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14-Inch Swing Check Valve Test

Description: The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)
Date: February 10, 1960
Creator: Cygan, R.
Partner: UNT Libraries Government Documents Department
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100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
Partner: UNT Libraries Government Documents Department
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Anion Exchange Recovery of Plutonium From Reduction Residues

Description: Technical report. From Abstract: "An anion exchange process was demonstrated for the recovery of plutonium from waste produced in the reduction of plutonium salts to the metal. Plutonium in a highly salted 6M nitric acid solution derived from the dissolution of slag and crucible waste was separated from impurities by absorbing the Pu (IV) nitrate complex on the anion exchange resin and subsequently eluting with nitric acid. A flowsheet for plant operation is presented."
Date: February 1960
Creator: Russell, Edwin R.
Partner: UNT Libraries Government Documents Department
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Anion Exchange Recovery of Plutonium From Reduction Residues

Description: An anion exchange process was demonstrated for the recovery of Pu from waste produced in the reduction of Pu salts to the metal. Pu in a highiy salted 6M nitric acid solution, derived from the dissolution of slag and crucible waste, was separated from impurities by absorbing the Pu(IV) nitrate complex on the anion exchange resin and subsequentiy eluting with dilute nitric acid. A flowsheet for plant operation is presented. (auth)
Date: February 1, 1960
Creator: Russell, E. R.
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 2, Supplement]: Separate Studies

Description: From summary and conclusions: This study has been made to determine the feasibility of installing reheat steam facilities in conjunction with the selected 306-mw boiling water nuclear power plant.
Date: February 1960
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Calculation of Temperature Rise in Deeply Buried Radioactive Cylinders

Description: Temperatures were calculated relative to the storage of radioactive solid waste as a function of time and radial distance for radioactive solid cylinders in infinite solid media of "average soil," "average rock," and salt. A resistance at the cylinder--infinite medium boundary was included in the form of an air space. For the range of parameters used and withia the practical limits of accuracy, the maximum temperature rise increased linearly with the heat generation rate. The fission product spectrum was not significant in the determination of the maximum temperature rise. Under the pessimistic storage conditions assumed, the storage of cylinders of a practical size appears feasible without excessive temperature rise. A maximum temperature rise of 1000 deg F would be produced with an initial heat generation rate of 1300 to 1600 Btu/hr-ft/ sup 3/ for cylinders with a 5-in. radius, with 350 to 450 Btu/hr-ft/sup 3/ for a 10-in. radius, and with 175 to 210 Btu/hr-ft/sup 3/ for a 15-in. radius, assuming a thermal conductivity of the radioactive cylinder of 0. 1 Btu/hr-ft- deg F. (auth)
Date: February 25, 1960
Creator: Perona, J. J. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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The Catalysis of the Hydrogen-Oxygen Reaction by Aqueous Slurries of Thorium Oxide and Thorium-Uranium Oxide

Description: Aqueous slurries of thorium oxide and thorium oxide containing urarium were investigated for their catalytic activity for the reaction of hydrogen and oxygen to form water. Pure thorium oxide. thorium-uranium oxide mixed crystals prepared by calcining coprecipitated oxalates, and thorium oxide with uranium oxide sorbed on the surface were used after calcining at 650, 800, and 1000 deg . The reaction rates were found to be first order with respect to hydrogen pressure and zero order with respect to oxygen pressure in all cases at temperatures from 230 to 300 deg - and total gas pressures from 100 to 2000 psi. For the pure thorium oxide an average activation energy of 41 kcal/mole and an average frequency factor of 4.6 x lO/sup 8/ moles/psi H/sub 2/hr-g of ThO/sub 2/ were found. Addition of uranium lowered both factors, the maximum effect giving a DELTA E/sub a/ of approximately 14 kcal with an A of approximately 10/sup -2/. Actual rates for all catalysts were within one order of magnitude when compared on a unit surface area basis. This compensation effect was explained on the basis of a two-site process, one site being related to the uranium concentration on the catalyst surface and the other characteristic of pure thorium oxide. A few tests on uranium trioxide slurries gave initial fast rates followed by slow ones, the change being accompanied by reduction of the surface uranium under the experimental conditions. The apparent activation energy for both surface conditions was 26 kcal/mole based on first order rate constants with frequency factors of 2.2 x 10/sup 4/ and 2.5 x 10/sup 3/ moles/psi H/sub 2/hr-g for the initial and final rates, respectively. (auth)
Date: February 1, 1960
Creator: Krohn, N. A.
Partner: UNT Libraries Government Documents Department
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CHANGE OF KEWB REACTOR CORES-EVALUATION OF SIGNIFICANCE WITH REGARD TO ASSOCIATED HAZARDS

Description: The KEWB Facility is described, and an over-all technical evaluation is made of the hazards associated with changing from a spherical to a cylindrical core. The characteristics of the two systems, the operation and emergency procedures, a brief history of the program, a summary of the data obtained, and maximum accident analyses are given. The conclusion is that the core change does not represent an adverse change with respect to associated hazards. (T.R.H.)
Date: February 1, 1960
Partner: UNT Libraries Government Documents Department
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CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, DECEMBER 1959

Description: Chemical-Metallurgical Processing. A direct-cycle pyrometallurgical fuel-processing plant is being constructed in conjunction with EBR-II. The gamma- irradiation testing of the 175-watt white fluorescent mercury vapor lamp was continued to an integrated exposure of 2 x 10/sup 9/ rad. Irradiation tests of Shell APL grease were completed, and the estimated useful life of this grease in the Air and Argon Cells is 2 and 3 years, respectively. Tests of the three - types of d-c motors used in the operating manipulator of the Argon Cell indicate an expected useful cell operating life of 2 to 3 years. Continued irradiation tests of mineralinsulated cable show no catastrophic breakdown of the electric insulation even after an accumulated gamma dose of 8.4 x 10/sup 9/ rad. The scheme currently under consideration for processing melt-refining residues involves a reduction of skull oxides by a solution of Mg in liquid Cd. Molten salt fluxes had variable effects on the rate of oxide reduction in dilute Mg systems. Work was continued on development of processes for EBR-II blanket materials. A large-scale metal-distillation unit to demonstrate metal distillation at rates up to 100 kg/hour is under construction. Two medium carbon steel thermal-convection loops were built and operated to ascertain the extent of corrosion under adverse thermal conditions. Data were obtained for the solubilities of V, Fe, and Ni in liquid Cd at temperatures from 400 to 650 deg C. Corrections were made to data on the solubility of Th in liquid Zn. Solubilities of U in Si-free Zn--Mg solutions were found to be significantly higher than when silicon was present. The peritectic temperature in the U--Cd system was found to be 474 plus or minus l deg C. The activity coefficient of U in Al at4.8% U and 686 deg C is estimated to be 1.25 x 10/sup …
Date: February 1, 1960
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for January 1960

Description: Production of Pu nitrate, UO{sub 3}, and unfabricated Pu metal met schedules. Decontamination performance of Purex process continued below standard. The cerium-144 cask is being redesigned. A ``powered ferret``, for driving a scintillation counter through a conduit to monitor ground activity beneath waste storage tanks, is being designed.
Date: February 22, 1960
Partner: UNT Libraries Government Documents Department
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Chemistry Division Semiannual Report June through November1959

Description: High-energy studies of the (p, 2p) reaction in Zn{sup 68} and Fe{sup 57} are being carried out. The excitation functions for the reactions, Zn{sup 68}(p, 2p)Cu{sup 67} and Fe{sup 57} (p, 2p)Mn{sup 56} are being measured from 400 Mev to 6.2 Bev. Preliminary results are shown in Table 1. The cross sections are calculated on the basis of a 10.7-mb cross section for the Al{sup 27} (p, 3pn)Na{sup 24} reaction used to monitor the proton beam. The yield of Mn{sup 52} from proton bombardments of natural iron is found to be approximately constant at 7 mb over the energy region 400 Mev to 4.0 Bev. Similarly, the yields of Cu{sup 61} and Cu{sup 64} from proton bombardment of natural zinc are constant at 17 mb and 13 mb, respectively, over the same energy region. Experiments are being carried out in an attempt to measure the cross section for the reaction Zn{sup 68} ({pi}{sup +}, {pi}{sup +}p)Cu{sup 67}, using 310-Mev {pi}{sup +} produced at the 184-inch cyclotron. The meson beam, which is produced by 720-Mev protons incident on copper, has an intensity of about 10{sup 6} {pi}{sup +} per min over a 3-in.-diameter circle. The total induced activity of Cu{sup 67} from zinc of natural isotopic composition is about 100 cpm as detected by an end-window gas-flow proportional counter. The target thickness is 600 mg/cm{sup 2}, so that the mesons lose only about 5 Mev in passing through the target. Bombardment time is from 8 to 20 hours. Copper-67, half-life 61 hours, has been radiochemically detected, and experiments are being carried out to determine what part of the observed activity is due to the Zn{sup 68} ({pi}{sup +}, {pi}{sup +}p)Cu{sup 67} reaction and what part is due to the interaction of stray or secondary fast neutrons with Zn{sup 67} (4.1% abundant) …
Date: February 8, 1960
Partner: UNT Libraries Government Documents Department
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Circuit Dynamics of the Pinch

Description: The following document aims to analyze the dynamics of a pinch tube, including the reaction back on the energy source.
Date: February 1960
Creator: Killeen, John & Lippmann, B. A.
Partner: UNT Libraries Government Documents Department
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A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958

Description: From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date: February 1960
Creator: Brodsky, Allen & Beard, G. Victor
Partner: UNT Libraries Government Documents Department
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Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
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Description of Facilities and Mechanical Components: Medical Research Reactor (MRR)

Description: Report issued by the Brookhaven National Laboratory discussing the Medical Research Reactor at the Medical Research Center. Design, tests, and operations of the reactor are presented. This report includes tables, illustrations, and photographs.
Date: February 1960
Creator: Godel, Jules B.
Partner: UNT Libraries Government Documents Department
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Design Studies on Cesium-137 as a Source for High Level Gamma Irradiations. Quarterly Progress Report No. 2 Covering the Period From Sept. 1, 1959 to Dec. 1, 1959

Description: Further studies are reported on the analytical behavior and experimental testing of Cs/sup 137/ plaque irradiator designs. Low-level sources used for the initial experiments consisted of about 7 mc of Cs/sup 137/ aqueous solution in brass trays 20 by 20 by 1/2 in. high having wall thicknesses of 1/16 in. Calibration tests were made preliminary to radiation field mapping. (T.R. H.)
Date: February 29, 1960
Creator: Voyvodic, L.
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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