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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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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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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
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River Soundings. Test Results

Description: 1960. 6p. OTS. Depth measurements were performed in the Screenhouse intake channel and in the Ohio River in the vicinity of the Shippingport PWR Screenhouse. The need for dredging was established. (C.J.G.)
Date: June 22, 1960
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
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Radiative Heat Transfer in Multisurfaced Non-Black Enclosures With Application to the Egcr Fuel Bundle

Description: In an investigation of the detailed temperature structure of the seven- element cluster of cylinders surrounded by a sleeve which comprise the fuel assembly for the EGCR, the radiative interchange of heat between the rods and sleeve was evaluated. A procedure advocated by Hottel was used to determine the view factors for gray enclosures taking into account the multiplicity of reflections, absorptions, and secondary radiations. (auth)
Date: July 22, 1960
Creator: Epel, L. G.
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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AEC Group Shelter

Description: As a result of atomic shelter tests and field experiments condueted over the past nine years, it has been conclusively shown that shelters provide the only promising means of civilian protection in the event of a nuclear war. Design details are presented for a group shelter to accommodate 100 persons of all age groups and both sexes. The shelter structure is a multiplate corrugated- steel arch set on a concrete slab with end walls of bridge plate sheathing. The entire structure is covered with … more
Date: June 22, 1960
Partner: UNT Libraries Government Documents Department
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A CORROSION STUDY OF WELDED STAINLESS STEEL FUEL ELEMENTS

Description: Fuel element corrosion studies designed to and in selecting and evaluating SM-2 fuel element welding techniques are discussed. Tests on type 347 ss plate type fuel elements welded by the selected tungsten inert gas technique showed good corrosion integrity of specimens under a variety of conditions including a 500-hr test under simulated SM-2 conditions of flow and coolant chemistry. (auth)
Date: December 22, 1960
Creator: Bergen, C. R.
Partner: UNT Libraries Government Documents Department
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Current status -- Second generation process tube internal corrosion

Description: Seven water leaks during the past year because of internal corrosion of second generation process tubes have emphasized the need for additional corrosion information. Numerous out-of-pile and probolog examinations have been made to determine the nature of the corrosion, and mixer fuel elements currently are charged in central zone tubes in order to reduce the corrosion rates. This document presents the data obtained to date as a general description of the tube condition at the time when the mix… more
Date: June 22, 1960
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department, monthly record report, February, 1960

Description: This document details activities of the irradiation processing department at the Hanford Reservation during the month of February, 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operation; Manufacturing Operation; Facilities Engineering Operation; Relations Practices Operation; Financial Operation; and NPR operation.
Date: March 22, 1960
Partner: UNT Libraries Government Documents Department
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Piping changes for increased production at B, D, DR, F, C, and H reactors

Description: This study proposes improvements in the process water piping adjacent to the front and rear faces of these reactors. This report covers the external piping of the reactors from the incoming valve pit to the inlets of the outgoing retention basins.
Date: January 22, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Semi-final report (report No. 3) E-N load conversion ratios

Description: Experimental data on plutonium yield and U{sup 235} burnout are now available on the E metal portion of three central zone striped E-N columns and one fringe blanket E column. These data and an overall E-N load conversion ratio based on experimental data are now reported.
Date: December 22, 1960
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Proposed solid state diffusion bonding (SSDB) process: Gas pressure bonding

Description: This report presents a technical and economic study of the lead-dip canning process compared to two types of solid state diffusion bonding processes (hot-press die and gas pressure bonding) for Hanford production fuel elements (exclusive of NPR). It is concluded that either bonding process has potential advantages over the lead-dip process. The gas pressure bonding process has advantages over the hot-press die process.
Date: June 22, 1960
Creator: Weakley, E. A.
Partner: UNT Libraries Government Documents Department
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