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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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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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Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
Partner: UNT Libraries Government Documents Department
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Interim Report -- The Retention of Particles in Ducts Transporting Aerosol Streams

Description: Accurate sampling of particulate in gaseous effluents is required for auditing and control of radioactive wastes released to the environment at installations generating or processing radioactive materials. Over the years a variety of sampling probe configurations, sampling velocities, lengths and sizes of sample delivery lines have been used locally to obtain these samples. Efforts to properly evaluate the validity of samples in most sampling installations have been hampered by a lack of basic … more
Date: February 1, 1960
Creator: Postma, A. K. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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Hydraulic System Flow Decay Relations During Loss of External Power

Description: Over the last decade, several computational methods have been developed and used to examine reactor flow transients caused by pump outage. The variations in system character which have been analyzed are sufficiently diverse that it appears worthwhile to compile them into a single report.
Date: February 11, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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The Irradiated Rupture Prototype (IRP) Design

Description: One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
Partner: UNT Libraries Government Documents Department
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Evaluation of Fretting Corrosion of ZR-2

Description: Although the corrosion of resistance of Zircaloy--2 clad fuel elements in high temperature water is excellent, some concern has been expressed in regard to the resistance against fretting corrosion. Since this form of corrosion can proceed quite rapidly it could induce fuel element failure through penetration of the cladding. Fretting corrosion if it occurred, would take place either where the fuel element contacted the process tube or where portions of the fuel element contacted each other, e.… more
Date: February 5, 1960
Creator: Lobsinger, R. J.
Partner: UNT Libraries Government Documents Department
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The Use of Ultrasonic in Electrodeposition and Electroplating : a Bibliography

Description: This bibliography contains 20 references on the use of ultrasonic in electrodeposition and electroplating. The bibliography is limited to the period 1955 to 1959, with the references arranged alphabetically by title. Sources used in compiling this bibliography were: Applied Science and Technology Index, ASM Review of Metal Literature, Chemical Abstracts, Industrial Arts, Index, Nuclear Science Abstracts.
Date: February 18, 1960
Creator: Cernak, Elizabeth A.
Partner: UNT Libraries Government Documents Department
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A Systematic Procedure for Preparing Specifications on Electronic Instrumentation and Control Systems

Description: Abstract. A systematic procedure for preparing purchase specification on electronic instrumentation or control systems has been developed. This procedure results in preparation of specifications which: 1) make it possible to find any particular specification requirement quickly; and 2) insure that no important requirement has been omitted. Details of this systematic specification preparing procedure presented.
Date: February 4, 1960
Creator: Olken, Hyman
Partner: UNT Libraries Government Documents Department
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Scintillation Counter [gamma]-Spectra Unfolding Code for the IBM-650 Computer

Description: Abstract. An IBM-650 computer code for the detailed unfolding of [gamma]-ray spectra obtained from NaI scintillation counters has been developed. The procedure is set up to remove analyzer scale dependence and to largely remove energy dependences. Computer time is about 1 minute per [gamma]-ray.
Date: February 17, 1960
Creator: West, Harry I., Jr. & Johnston, Bradley.
Partner: UNT Libraries Government Documents Department
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Image Converter Tubes : Manufacturer's Data

Description: Introduction. A survey has been made of the image converter tubes generally available in this country and Europe. Ultraviolet and infrared types using photocathodes were included, buy x-ray and solid state types were omitted. Since this is the first time that this list has been compiled, it may have errors and omissions. The author will appreciate any corrections or suggestions, and it is hoped that revised lists will be published from time to time.
Date: February 1960
Creator: Inami, F. K.
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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Recovery of Neptunium From Purex Waste by an Agitated Bed of Anion Exchange Resin

Description: Technical report. From Abstract: "Data are presented for the absorption of thorium and neptunium from synthetic waste concentrate of the "Purex" process by a miniature agitated bed of anion exchange resin. The behavior of neptunium indicated that efficient recovery should be obtained from Purex high activity waste concentrate by this technique. A method was developed for calculating absorption losses from agitation beds of resin. The predicted losses were in excellent agreement with experimenta… more
Date: February 1960
Creator: Prout, William E., 1921- & Fernandez, LeVerne P.
Partner: UNT Libraries Government Documents Department
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Physics Data From a Mockup of the HWCTR Lattice in the PDP

Description: Technical report. From Abstract: "Experiments were performed in the Process Development Pile (PDP) with a critical mockup of the Heavy Water Components Test Reactor (HWCTR) lattice. Reactivity measurements served to determine control rod worths, the temperature coefficient of the reactor at low temperatures, the dependence of keff on concentrations of U235 and poisons in the "driver" region of the reactor, and the changes in keff that occur in certain conceivable accidents in the HWCTR. Flux di… more
Date: February 1960
Creator: Graves, William E.
Partner: UNT Libraries Government Documents Department
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