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Advantages of palmolive alternate

Description: It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date: March 17, 1959
Creator: Coppinger, E. A. & Merrill, E. T.
Partner: UNT Libraries Government Documents Department
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Design of Production test IP-243-A-6-FP, evaluation of X-8001 alloy aluminum components fabricated from cast blanks

Description: The objective of this test is to determine the quality and erosion resistance of cape and cans produced from cast X-8001 alloy blanks through fabrication and irradiation of limited quantities in accordance with the testing procedure herein defined. Components which were fabricated from X-8001 alloy cast blanks have been subjected to rigorous out-of-reactor tests and have indicated equivalence or possible superiority to standard X-8001 alloy components. It is, therefore, proposed that; (1) six e… more
Date: March 17, 1959
Creator: Hodgson, W. H. & Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Trapping of Energetic Ions by Neutralization of a Polarized Beam

Description: Recent experiments show that a positive ion beam with a density exceeding 10/sup 8/ ions/cm/sup 3/ will neutralize its space charge by trapping electrons within the beam. This trapping of electrons converts the ion beam to a neutral plasma suitable for injection and polarization experiments in a cross magnetic field. The ion energy used is about 500 volts. The beam moves readily across the magnetic field due to polarization of positive and negative charges. To create a hot plasma, it will be ne… more
Date: March 17, 1959
Creator: Luce, J. S.
Partner: UNT Libraries Government Documents Department
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Bonding of Tantalum

Description: Technical report describing the investigation undertaken to determine the necessary requirements for obtaining sound bonded joints on tantalum. Corrosion and Mass Transfer Loops LTTN 237A and 427 called for fabrication of 430 stainless steel clad tantalum tubing. Since there was little or no experience at welding this material at CANEL, specimens were welded using vacuum chambers and plastic chambers as normally used for loop fabrication. Resistance welding was performed without the use of a … more
Date: June 17, 1959
Creator: Rogers, S. L.
Partner: UNT Libraries Government Documents Department
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Program on the IBM 709 Digital Computer of the P3 Approximation to the Boltzmann Transports equation in Cylindrical Geometry

Description: In formulating this general diffusion theory expression which represents the neutron balance in a nuclear chain reactor the following assumptions were made : (1) the medium through which the neutrons are diffusing has a low neutron capture cross section, (2) the region in which the flux distribute is being described is two or three mean free paths from strong sources and sinks or from a boundary. Certainly, is going to the lattice cell of a receptor, both of the above conditions are violated; f… more
Date: June 17, 1959
Creator: Matsumoto, D. D. & Richey, C. R.
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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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. Rare earth solubility levels and t… more
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
Partner: UNT Libraries Government Documents Department
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Prototype F-F6 demister installation at Purex for the future single-stage recovery of nitric acid from high-level wastes: Definitive design

Description: At present, the Purex Plant employs a two-stage process for the recovery of nitric acid from high-level wastes. This report summarizes the results of a design study on the Phase I installation of a prototype demister (vapor filter) between the E-F6 Concentrator and the T-F5 Acid Absorber. Further, the results of an engineering study are presented on the feasibility of the subsequent Phase II bypassing of the E-F11 Concentrator and auxiliaries to permit single-stage acid recovery, once satisfact… more
Date: July 17, 1959
Creator: Michels, L.R.
Partner: UNT Libraries Government Documents Department
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Recent Developments in Graphite

Description: Developments in the production of various graphite products and data on the properties, outgassing, and radiation resistance of various graphites are reviewed. (C.J.G.)
Date: July 17, 1959
Creator: Kosiba, W. L.
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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Division of Reactor Development Programs Monthly Report- July 1959

Description: Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 … more
Date: August 17, 1959
Creator: McEwen, L.H.
Partner: UNT Libraries Government Documents Department
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Instantaneous Velocity Profile Measurement by Photography

Description: An apparatus is described for using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles in flowing liquids. Phosphor and film data are tabulated, and factors to be considered in analysis ot the photographs are discussed. (J.R.D.)
Date: August 17, 1959
Creator: Hoffman, H. W.
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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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 obtalning a quantitative measurement of the activity of the transient-equilibrium mixture. (auth)
Date: August 17, 1959
Creator: Reynolds, S.A.
Partner: UNT Libraries Government Documents Department
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METHODS FOR APPLYING TRANSMISSION AND /eta/-vs-E CORRECTIONS IN THE DETERMINATION OF /eta/$sub 2200$ BY THE MACKLIN-deSAUSSURE EXPERIMENT

Description: A careful determination of /sub 2200/ from results of the Macklin- deSaussure manganese-bath experiment involves corrections for (1) the weak but nonzero transmission of subcadmium neutrons through the uranium or plutonium foils and (2) the small variation of with energy in the subcadmium region. The derivation of a single general expression for applying both these corrections is presented, and two lBM 704 codes (MTC and GTC) which were written especially to facilitate the numerical evaluation … 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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Plant Modification for Reprocessing Non-Production Reactor Fuels Design Criteria for Fuel Element Storage Facility Building 221-U

Description: Facilities shall be provided in the 221-U Building for removing fuel elements from the casks as placed in the railroad tunnel from the transfer facility and moving the elements to modified existing 10' X 16' X 14' storage tanks in ten existing cells where they will be stored, until scheduled for processing.
Date: August 17, 1959
Creator: Yates, M. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report - October, November, December 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: A number of Pu-Al and UO2-PuO2 Zircaloy clad capsules have been fabricated for irradiation in the MTR. In addition, a four rod cluster containing Al 8 w/o Pu and Al 12 w/o Si 8 w/o Pu cores has been successfully irradiated and discharged from Loop 3 of the KER. A second four rod cluster is awaiting irradiation and design and fabrication of a seven rod cluster test element is underway.
Date: August 17, 1959
Creator: Wick, O.J.
Partner: UNT Libraries Government Documents Department
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Calculation of K reactor flow decay transient

Description: The process water pumping system for the K-reactors consists of six parallel sets of two series-connected pumps. A BPA outage could sever the power to all pumps. It is of major concern to known how the reactor flow decays with time following the power severance. The following analysis gives the general solution of this problem without recourse to the assumptions which have been used heretofore. The solution of the decay problem was programmed on the IBM 709. The program will give the flow trans… more
Date: September 17, 1959
Creator: Massena, W. A.
Partner: UNT Libraries Government Documents Department
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A Study of Complex Ions in Fused Salt Systems. Final Report

Description: Absorption spectrophotometric methods were used in a study of complex ion formation and acid-base reactions in fused chloride and nitrate systems. Several methods for the treatment of spectrophotometric data were investigated. The spectra of various chromium salts were determined in three nitrate melts and in fused lithium chloride-pothssium chloride. In low solute concentrations in LiNO/sub 3/-KNO/sub 3/, NaNC/sub 3/-KNO/sub 3/, and LiCl-KCl melts, the species found was the chromate ion, while… more
Date: September 17, 1959
Creator: Osteryoung, R. A.; VanNorman, J. D. & Christie, J. H.
Partner: UNT Libraries Government Documents Department
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Waste disposal criteria existing reactor expansion study

Description: This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bul… more
Date: November 17, 1959
Creator: Hall, R. B.
Partner: UNT Libraries Government Documents Department
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