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Solid State Division Semiannual Progress Report for Period Ending August 30, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Solid State Division during 1956. Descriptions of progress and studies made are presented. This report includes tables, illustrations, and photographs.
Date: December 17, 1956
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Interim Report on Corrosion by Zirconium-Base Fluorides

Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
Partner: UNT Libraries Government Documents Department
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A New Anionic Solvent Extraction Technique

Description: From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
Partner: UNT Libraries Government Documents Department
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Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Partner: UNT Libraries Government Documents Department
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The Isolation and Purification of Americium

Description: Gram amounts of americium were separated quantitatively from kilogram quantities of lanthanum to yield an americium product approaching 90% purity. The remaining impurity was chiefly yttrium. Elution of americium from 25% loaded Dowex 50 resin column with 0.15 M citric acid— 0.10 M diammonium citrate — 0.3 M ammonium nitrate, pH 3.3 gave a product containing 99% of the americium with a La/Am ratio of 1/100 or less in one fourth of a column volume, in this case about 1 100-fold volume reduction.… more
Date: April 17, 1956
Creator: Campbell, D. O.
Partner: UNT Libraries Government Documents Department
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Development of the Excer Process

Description: Two revised Excer process flowsheets are presented for the production of UF4 from urnayl nitrate solution. In both, the uranium is sorbed on a cation-exchange resin and eluted with aqueous HF. In one, the resulting UO2F2 in dilute HF is mixed with dilute sulfuric or hydrochloric acid and electrolytically reduced in a cation-exchange-membrane cell, and the precipitated UF4·0.75H2O is dried and dehydrated to anhydrous UF4. A cost of 20¢ per pound of reduced uranium is estimated. In the other, amm… more
Date: April 17, 1956
Creator: Marinsky, J. A.
Partner: UNT Libraries Government Documents Department
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Air Scattering of Co60 Gamma Rays: Theory Versus Experiment

Description: For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Date: April 17, 1958
Creator: Moran, Rubert S.
Partner: UNT Libraries Government Documents Department
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Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure

Description: Few data exist for the thermal conductivity and viscosity of gases at very high pressure. The possibility of using gases for heat transfer media at pressures up to 100 atmospheres and above raised the problem of estimating variations in the conductivity and viscosity at high pressure. Generalized plots are presented which are based on the work of Enskog, Eucken, and Hirschfelder et al. Some pertinent data from Hirschfelder et al and from Hilsenrath et al are presented.
Date: January 17, 1957
Creator: Lyon, Richard Norton
Partner: UNT Libraries Government Documents Department
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The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

Description: The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
Partner: UNT Libraries Government Documents Department
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HRT Temperature Measurement System - Issue No. 3

Description: The following temperature measurement tabulation consists of two parts. Part I lists all HRT thermocouples, their location, the junction box thru which the leads pass, and their termination, if on an instrument. Part II lists all temperature read out instruments and their location. A total of 577 thermocouples are listed in this tabulation. The roughly 77,000 ft of wire used in connecting them up cost $6,799. Temperatures are read on 24 instruments. Cost of these was approximately $15,688. Acce… more
Date: January 17, 1957
Creator: Grimes, J. D.
Partner: UNT Libraries Government Documents Department
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Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957

Description: The HRT mockup was shut down February 16, 1957 after operating for 576 hours on high concentration uranyl sulfate. At this time, all corrosion samples in the system were removed and replaced, and the wire extending thought the letdown hear exchanger was removed of examination.
Date: June 17, 1957
Creator: Wacker, R. E. & Griese, J. C.
Partner: UNT Libraries Government Documents Department
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The Relationship of Aqueous ThO2 Slurry Physical Properties of the Engineering Design of a Reactor System

Description: In a reactor system the principal components affect by slurry properties are the blanket vessel, pressurizer, heat exchanger, and dump tant. The particular properties that affect the operation of these components are: caking, degree of flocculation, foaming, and slime formation. these properties are related to the characteristics of compounds in a reactor system through experience gained in the operation of slurry loops. It is pointed out that the optimum slurry for one component may not necess… more
Date: June 17, 1957
Creator: Thomas, D. G.
Partner: UNT Libraries Government Documents Department
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Status and Future Program of Homogeneous Reactor Fuel Processing Studies

Description: The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
Partner: UNT Libraries Government Documents Department
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Instantaneous Velocity Profile Measurement by Photography

Description: The following is taken from ORNL-2257, Instantaneous Velocity Profile Measurement by Photography, by R. E. Lynch, L. D. Palmer, and G. M. Winn. This report is in in preparation status; and errors, inconsistances, and omissions in he language, as well as in the technical aspects, may exist. The technique of using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles is covered by AEC Patent Application No. SN-710, 371 issued… more
Date: August 17, 1959
Creator: Lynch, F. E.; Palmer, L. D.; Winn, G. M. & Hoffman, H. W.
Partner: UNT Libraries Government Documents Department
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THOROBRED - An IBM-704 Code for Steady State Nuclear and Economic Calculations of Two=Region Homogeneous Reactors

Description: THOROBRED is an IBM-704 code for the calculation of nuclear and economic characteristics of two-region homogeneous reactors operating on a U-Th fuel cycle in the steady state. The major input variables are reactor dimensions, power level, thorium concentration, chemical and purification systems cycle times, corrosion rates, fraction of Pa loss, and nuclear and economic data. The output includes equilibrium isotope concentrations, neutron balance, and a breakdown of fuel cost. Running times are … more
Date: January 17, 1961
Creator: Jaye, S. & Fowler, T. B.
Partner: UNT Libraries Government Documents Department
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Use of 4Pi High-Pressure Ionization Chambers as Secondary Standards for Calibration of Gamma-Ray Sources

Description: This memorandum is intended to serve as a nearly final draft of a section of a future report on an experiment to determine the spectrum of gamma-rays given off during U-235 fission. For this purpose it is necessary to give adequate details to expose the major bases of the spectrometer calibration in the lower energy regions.
Date: April 17, 1961
Creator: Peelle, R.W.
Partner: UNT Libraries Government Documents Department
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Determination of Suitable Insulation for a 1-5/16" Helium Filled Annulus in the ORR Helium In-Pile Loop, Design No. 4

Description: Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1… more
Date: August 17, 1959
Creator: Knight, R. B. & Helms, R. E.
Partner: UNT Libraries Government Documents Department
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Measurement of the "Active Deposit" of Thoron

Description: A description is given of the properties of the nuclides included in the "active deposit" of thoron. A method is presented for obtaining a quantitative measurement of the activity of the transient-equilibrium mixture.
Date: August 17, 1959
Creator: Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
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Methods for Applying Transmission and n-vs-E Corrections in the Determination of n2200 by the Macklin-deSaussure Experiment

Description: A careful determination of n2200 from results of the Macklin-deSaussure manganese bath experiment involves corrections for (1) the weak but non-zero transmission of sub-cadmium neutrons through the uranium or plutonium foils, and (2) the small variation of n with energy in the sub-cadmium region. This report presents the derivation of a single general expression for applying both these corrections, and then describes two IBM 704 codes (MTC and GTC) which were written especially to facilitate th… more
Date: August 17, 1959
Creator: Halbert, Edith C.; Maskewitz, Betty F. & Wynn, R. L.
Partner: UNT Libraries Government Documents Department
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Solubility of Oxygen in Aqueous Uranyl Sulfate Solutions at Elevated Temperatures and Pressures

Description: Plots of oxygen solubility data are presented. The data are mainly those of Stephen et al, and the plots involve interpolation and extrapolation of those data to cover a temperature range of 210 o 330' C, an oxygen pressure range of 0-2000 psi, and a uranyl sulfate concentration range of 0-300 g U/1.
Date: September 17, 1959
Creator: Davis, R. J.
Partner: UNT Libraries Government Documents Department
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Liquid-Liquid Immiscibility Above 300' C In The System UO3-SO3-N2O5-H2O

Description: Newly developed fused-salt-bath apparatus currently in use for the observation of liquid-liquid immiscibility in solutions sealed in silica tubes is described. Immiscibility temperatures are reported for 0.04, 0.08 and 0.16 molal UO2++ solutions in the system UO3-SO3-N2O5-H2O.
Date: November 17, 1959
Creator: Barton, C. J.; Hebert, G. M. & Marshall, W. L.
Partner: UNT Libraries Government Documents Department
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