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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "With careful attention to details, tritium assays of satisfactory accuracy have been achieved on low activity standard samples by dry combustion and liquid scintillations counting of the product water.This method is faster, more accurate and dependable than the zinc fusion-ion chamber method fro low level tritium assays. At 380 degrees C, tritium loses from hydrocarbon tracers by isotopic exchange is significant and must be corrected for in tracer measurements at this elevated temperature."
Date: November 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "This is the first quarterly report on Task II of the subject Utilization of Radioactive Isotopes in Coal Process Research. There were two separate projects on Tank I; I. methods Development for Tritium Labeling of Coal Product Hydro-carbons, and II. Applications of Radio-Tracer Techniques to the Study of Fluidized Particle Mechanics. The following extended work on Task II concerns only Methods Development of Radio-Tracing With Tritium."
Date: August 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
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The p-n Cross Sections onf Ti47, V51, Cr52, Co59, and Cu63 from 4 to 6.5 Mov

Description: Absolute (p,n) cross sections have been measured for Ti47, V51, Cr52, Co59, and Cu63 at energies between 4 and 6.5 Mov. These data plus earlier measurements of the cross section for inelastic proton scattering have been used to estimate total proton absorption cross sections for V51 and Co59. An optical model calculation using parameters giving a good fit to elastic scattering measurements predicts an absorption cross section in good agreement with the measurements for Co59. For V51, some sets of parameters gave good agreement with the measured absorption cross section, but the fit to the elastic scattering data was only fair.
Date: June 15, 1960
Creator: Taketanit, H. & Alford, W. P. (William Parker), 1927-
Partner: UNT Libraries Government Documents Department
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Thorium Oxide Infiltration of Graphite Spheres

Description: Work on the preparation of graphite spheres containing thorium oxide for use as breeder elements in the Pebble Bed Reactor-Steam Power Plant is described. Graphite spheres of varying density were infiltrated with thorium nitrate solutions, followed by denitration to thorium oxide.
Date: June 15, 1960
Creator: Parker, W. E. & Rusinko, F.
Partner: UNT Libraries Government Documents Department
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Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization

Description: The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Date: September 15, 1960
Creator: Isotopes Incorporated
Partner: UNT Libraries Government Documents Department
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Zero Power Experiments for the SM-1 Core II : Task XV

Description: Abstract: An element by element reactivity check for SM-1 Core II fuel elements and control rod absorber sections was performed and the burnable nuclear poison loading in the SM-1 Core II stationary fuel elements was established. An approach to criticality of the SM-1 Core II was performed by the inverse multiplication method and the critical rod bank position obtained as a function of fuel loading up to the full SM-1 Core II loading. Maximum and minimum core reactivity measurements were obtained by selective loading of stationary fuel elements and the total "excess K" for the core established. Power distribution measurements in the region of the core-reflector interface and the fuel-absorber interface in the control rod assemblies were performed. The effectiveness of europium flux suppressors in the top of control rod fuel elements and the power peaking in stationary elements adjacent to water gaps in control rod assemblies were measured. Survey measurements established the worth of spiking cold clean SM-1 cores with SM-2 elements, and of water holes in the SM-1 core which might be utilized as flux traps for materials irradiation.
Date: March 15, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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A Multichannel Digital Recording System

Description: Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Partner: UNT Libraries Government Documents Department
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Steady-State Tests of a Reactor Safety Device

Description: Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date: December 15, 1960
Creator: Springer, T. H.
Partner: UNT Libraries Government Documents Department
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A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Partner: UNT Libraries Government Documents Department
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Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Partner: UNT Libraries Government Documents Department
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Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Description: Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
Partner: UNT Libraries Government Documents Department
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Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
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