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Charging and Discharge of Demineralizer Resins. Section IV. First Performance. Core I, Seed 1. Test Results DL-S-180, T-612085

Description: The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.
Date: December 3, 1959
Creator: Eckenrode, G. E.
Partner: UNT Libraries Government Documents Department
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The Determination of Decontamination Factors for Radioisotopes Through Lithium Hydroxide Resin. Section I. Second Performance. Core I, Seed 1. Test Results DL-S-277-S, RNI-22

Description: The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.
Date: December 3, 1959
Creator: Strauos, Roger O.
Partner: UNT Libraries Government Documents Department
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Neutron-Flux Measurements in a Flat Plate Fuel Element

Description: The equipment and experiments performed to measure the thermal-neutron- flux distribution in a fuel assembly of an experimental loop mock-up of a gas:cooled reactor at the Battelle Research Reactor (BRR) are described. The loop was located adjacent to the core of the BRR and contained one fuel assermbly composed of seven flat fuel plates each containing approximately 29.5 g of U/sup 235/. The plates consisted of a core 0.050 in. thick of UO/sub 2/ dispersed in Type 347 stainless steel and clad … more
Date: December 3, 1959
Creator: Morgan, W.R.; Anno, J.N. Jr. & Chastain, J.W. Jr.
Partner: UNT Libraries Government Documents Department
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Further Investigations of Natural Environmental Radiation

Description: Report documenting the investigation of cosmic and terrestrial background radiation. "Remeasurements in many locations furnished estimates of dosimetric increase in terrestrial levels due to fallout. Radiation measurement sin residential dwellings in he New York metropolitan areas are described" (p. 1).
Date: November 3, 1959
Creator: Solon, Leonard R.; Lowder, Wayne M.; Shambon, Arthur & Blatz, Hanson
Partner: UNT Libraries Government Documents Department
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The High-Energy Electrostatic Plasma Gun

Description: This report analyzes the High-Energy Electrostatic Plasma Gun, which is to be used for propulsion.
Date: November 3, 1959
Creator: Fox, Raymond
Partner: UNT Libraries Government Documents Department
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Nuclear Safety in Manufacturing Plants

Description: From Introduction: "In the following pages are summarized the factors which influence neutron economy and which, therefore, are important in nuclear safety."
Date: November 3, 1959
Creator: McLaughlin, James E.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Meeting: September 1959

Description: From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section I. EFPH-4182. First Performance. Core I, Seed 1. Test Results DL-S-231 (T-612394)

Description: The purpose of the survey was to determine the radiation levels in the 1 D Boiler Chamber during plant operation. The conclusion of this survey is that the radiation level in the 1 D Boiler Compartment with the 1A, 1B, and 1C Main Coolant loops in service at approximately 100 per cent power ranged from .03 MR/HR to 6.0 MR/HR.
Date: November 3, 1959
Creator: Ritz, William C.
Partner: UNT Libraries Government Documents Department
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An Improved Gamma Detector Using Gamma Moderation

Description: Abstract: "Theoretical and experimental results of the effect of gamma moderation are described. A 6.7-fold enhancement factor was obtained with a 1/8-in. - thick sodium-iodide crystal when using gamma moderation and a Co-60 gamma source. A counter was designed and built to make the most use of gamma source. A counter was designed and built to make the most use of gamma moderation. The results indicate that this counter can be made energy independent over a wide region. Though the cost of the c… more
Date: September 3, 1959
Creator: Fox, Raymond
Partner: UNT Libraries Government Documents Department
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Microbarograph Evaluation Report

Description: From introduction: This report describes the procedures used and the results obtained in evaluating the Wiancko type 3-PBM-2 microbarograph system.
Date: September 3, 1959
Partner: UNT Libraries Government Documents Department
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Some Thermodynamic Properties of Freon-114

Description: Introduction: The thermodynamic properties of Freon-114 presented herein supplement those of Volume I and encompass a range of temperature above the critical to 400 F &176 F.
Date: September 3, 1959
Creator: Van Wie, N. H. & Ebel, Robert A.
Partner: UNT Libraries Government Documents Department
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Isotopic sources of secondary radiation : second interim technical report covering the period from March 1 to July 1, 1959

Description: Summary. During the past year the work carried out in this program has included experiments on the x-ray output produced by the separated fission product beta sources, the interpretation of such experiments for the effective design of high level secondary x-ray sources, and the design and testing of prototype sources of secondary radiation for specific industrial applications. In this report results of work carried out during the past fours months are reported: (1) analysis of beta-excited x-… more
Date: August 3, 1959
Creator: Voyvodic, L.
Partner: UNT Libraries Government Documents Department
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Melting Point of Th-U-C Fuel Elements

Description: From the point of view of predicting melting behavior of fuel elements containing fission products after 50 percent burn-up, the fuel can be considered to consist of 2000 moles Th, 150 moles U, 55 moles of rate earth metal, 31 moles of Zr, 25 moles of Mo, 20 moles of Rh-Ru-Tc, and 15 moles of alkaline earth metal. All other fission products are present in too small amounts to have any important effect upon the melting point or will have vaporized. However, the presence of alkali metal vapor sho… more
Date: August 3, 1959
Creator: Brewer, Leo, 1919-2005
Partner: UNT Libraries Government Documents Department
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Comments on calcined 1WW storage

Description: Studies are under ray in Chemical Research and Development to-provide the technical ``know-how`` necessary to calcine Purex 1WW and safely store the solid product. The solid product can be stored as the particulate solid from the calciner or, after further treatment, as a solid matrix or melt. In this regard, Chemical Research is studying a PO{sub 4}BO{sub 2} melt. This document presents expected fission product heat generation rates in the solid product, shows the effect of various variables o… more
Date: June 3, 1959
Creator: Coppinger, E. A.
Partner: UNT Libraries Government Documents Department
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Methods of Controlling Core-Wall Temperatures in Aqueous Homogeneous Reactors

Description: The problem of controlling the surface temperatures of core vessels in two-region aqueous homogeneous reactors has been examined by analyzing several possible systems for cooling the wall: (1) direction of the inlet core fluid along the wall at a high velocity; (2) passage of heavy water through the wall of a double-wall core vessel; and (3) flow of cool blanket slurry past the wall.
Date: June 3, 1959
Creator: Rosenthal, M. W.
Partner: UNT Libraries Government Documents Department
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Development and Preliminary Testing of Powder-Lock Feeder

Description: At the request of 234-5 Development, studies of a system for controlling plutonium powder transfer were undertaken by Process Equipment Development. This report presents details of equipment designed to fulfill requirements and proposes equipment for installation on additional Hot Button Line prototypes.
Date: April 3, 1959
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department
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Effect of Moderator Height on Reactor and Vertical Flux Distribution in PRTR

Description: Primary control of the PRTR is achieved by regulating the level of the heavy water moderator which is held in the reactor vessel by a helium gas balance system. Emergency shutdown is effected by a gas-balanced moderator dump system which drain the moderator from the calandria at a rapid rate. This report presents a quantitative appraisal of the reactivity effects due to moderator level changes in controlling or scramming the reactor. In conjunction with the reactivity calculations, solutions we… more
Date: March 3, 1959
Creator: Reginmbal, J.J.
Partner: UNT Libraries Government Documents Department
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Piping Components for Organic Coolant Systems

Description: Organic compounds have been considered for use as reactor coolants for two primary reasons. First, the high boiling points of the compounds would permit the reactor to operate at high temperature without the need for the high pressure required when water is used as a coolant. Secondly, the compounds are less corrosive than water and would permit the use of carbon steel rather than stainless steel components in the reactor. Unfortunately, the organic compounds proposed for use as reactor coolant… more
Date: March 3, 1959
Creator: Floyd, H. L.
Partner: UNT Libraries Government Documents Department
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Physics effects of water mixing pieces

Description: The effects of ``water mixing`` pieces on the axial flux distributions and reactivities of the K Reactors are discussed in this report. Two mixing piece configurations in the K piles are compared to provide a basis for determining the optimum configuration with respect to rupture control, reactivity cost and temperature cycling effects.
Date: February 3, 1959
Creator: Parkos, G. R.
Partner: UNT Libraries Government Documents Department
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Neptunium-aluminum fuel capsule irradiation; GEH-14-60, 61, 62, 63

Description: The purpose of the test described in this report is to examine the irradiation behavior of a proposed target alloy for use in Hanford reactors and to provide material for chemical separation studies.
Date: December 3, 1958
Creator: Bates, J. L.; Roake, W. E. & Voiland, E. E.
Partner: UNT Libraries Government Documents Department
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Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department
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Characteristics of the Langley 8-Foot Transonic Tunnel With Slotted Test Section

Description: "A large wind tunnel, approximately 8 feet in diameter, has been converted to transonic operation by means of slots in the boundary extending in the direction of flow. The usefulness of such a slotted wind tunnel, already known with respect to the reduction of the subsonic blockage interference and the production of continuously variable supersonic flows, has been augmented by devising a slot shape with which a supersonic test region with excellent flow quality could be produced. Experimental l… more
Date: July 3, 1958
Creator: Wright, Ray H.; Ritchie, Virgil S. & Pearson, Albin O.
Partner: UNT Libraries Government Documents Department
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Examination of Factors Affecting the Quality of Vacuum Induction-Melted Uranium

Description: The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.
Date: July 3, 1958
Creator: Endebrock, Roy W.; Foster, Ellis L. & Dickerson, Ronald F.
Partner: UNT Libraries Government Documents Department
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