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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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THE RECOVERY OF MECHANICALLY ENTRAPPED PLUTONIUM FROM CASTING SKULLS AND TURNINGS

Description: The small critical mass of plutonium which limits charge size, coupled with its value necessithting quantitative recovery from all residues, makes the direct recovery of mechanically entrapped plutonium from casting skulls and oxidized turnings an economic necessity. The newest method used at the Los Alamos Scientific Laboratory for the direct recovery of entrapped plutonium involves mechanical stirring and vibration of the plutonium melt to physically break up to spongy skull and oxide film, t… more
Date: November 22, 1963
Creator: Harbur, D.R.; Romero, J.W. & Anderson, J.W.
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Quarterly Progress Report: June 1960

Description: Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission g… more
Date: August 22, 1960
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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THE SNAP II POWER CONVERSION SYSTEM. Topical Report No. 6, Bearing Design and Development

Description: A preliminary analysis conducted on various types of bearings indicated that hydrodynamic type journal and thrust bearings lubricated with a portion of the mercury from the condensate return pump would best suit the SNAP II requirements. Experimental rssults confirmed the bearing design approach. Stable bearing operation was obtained at speeds in excess of the 40,000 rpm design objective with simulated loads of 1 to 10 g in the radial direction, and 0 to 2 g in the axial direction. Total power … more
Date: June 22, 1960
Creator: Waldron, W.D.
Partner: UNT Libraries Government Documents Department
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Purex Pulse Column Studies-1960

Description: A series of pilot plant runs was conducted to define new cartridges for increasing the capacity in the Purex 1 Bx, 2A, lC and 2E columns and eliminate plastic cartridge failures in the HA column scrub section, the HS column and the 2A column. The most favorable designs are presented and data from the various runs are included. (J.R.D.)
Date: February 22, 1961
Creator: Jansen, G. & Richardson, G.L.
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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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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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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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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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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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
open access

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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