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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, April 1, 1958 to March 31, 1959

Description: This report is the final in a series of preliminary reports that follow the studies of scavenging systems related to radioactive fallout. The project consisted of two phases: preliminary experiments to relate the sizes of particles in air to specific radioisotopes, and preliminary laboratory studies of scavenging of particles by liquid drops, including studies of sticking probability and effects of Brownian motion and water vapor diffusion.
Date: April 30, 1959
Creator: Rosinski, John & Stockham, John D.
Partner: UNT Libraries Government Documents Department
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Solid State Division Quarterly Progress Report: August 1952

Description: This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date: January 30, 1959
Creator: Billington, D. S. (Douglas S.) & Howe, J. T.
Partner: UNT Libraries Government Documents Department
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The Nuclear Ramjet Propulsion System

Description: The following report describes the workings and development of the nuclear ramjet propulsion systems.
Date: June 30, 1959
Creator: Merkle, Theodore C.
Partner: UNT Libraries Government Documents Department
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Thermodynamics of Irreversible Processes: The Experimental Verification of the Onsager Reciprocal Relations

Description: Report discussing theories of irreversible thermodynamic processes. "The purpose of this review is to collect the presently available experimental data for a variety of quite different irreversible phenomena and to show that this evidence does indeed verify the Onsager Reciprocal Relations."
Date: July 30, 1959
Creator: Miller, Donald Gabriel
Partner: UNT Libraries Government Documents Department
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Proposed study program of the effects on Hanford of a dam at Columbia River mile 348

Description: At the request of Hanford Operations Office, Atomic Energy Commission, a study was made of the effects on the Hanford Facilities of a navigation and power dam at Columbia River mile 348, about five miles upstream of the 300 Area. The original study was based on a nominal slack-water pool elevation of 395 to 400 feet at the dam location. A supplemental study evaluated the effects on plant facilities of a dam at the same location but with slack-water pool elevation of 385 feet. In addition to eff… more
Date: June 30, 1959
Creator: Jasko, R. T.
Partner: UNT Libraries Government Documents Department
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The Design of Large Cryogenic Magnet Coils : Paper No. 2

Description: Abstract: "Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils."
Date: October 30, 1959
Creator: Post, Richard F. & Taylor, C. E.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Partner: UNT Libraries Government Documents Department
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Uranium Recovery From Sodium-Zirconium Fluoride Salt Mixtures, Volatility Pilot Plant Runs L-1 Through L-9

Description: About 606 kg of sodium-zirconium fluoride salt mixture, similar to the ARE fuel but non irradiated, was reprocessed in the Volatility Pilot Plant. Development studies concerning decontamination and plutonium behavior were carried out. Complete decontamination from fission products was achieved.
Date: September 30, 1959
Creator: Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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Description of Purex Plant Process

Description: A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)
Date: April 30, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department
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THE SELF-DIFFUSION OF NIOBIUM--III. Final Progress Report for July 1, 1958 to January 1, 1959

Description: The self-diffusion coefficient of niobium was measured over the temperature range 1535 to 2120 C, using the radioactive isotope Nb95 as the tracer. The data for the temperature dependence of the self-diffusion coefflcient are best fitted by the equation D = (12.4 cores consistin 0.2) exp STA(-105,000 cores consistin 3OOO)/RT! cm/sup 2//sec. (auth)
Date: March 30, 1959
Creator: Resnick, R.; Castleman, L.S. & Seigle, L.
Partner: UNT Libraries Government Documents Department
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Reactor Coolant Decontamination: A Literature Survey

Description: Literature on reactor coolant and coolant loop contamination and decontamination was reviewed. The survey covered the four main reactor coolant types (water, gas, organic and liquid metal) and both activated corrosion products and fission product from leaks, The mechanisms and rates of deposition of the various materials in= the various coolants were compared. Various chemical decontaminating solution compositions and procedures were collected and presented.
Date: October 30, 1959
Creator: Mailen, J. C.
Partner: UNT Libraries Government Documents Department
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The Origin and Nature of Radioactive Wastes in the Atomic Energy Program

Description: There is great uncertainty in defining the nature of radioactive wastes from power reactor fuel reprocessing since it is not yet possible to say which processing methods will be used. For this reason several approaches to the problem and the wastes associated with each are described here.
Date: November 30, 1959
Creator: Bruce, F. R.
Partner: UNT Libraries Government Documents Department
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Shutdown heat exchangers

Description: Typical transient temperature curves for the reactor outlet coolant have been obtained for the cooldown period. Additional curves showing the relationship of several variables on the required heat exchanger area were obtained.
Date: July 30, 1959
Creator: Condotta, D. L.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of a nickel plated fuel element from PT-IP-207-A (RM-306)

Description: A .0005 inch thick chemically nickel plated, C-64 aluminum clad, natural uranium, internally and externally cooled, Hanford production fuel element, which had incurred a ``side hot spot`` during irradiation, was shipped to the Radiometallurgy Laboratory in June 1959 for post irradiation examination. The slug vas irradiated to approximately 400 MWD/T in C Reactor as part of PT-IP-207-A. The examination was requested by personnel from Process Engineering, Fuels Preparation Department and Process … more
Date: October 30, 1959
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Results of reverse flow experimental tests for C operational charge-discharge tube at low tub powers

Description: The purpose of this report is to present the results of laboratory experiments in which coolant water flowed backwards through a ``C`` reactor process tube with operational charge-discharge front fittings under conditions of typical reactor rear header pressures and post-scram rear header water temperature and tube powers. This information is of value in planning and interpreting transient experiments investigating the consequences of the rupture of reactor front face piping to a single tube.
Date: April 30, 1959
Creator: Fitzsimmons, D. E. & Hesson, G. M.
Partner: UNT Libraries Government Documents Department
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Production Test IP-261-C determination of power rate meter response

Description: This test will determine approximately the relationship between the power rate of rise indicated by the power rate meter and the actual pile power, rising period, and power rate. The actual pile power and power rate cannot be measured accurately during rapidly changing conditions; it is the intent of this test primarily to demonstrate that rate of rise protection offered by the power rate meter an be calculated to the same order of accuracy as the measurements of actual conditions.
Date: April 30, 1959
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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Studies of Zirconium-Iron-Tin Alloys. Report No. 6 (Final) for July 1, 1958-March 31, 1959

Description: The intermetallic compounds of the zirconium-irontin system (i.e., ZrFe/ sub 2/ and Zr/sub 4/Sn) were studied at 500 and 1100 C. The alloys were prepared from iodide zirconium and high-purity iron and tin by nonconsumableelectrode arc melting techniques under an inert atmospherc. Specimens were encapsulated in Vycor and annealed at the prescribed temperatures followed by a water quench. Data were gathered through the use of metallographic, x-ray diffraction, visible incipient melting, and magne… more
Date: April 30, 1959
Creator: Tanner, L.E. & Simcoe, C.R.
Partner: UNT Libraries Government Documents Department
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Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Summary Report

Description: Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the e… more
Date: April 30, 1959
Creator: Rosinski, J. & Stockham, J.
Partner: UNT Libraries Government Documents Department
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Variable Moderator Reactor Development Program. Quarterly Progress Report No. 2

Description: The hydrodynamics code BOCH was used to obtain the relationship between a large number of variables such as voids, flux, pin spacing, power density, and pressure for VMR lattices. Based upon these relationships, a reference core design was selected for examination, using the integrated physics and hydrodynamics analytical modeis. The analog representations of the VMR core kinetics describing the individual blocks of a model block diagram were completed. A simplified core physics analysis was co… more
Date: November 30, 1959
Partner: UNT Libraries Government Documents Department
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Dissolution of Zirconium Matrix Fuels in Molten Fluoride Salts

Description: The application of the Volatility Process for reprocessing spent reactor fuels to zirconium fuel elements requires the conversion of the fuel to a fluoride form. This conversion can be accomplished by the dissolution of such fuels in a bath of molten fluoride salts with a hydrogen fluoride sparge. Studies with dummy zirconium fuel elements showed dissolution rates averaging 2 mg/sq cm-min. The effect of submergence, geometrical configuration, and HF impingement rate appeared more significant th… more
Date: January 30, 1959
Creator: Horton, R. W. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism

Description: This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62… more
Date: December 30, 1959
Creator: Troutner, V. H.
Partner: UNT Libraries Government Documents Department
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