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Dispersions of Uranium Carbides in Aluminum Plate-Type Research Reactor Fuel Elements

Description: The technical feasibility of employing uranium carbide aluminun dispersions in aluminum-base research reactor fuel elements was investigated This study was motivated by the need to obtain higher uranium loadings in these fuel elements. Although toe MTR-type unit, containing a 13 18 wt% U-Al alloy is a proven reactor component, fabrication problems of considerable magnitude arise when attempts are made to increase the uranium investment in the alloy to more than 25 wt.%. Au approach to these fab… more
Date: November 19, 1959
Creator: Thurber, W. C. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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On the Dynamic Design of Non-Regenerative Transistor Circuits : Report No. 94

Description: In this technical report, firstly, the transfer function of a non-regenerative, base-driven transistor circuit is derived by applying the linear equivalent circuit method. The results are experimentally verified. Secondly, the idea of the inverse-gain-bandwidth is introduced as the criterion of the dynamic design. Thirdly, the stability factor is explained. Finally, it is shown that a system constructed by various types of transistor switching circuits is reduced to a long train of unit chains … more
Date: November 19, 1959
Creator: Kunihiro, Toshiro
Partner: UNT Libraries Government Documents Department
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THERMODYNAMICS IN THE FUSED SALT DISSOLUTION PROCESS FOR ZIRCONIUM FUEL

Description: A discussion is given of the role of thermodynamics in the fused-salt volatility process, particularly as it applies to oxidation-reduction reactions affecting zirconium, uranium, nickel, chromium, ruthenium, and other elements present in the hydrofluorination head-end step. (auth)
Date: November 19, 1959
Creator: Cathers, G.I.
Partner: UNT Libraries Government Documents Department
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Accuracy of Volume Measurements in a Large Process Vessel

Description: The Non-Production Fuel Reprocessing Program involves the chemical processing of valuable reactor fuels received from privately owned power reactors. It is necessary therefore, to accurately measure the fuel material received in order to insure proper payment to reactor operator and to provide the Atomic Energy Commission with appropriate accountability data. The volume measurement study described herein was conducted in order to determine the limits of accuracy that could be obtained in measur… more
Date: October 19, 1959
Creator: Pleasance, C. L.
Partner: UNT Libraries Government Documents Department
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PLUTONIUM OXALATE DISK FILTER AND FILTER MEDIA STUDIES

Description: for filtration of plutonium oxalate slurries. A scalpel produces a slit in the filter precoat, leading to increased filtration in this slit, and the oxalate is removed by a doctor knife; this technique results in prolonged blowback cycles and more uniform delivery of filtered oxalate to subsequent processing steps. Several types of filter media were tested, and rigid porous aluminum oxide was found to be the best one. (D.L.C.)
Date: October 19, 1959
Creator: Rey, G.
Partner: UNT Libraries Government Documents Department
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Plutonium Oxalate Disk Filter and Filter Media Studies

Description: Presently rotary drum filters are being used for plutonium oxalate slurry filtration in the 234-5 Building. Changing of the filter cloth used on a rotary drum is a time consuming operation which involves ever increasing radiation exposure to maintenance personnel. Consequently, studies were conducted in the 321 Building on a disk type filter which could be adapted for simple and quick ("one-nut") replacement of the filter medium.
Date: October 19, 1959
Creator: Rey, George
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of KER-1-3 seven rod cluster fuel elements (RM-277)

Description: Two coextruded, Zr-2 clad, natural uranium, seven rod cluster fuel elements were irradiated to a calculated exposure of 1250 MWD/T in the KER Facility and discharged 1-16-59. The fuel elements were NPR candidate fuel and examination was requested to determine the behavior of coextruded, Zr-2 clad, natural uranium irradiated at core temperatures of approximtely 425{degree}C. The elements were transferred to the Radiometallurgy Laboratory 2-25-59. The elements demonstrated excellent in reactor pe… more
Date: October 19, 1959
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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A Rotating Source for Calibration Purposes

Description: This paper discusses a remotely operated system developed to transport (raise and lower) a 1/2 gram radium gamma radiation source for calibration of the HAPO film badges and finger rings. The system employs the rotometer principle for positioning the source for operating purposes. An accurate timer is utilized to assure the desired exposure time.
Date: October 19, 1959
Creator: Kocher, L. F.
Partner: UNT Libraries Government Documents Department
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Supplement C to Production Test IP-250-A, Irradiation of Zircaloy-2 jacketed tube and tube elements in the KER loop

Description: The objective of this Supplement described in this report to Pt-IP-250-A is to d enriched tube-and-tube elements will develop pitting corrosion on the Zircaloy-2 jackets when irradiated in pH 10 water. The measurement of dimensional changes in the fuel elements and the observation of the effect of irradiation on the uranium and bond area are also objectives of the test, but secondary in importance to identifying a pitting corrosion problem in NPR quality water, if one exists.
Date: October 19, 1959
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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TRANSIENT TESTS OF HNPF PROTOTYPE SODIUM PUMP DRIVES

Description: The objectives of this study were to demonstrate that the pump speed control system will respond as defined in the equipment specifications and to determine optimum values of controlling variables that will minimize the oscillations that occur in the Na flow rate when transient signals are imposed on the pump speed control system. (W.L.H.)
Date: October 19, 1959
Creator: Atz, R. W.
Partner: UNT Libraries Government Documents Department
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A VISUAL STUDY OF THE CORROSION OF DEFECTED ZIRCALOY-2-CLAD FUEL SPECIMENS BY HOT WATER

Description: The failure of defected Zircaloy-2-clad uranium and uranium -2 wt.% zircorium fuel specimens in high-purity high-pressure water at 200 to 345 deg C was observed in a windowed antcclave. Time-lapse color motion pictures were taken to provide a record of the progressive changes ending in the complete disintegration of the core material in the specimens. Continuous measurement of the pressure increase caused by accumulation of hydrogen served to monitor the progress of the reaction when clouding o… more
Date: October 19, 1959
Creator: Stephan, Elmer F.; Miller, Paul D. & Fink, Frederick W.
Partner: UNT Libraries Government Documents Department
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HNPF PROCESS TUBE-GRID SEAL

Description: A maximum leak rate of 0.08% was measured for a piston ring seal assembly which was evaluated for use as the Hallain Power Reactor process tube- grid plate seal. A maximum leak rate of 0.14% was observed after subjection to 10,000 cycles (560 hr) in 625 deg F Na. The maximum leak rate was 0.07% after 25 cycle exposure in 1000' Na. Vertical scoring of both the rings and bore tube was observed. Sodium was observed to remain behind the rings after washing. (C.J.G.)
Date: August 19, 1959
Creator: Charles, J.
Partner: UNT Libraries Government Documents Department
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Design and Evaluation of HAPO Canned Motor

Description: The transfer or circulation of raw dissolver solutions containing gross particulate matter presents many problems not easily overcome by standard pumping equipment. In April of 1956 the HAPO concept of a modified Archimedes screw pump was developed. Two basic models, externally powered and driven through extended shafts, were constructed and tested. Operation of these preliminary models was so satisfactory that a third unit, integrally formed into drive motor, was built and placed in extended … more
Date: June 19, 1959
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department
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Neutron flux in K Reactor discharge area during operation

Description: Based on the activation of gold foils in an hydrogeneous medium, the neutron flux incident on the rear wall of the discharge area of the KE reactor is estimated to be 6000 M/cm{sup 2} sec. The effective energy of the neutrons is estimated to be approximately 4 Mev. Neither of these values confirm order-of-magnitude estimates of the neutron flux and neutron energy expected to exist in the discharge area.
Date: June 19, 1959
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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POWER REACTOR FUEL REPROCESSING PROCESS WASTES

Description: Data on waste volumes and heat generation of several reactor fuels which may be reprocessed in the Power Reactor Fuel Reprocessing Pilot Plant at ORNL are tabulated. (auth) l6876 A tabulation containing information on the power of existing and proposed U. S. and U. S.-built reactors of 10 kw or greater thermal power is presented. Estimated fuel reprocessing loads for irradiated fuels are also iucluded. (auth)
Date: June 19, 1959
Creator: Conger, W L
Partner: UNT Libraries Government Documents Department
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Power Reactor Fuel Reprocessing Process Wastes

Description: Data on waste volumes and heat generation of several reactor fuels which may be reprocessed in the Power Reactor Fuel Reprocessing Pilot Plant at ORNL are tabulated.
Date: June 19, 1959
Creator: Irvine, A. R.
Partner: UNT Libraries Government Documents Department
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Theoretical Study of Single-Transfer Line Concatenated Pulse Column Systems

Description: Calculations indicate that single-transfer line concatenated pulse column systems can be operated with static pressures that are not excessive if a sufficient number of vessels are employed in the system. The required number of vessels can be attained by using a series of short columns or by using holdup pots in conjunction with a limited number of columns.
Date: June 19, 1959
Creator: Johnson, H. F.
Partner: UNT Libraries Government Documents Department
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THEORETICAL STUDY OF SINGLE-TRANSFER LINE CONCATENATED PULSE DOLUMN SYSTEMS

Description: Calculations indicate that single-transfer line concatenated pulse column systems can be operated with static pressures that are not excessive if a sufficient number of vessels are employed in the system. The required number of vessels can be attained by using a series of short columns or by using holdup pots in conjunction with a limited number of columns. General equations for calculating pressure drops and power requirements are presented. (auth)
Date: June 19, 1959
Creator: Johnson, H F
Partner: UNT Libraries Government Documents Department
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Description of Purex Plant Process

Description: Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date: May 19, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department
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Determination of Thickness of Oxide Film on Phosphor Bronze

Description: The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between the two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of film, and surface area of film. A value of 1080 A was calculated as the thickness by t… more
Date: May 19, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Determination of Thickness of Oxide Film on Phosphor Bronze

Description: The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between these two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of the film, and surface area of film. A value of 1080 A was calculated as the thicknes… more
Date: May 19, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Fission Project Yield of Inert Gases

Description: The final percentage of xenon created by fission in uranium and plutonium is a function of the neutron flux intensity. The flux dependence results because axenon 133 and 135 can be converted to a a stable xenon isotope by neutron capture instead of decaying into cesium.
Date: May 19, 1959
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
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Historical record of data on flood control

Description: Last year (1948) during the flood period the flow at Grand Coulee fluctuated widely. 2 PM, June 8, 543000 c.f.s.; 4 AM, June 9, 568000 c.f s.; 2 PM, June 9, 543000 c.f.s.; 2 AM, June 10, 573000 c.f.s. A total instantaneous fluctuations of 37,500 c.f.s. was reported. Now there is installed a new control. This control can keep downstream variation within 500 c.f.s. By lowering the lake level prior to the crest period, the drum gates could be used as flood control (1948 high water basis) the drum … more
Date: May 19, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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