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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 facilitated by the fact that all employees affected had personnel dosimeters in their possession when the incident occurred. The interpretation of the data supplied by these dosimeters was supplemented by information gathered by techniques that were developed in connection with other accidents. Below, the available information is first presented and then applied in a discussion of the dosimetry of the people involved in the accident.
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
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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 designed that graphite contraction was recognized as a threat to stack life. Under the present operating conditions, contraction is largely dependent upon neutron flux levels. To date, this study has been largely concerned with the K Reactors, since the vast bulk of the distortion data available is from the Ks. This study not only attempts to explain the mechanisms by which the K Reactors arrived at their present state of distortion but also provides a basis for forecasting future distortion. An understanding of the nature and magnitude of the forces at work within the stacks will enhance the possibility of devising means of conteracting the present trends.
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 contaminating the cesium with oxygen (or water) was observed to increase cesium wettability. (auth)
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. (N.W.R.)
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, but the full implications asscciated with any change in pressure differential must be understood before adopting the above flow rate. (auth)
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 its sleeve, it is concluded that the thermocouple will have to be bonded to the sleeve for dependable reading of true sleeve temperature. Drawings of the heater assembly and thermocouple are given. (D. L. C.)
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 prod- C, and furnace cooled. Room- and elevated-temperature hardness measurements were used to estimate the tensile strengths of the alloys, while corrosion resistance was evaluated by 1000-hr exposures to static 300 ction prod- C water. (auth)
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 allovs and unalloyed niobium was broken known by- forging ingots (protected from oxidation by molybdenum ciins) at 2550 deg F and rolling at 800 deg F. After the initiai breakdown of the cast structure, the alloy-s were coid roiied to a total of 95 per cent reduction with no difficulty .A second fabrication technique was employed for a second set of alloys. Unalloyed niobium and 1.29 wt. % chromium, 2.74 wt. 3 zirconium, 4.5 wt.% molybdenum, and 10 wt. % titanium-3 wt.% chromium alloys were forged and rolled at 1000 deg F to break down the cast structure and then cold rolled to 0.030-in. sheet. the sheet obtained by this technique showed moderate edge cracking. Tensite tests on the coid-worked materiais at 1200 and 1470 deg F indicate that chromium and zirconium.ire both potent strengtheners of niobium: the 1.84 wt.% chromium alloy- hiid a 0.2 per cent offset yield strength of 107,000 psi at 1200 deg F and 69,000 psi at 1470 deg F, and the 4.33 wt. % zirconium alloy had a 0.2 per cent offset yield strength of 69,000 psi at 1470 deg F. Limited welding studies indicate that strong and reasonably ductlle welds can be produced both by arc and spot welding. (auth)
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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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 fire hazard. These include minimizing of the in-core residence time of a fuel element with a cladding defect which permits uranium corrosion, employment of removal and discharge techniques which do not contribute to the deterioration of the fuel element, and minimizing of the time interval between discharge and entry into the retention basin. (J.R.D.)
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 of the gas are monitored continuously. The operating procedure and data are presented for a typical heating experiment in which fused uranium dioxide was studied. (auth)
Date: July 22, 1960
Creator: Barnes, R. H. & Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
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