pressure recovery has been varied with Mach number, reasonable values for a real inlet having been chosen. Nozzle throat area and exit area have been fixed at the design values. Hence this study can be used, in conjunction with missile drag data, to construct a flight envelope.
Date: April 22, 1963
Creator: Moyer, J. H.
Partner: UNT Libraries Government Documents Department
open access

K Reactor moderator distortion study

Description: Irradiation-induced moderator distortion has plagued the Hanford reactors from their earliest days until the present. The first-manifestation of graphite distortion was in the form of expansion of the B, D and F stacks. It was found that expansion was very temperature-dependent and could be reversed by raising the graphite operating temperature. The DR, H, C and K Reactors were designed with provisions to minimize, or accommodate expansion. It was not until after the K Reactors had been designe… more
Date: June 22, 1964
Creator: Alexander, W.K. & Russell, A.
Partner: UNT Libraries Government Documents Department
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Stress-Dependent Interactions Between Cesium and Other Materials. Summary Report, February 15, 1962-February 15, 1963

Description: Metals and alloys germane to thermionic energy converter usage were screened for embrittlement by liquid cesium. Techniques are described for more detailed studies of ceramics and susceptible metals. Definite reductions in tensile ductility were observed for 302 stainless steel and molybdenum. Bend ductility was lowered in titanium, titanium-8 aluminum-4 vanadium alloy, niobium, tantalum, and silver-- copper eutectic solder. Some difficulty in reproducibly wetting samples was evident. Slightly … more
Date: March 22, 1963
Creator: Levinson, D. W.
Partner: UNT Libraries Government Documents Department
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SODIUM-HEATED STEAM GENERATOR DEVELOPMENT. Interim Status Report

Description: Design and development of a once -through sodiumheated steam generator are discussed. Research proposals are discussed for evaluating: carbon transfer and mass transfer effects in the steam generator, effect on heat transfer and two- phase flow of coiling tubes, corrosion of Croloy 21/4 in products of sodium-water reactions, procedure for welding tube to back side of the tube sheet, radiographic inspection of back side tube welds, and chemical simulation of sodium environment for leak testing. … more
Date: January 22, 1964
Partner: UNT Libraries Government Documents Department
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An Investigation of the Structural Integrity of Selected Components of the Oak Ridge Research Reactor

Description: An investigation was made to determine the structural behavior of selected components of the Oak Ridge Research Reactor for increased power level conditions. It was found that a reactor cooling water outlet temperature of 150 deg F will cause severe plastic strain cycling in the aluminum housings for the large test facilities. Increasing the reactor cooling water flow rate of 21,000 gpm will cause plastic deformations in certain reaons of the core box. These latter deformations can be tolerated… more
Date: July 22, 1960
Creator: Corum, J M; Greenstreet, B L; Maxwell, R L & Rosenthal, M W
Partner: UNT Libraries Government Documents Department
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PERTURBATION TECHNIQUES FOR THE DEFLECTING MODE

Description: The perturbation metheds used to obtain a relative plot of the electric field and the value of R/Q are described. A method involving radial pulling of dielectric and metallic beads is proposed for the R/Q measurement. The experimental data are shown to agree with the previously presented theoretical predictions. (D.C.W.)
Date: August 22, 1963
Creator: Hahn, H. & Halama, H.J.
Partner: UNT Libraries Government Documents Department
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PERIODIC RADIATION SURVEY OF REACTOR PLANT CONTAINER AND COMPONENTS AFTER SHUTDOWN. CORE I, SEED I. SECTION 3. Test Results (T-612076)

Description: The effect of isolation and forced draining on the radiation level of the 1AC coolant purification hairpin loop was investigated. The activity in the horizontal and vertical legs (U-bend) of the loop piping was determined by a radiochemical analysis of the crud deposits. (C.J.G.)
Date: May 22, 1960
Partner: UNT Libraries Government Documents Department
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Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and … more
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE USE OF COAGULANT AIDS IN THE LIME-SODA TREATMENT OF LARGE- VOLUME, LOW-LEVEL RADIOACTIVE LIQUID WASTE

Description: Studies on the use of coagulant aids in the lime-soda treatment of large- volume, low-level radioactive liquid waste revealed that a combination of Hagan Aids No. 50 and No. 18 gave fairly good results under most conditions. The effects of feed solution concentrations, mode and point of addition, and water temperature were studied. (C.J.G.)
Date: August 22, 1960
Creator: Subbaratnam, T; Cowser, K E & Struxness, E G
Partner: UNT Libraries Government Documents Department
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Development of High-Strength Corrosion-Resistant Zirconium Alloys

Description: Approximately 100 ternary and quaternary spongezirconium alloys were screened for structural and cladding applications in a natural-uranium-fueled heavy-watermolerated power reactor. The alloy additions studied included2 to 4 wt.% Sn, 0.5 to 2 wt.% Mo, and 1 to 3 wt.% Nb. The effect of 0.1 wt.% Fe and 0.05 wt.% Ni additions to the experimental alloys was evaluated. All compositions were are melted, rolled at 850 ction prod- C from a helium- atmosphere furnace, vacuum annealed 4 hr at 700 ction … more
Date: February 22, 1960
Creator: De Mastry, J. A.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF HIGH-STRENGTH NIOBIUM ALLOYS FOR ELEVATED-TEMPERATURE APPLICATIONS

Description: A study to improve the elevated-temperature strength of niobium by solloving has resulted not only- in greatly improved strengths at 1200 and 1470 deg F but also in the development of improved fabrication techniques for these alloys. The most important step in the fabric:ition procedure of niobium and niobium-base allows is the initial breakdown of the cast structure. The cast structure of 1.84 wt. 4 chromium, 3.21 wt.% chromium. 4.33 wt. ' zirconium, and 20.5 wt.% titanium-4.28 wt. = chromium … more
Date: February 22, 1960
Creator: De Mastry, J. A.; Shober, F. R. & Dickerson, R. F.
Partner: UNT Libraries Government Documents Department
open access

PYROPHORICITY OF URANIUM IN REACTOR ENVIRONMENTS

Description: Current information relative to the pyrophoricity of uranium is reviewed and aspects of this troublesome phenomenon which can support further investigation are considered. Information on metallic uranium fuel element fires, up to the present, provide an inadequate base for extrapolation to future operations because of existing uncertainty with respect to causative mechanisms and fire control techniques. Experience at Hanford reactors indicates conditions which tend to reduce the fuel element fi… more
Date: January 22, 1960
Creator: Zima, G.E.
Partner: UNT Libraries Government Documents Department
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Apparatus for the Study of Fission-Gas Release From Fuels During Postirradiation Heating at Temperatures Up to 1600 C

Description: An apparatus to study rare-gas fission-product release from nuclear fuel materials during postirradiation heating was developed. Xenon and krypton fission gases escaping from a small specimen during heating at constant temperature are measured using a continuous radioactivity monitor and charcoal adsorption traps. The rhodium-wound furnace is capable of operation at 1600 deg C. Helium carrier gas is purified by activated alumina, copper, and zirconium traps, and the oxygen and moisture contents… more
Date: July 22, 1960
Creator: Barnes, R. H. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
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