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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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Boiling Water Reactor Study [Part 2, Supplement]: Separate Studies

Description: From summary and conclusions: This study has been made to determine the feasibility of installing reheat steam facilities in conjunction with the selected 306-mw boiling water nuclear power plant.
Date: February 1960
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Circuit Dynamics of the Pinch

Description: The following document aims to analyze the dynamics of a pinch tube, including the reaction back on the energy source.
Date: February 1960
Creator: Killeen, John & Lippmann, B. A.
Partner: UNT Libraries Government Documents Department
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A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958

Description: From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date: February 1960
Creator: Brodsky, Allen & Beard, G. Victor
Partner: UNT Libraries Government Documents Department
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Description of Facilities and Mechanical Components: Medical Research Reactor (MRR)

Description: Report issued by the Brookhaven National Laboratory discussing the Medical Research Reactor at the Medical Research Center. Design, tests, and operations of the reactor are presented. This report includes tables, illustrations, and photographs.
Date: February 1960
Creator: Godel, Jules B.
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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Heavy Water Moderated Power Reactor Plants [Part 1]: Design Study

Description: From preface: This report is one of a series covering a design study of heavy water moderated power reactor plants with the objective of selection and recommendation of a conceptual design for providing optimum economics with slight fuel enrichment.
Date: February 1960
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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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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The Liquid Metal Thorium Breeder Reactor

Description: From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."
Date: February 1960
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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Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Description: From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."
Date: February 1960
Creator: Argonne National Laboratory
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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Transistor Scintillation Spectrometer

Description: Report describing "an AC-operated portable scintillation spectrometer consisting of a preamplifier, a linear pulse amplifier, a single-channel pulse-height analyzer, a linear count-rate meter, a scaler, and a high-voltage power supply. The operation and performance of the circuits are discussed" (p. 3).
Date: February 1960
Creator: Strauss, Michael G.
Partner: UNT Libraries Government Documents Department
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ETR Nuclear Instrumentation : Final Report

Description: Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
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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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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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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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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