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A Study of the Fuel Value of Plutonium

Description: The fuel value of mixtures of plutonium isotopes has been calculated for five thermal reactors (Yankee, Dresden, Hallam, GCR-II, Carolinas-Virginia)
Date: February 11, 1960
Creator: Jaye, S.; Bennett, L. L. & Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Assay Methods Used In The ORNL Radioisotope Program

Description: A brief description is given of methods used in the measurement of radioactive content of radioisotopes distributed by the Oak Ridge National Laboratory. A tabulation of the techniques employed for seventy eight nuclear species is presented.
Date: February 1, 1960
Creator: Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
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Observed Heat Transfer In HRT Fuel And Blanket Heat Exchangers

Description: Data obtained during power operation of the HRT indicates that during the circulation of fuel solution at high temperatures for more than 260 days there was a small increase in heat transfer resistance in the heat exchangers. The change in heat transfer correlates with the increase of the amount of corrosion product solids in the reactor fuel system.
Date: February 8, 1960
Creator: Haubenreich, P. N.; Piper, H. B.; Buxton, S. R. & Engel, J. R.
Partner: UNT Libraries Government Documents Department
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Natural Circulation Burn Out Heat Flux For The ORR

Description: Natural circulation flow rate is calculated for the ORR core. From this flow rate, the burn out heat flux is found to be between 22,000 and 35,000 Btu/ft2-hr. It is concluded that under present conditions a positive acting after heat removal system is necessary for 30 mw operation.
Date: February 15, 1960
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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Hazards of Nuclear Power Units in Space Applications

Description: This review attempts to point up some of the hazards which may arise with the use of nuclear power plants in space vehicles. It examines hazards to the general population during both launch and return as well as to the occupants of the space vehicle.
Date: February 5, 1960
Creator: Lafyatis, P. G.
Partner: UNT Libraries Government Documents Department
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Material Balance Flowsheets

Description: This report presents material balance flowsheets for the dissolution of UO2, UO2-ThO2 and U-Mo fuels clad in stainless steel or zirconium by the Sulfex, Darex, and Zirflex process. These fuel elements are from power reactors which have been of may be committed to ORNL for reprocessing in the PRFR Program.
Date: February 1, 1960
Creator: Shappert, L. B.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Elements Reprocessing - Safety Report

Description: An analysis has been made of the steps taken to assure safe handling of the SRE fuel elements during reprocessing in the Power Reactor Fuels Reprocessing Program, mechanical phase, cell complex in Building 3026.
Date: February 5, 1960
Creator: Klima, B. B.
Partner: UNT Libraries Government Documents Department
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Progress letter No. 11 for January 1, 1960 through January 31, 1960

Description: A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date: February 15, 1960
Creator: Baron, Edeard H.
Partner: UNT Libraries Government Documents Department
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Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961

Description: During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date: February 16, 1960
Creator: Russell, Elizabeth Shull, 1913-2001
Partner: UNT Libraries Government Documents Department
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Progress Report for Period Covering January 15, 1960 - February 15, 1960

Description: Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date: February 15, 1960
Creator: Petrow, Henry G.
Partner: UNT Libraries Government Documents Department
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Atmospheric Tritium Analysis Technical Progress Report No. 2

Description: Following a discussion of various technical improvements in the tritium analysis facility, a summary is given of the tritium content of Chicago precipitation from 18 December 1957 to 15 June 1959. A smooth decay curve was obtained during an undisturbed period of two months following the "Hardtack" weapons tests in the spring and summer of 1958; a residence time for water in the troposphere of 21.0 + 1.4 days is reduced therefrom. Examination of the data following cessation of weapons tests reve… more
Date: February 16, 1960
Creator: Barrett, Earl W. & Huebner, Leonid
Partner: UNT Libraries Government Documents Department
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Effect of Irradiation of Solid Catalysts

Description: The work done during this period continued along the same lines as outlined in the first two quarterly reports. The catalysts irradiated this period all received a beta radiation dose of 200 megarads, ten times that given the catalysts previously. At this dosage, some changes in catalytic activity were observed.
Date: February 25, 1960
Creator: Andersen, H. C.; Rylander, P. N. & Keith, C. D.
Partner: UNT Libraries Government Documents Department
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Cyclic Pressure Tests of Large Size Pressure Vessels

Description: This investigation into the plastic fatigue strength of large size pressure vessels is a part of a general research program on plastic fatigue problems in pressure vessels which is being carried out at several laboratories. While the overall program includes identical pairs of vessels fabricated from A-201, A-302, and T-1 steels, the work in progress concerns only the A-201 vessels. This report covers the progress in the period from 15 January 1960 to 15 February 1960.
Date: February 15, 1960
Creator: Lemcoe, M. M.
Partner: UNT Libraries Government Documents Department
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Neutron Activation Analysis

Description: A high spot literature search was made of "Nuclear Science Abstracts" vols. 5-14 (1951-Feb. 15, 1960). the A. F. C. card catalog, and "Abstracts of Classified Reports" vols. 11-15 (Jan. 1955-June 30, 1959) for information on methods of neutron activation analysis.
Date: February 1960
Creator: Kauer, E. U.
Partner: UNT Libraries Government Documents Department
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Isotopic Method for Age Determinations of Industrial Products

Description: The month of January 1960 was devoted primarily to such pertinent matters as instrument evaluation and standardization. Two sets of calibrated standards were purchased from New England Nuclear for this work. The beta emitting set includes samples of carbon-14, cobalt-60, bismuth-210, thallium-204 and protaotinium-234. The set of gamma standards contains cobalt 57, cobalt 60, barium 133, cesium 137, and manganese-54. In addition, samples of both C-14 labeled benzoic and stearic acid are also on … more
Date: February 24, 1960
Creator: Gregson, T. C. & Bangs, L. B.
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys

Description: This informal letter report is the tenth of a series of monthly letter reports for the contract year. 15 March 1995 to 15 March 1960, describing the progress made on the research program, "Study of Factors Influencing Ductility of Iron-Aluminum Alloys," Contract No. AT(11-1)-742.
Date: February 9, 1960
Creator: Perkins, Frank C. & Nachman, Joseph F.
Partner: UNT Libraries Government Documents Department
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Evaluation Of Future Levels Of Radioactive Fallout

Description: The evaluations of future levels of strontium-90 deposition on the ground have been carried out for three different cases. 1. no more nuclear weapon tests are carried out after October 1958; 2. tests continue to be carried out at the same average rate as in the past; and 3. tests are carried out at the highest rate observed in the past, i.e. during the year 1958. These evaluations are done for Bombay, India, and are based on the ground deposition data on 1st October, 1958, and stratospheric inv… more
Date: February 1960
Creator: Vohra, K. G. & Mishra, U. C.
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for End Closures on NPR and KER Fuel Element

Description: With the development of the zircaloy-2 clad uranium fuel element, it was necessary to develop a method of closing the end of the element after the extruded tubes were cut to the desired length. Regardless of the ultimate design of the closure, a satisfactory zircaloy-2 fusion welding technique had to be worked out. The first fully successful welding was performed with electron beam welding in a vacuum chamber. To make satisfactory welds, the electron beam welding involved time and equipment, pl… more
Date: February 22, 1960
Creator: Corey, T. B.; DeWitt, D. E. & Nelson, I. V.
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 2

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Date: February 18, 1960
Creator: Hokenson, J. F. & Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on the Use of Activated Carbon as a Catalyst for the Dissolved Oxygen-Aqueous Hydrazine Reaction

Description: Theoretically aqueous hydrazine will react with dissolved oxygen for form only nitrogen and water. Most of the experimental evidence, however, indicates that the reaction proceeds rather slowly in low-temperature systems. Tests are currently being conducted to determine whether or not it is feasible to use activated carbon to catalyze the reaction in filtered water. A system of this type would be useful in high temperature reactors when it becomes necessary to convert to single-pass operation.
Date: February 24, 1960
Creator: Demmit, T. F.
Partner: UNT Libraries Government Documents Department
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Gas-Graphite Reactions. I. Thermal and Microwave Oxidation of Various Reactor-Grade Graphites*

Description: Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.
Date: February 10, 1960
Creator: Clark, T. J.
Partner: UNT Libraries Government Documents Department
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KAPL-120-8A Test Assembly Thermocouple Failure.

Description: This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.
Date: February 5, 1960
Creator: Dearing, F. E.
Partner: UNT Libraries Government Documents Department
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