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The Hard-Core Pinch. I

Description: This report analyzes a linear, hard-core pinch tube built to examine tubes afflicted by small-scale instabilities evident from many observations.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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The Hard-Core Pinch. II

Description: This report describes a toroidal version of the hard-core pinch and the additional information it can obtain to what the analogous linear pinch can get.
Date: July 31, 1959
Creator: Birdsall, D. H.; Colgate, Stirling A. & Furth, Harold P.
Partner: UNT Libraries Government Documents Department
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PRTR Total Energy Distribution Calculations

Description: Since the calculation of the PRTR energy distribution was first carried out by J. R. Triplett, the design has become sufficiently fixed to allow a refinement of his values. The present analysis, also, includes a calculation of the fraction of energy which is released in the shroud and process tubers that flows to the primary coolant to the top and bottom shield coolant is taken into consideration. Nuclear data used in the original calculations still appears satisfactory and is, therefore, util… more
Date: July 31, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Suggested Major Equipment for NPR Water Quality Control Labs

Description: Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.
Date: July 30, 1959
Creator: Bainard, W. D.
Partner: UNT Libraries Government Documents Department
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Thermodynamics of Irreversible Processes: The Experimental Verification of the Onsager Reciprocal Relations

Description: Report discussing theories of irreversible thermodynamic processes. "The purpose of this review is to collect the presently available experimental data for a variety of quite different irreversible phenomena and to show that this evidence does indeed verify the Onsager Reciprocal Relations."
Date: July 30, 1959
Creator: Miller, Donald Gabriel
Partner: UNT Libraries Government Documents Department
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1. K+ Charge Exchange - Search For K+ Charge Exchange

Description: An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.
Date: July 29, 1959
Creator: Birge, Robert W.; Courant, Hans J.; Lanou, Robert E., Jr. & Whitehead, Marian N.
Partner: UNT Libraries Government Documents Department
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II. K+ Charge Exchange - Production Of Ko Mesone By Charge Exchange Of K+ In Propane

Description: In another paper there was reported an attempt to observe the charge-exchange process in a counter-triggered multiplate cloud chamber at the Bevatron but the interpretation was ambiguous. Shortly after the close of that experiment the 30-in. propane bubble chamber at the Lawrence Radiation Laboratory was completed and able to be used for a combined engineering test and experiment. The existence of Reaction (1) has been confirmed in this experiment, and an approximate cross-section value for car… more
Date: July 29, 1959
Creator: Whitehead, Marian N.; Lanou, Robert E., Jr.; Birge, Robert W.; Powell, Wilson M. & Fowler, William B.
Partner: UNT Libraries Government Documents Department
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Time Dependence of the Beam in the 86-Inch Cyclotron

Description: In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date: July 29, 1959
Creator: Goodman, C. D.
Partner: UNT Libraries Government Documents Department
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Multiplication Measurements with Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Partner: UNT Libraries Government Documents Department
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Shielding on a 27,300 SHP Boiling Water Reactor Marine Propulsion System

Description: This report summarizes the radiation and shielding analysis for a 30,000 SHP natural circulation boiling water reactor for ship propulsion. The reactor is proposed for installation in a 60,000 DWT, 18 knot tanker of the T-7 class.
Date: July 25, 1959
Creator: Craig, W. D.
Partner: UNT Libraries Government Documents Department
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DC Bridge NPR Horizontal Rod Counting

Description: This report is a summary of work done for system development on the NPR ball safety backup for the horizontal rods. This phase of the system development is limited to discussion of the horizontal rod counting circuitry utilizing a direct current bridge network.
Date: July 24, 1959
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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Preliminary Chemical Flowsheets for the Decladding and Dissolution of Non-Production Fuels

Description: This document presents preliminary chemical flowsheets for cladding and core dissolution of zircaloy-clad uranium dioxide and stainless steel-clad uranium-molybdenum non-production fuels. These preliminary flowsheets together with existing process flowsheets should be adequate for process development in the currently forecast non-production fuels dissolution facility.
Date: July 24, 1959
Creator: Harmon, M. K.
Partner: UNT Libraries Government Documents Department
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Decontamination of the PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior.
Date: July 23, 1959
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

Description: The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energ… more
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Partner: UNT Libraries Government Documents Department
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PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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A Microspark Apparatus for the Study of Inclusions in Metals

Description: A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be … more
Date: July 22, 1959
Creator: Smith, F. M.
Partner: UNT Libraries Government Documents Department
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employe… more
Date: July 21, 1959
Creator: Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Partner: UNT Libraries Government Documents Department
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Multigroup Diffusion Theory Calculations for Recent Critical Experiments

Description: In connection with the program of the measurement of eta for U233, several critical experiments have been performed by R. Gwin and D. W. Magnuson of ORML with light water solutions of uranyl nitrate (highly enriched in either U233 or U35) in an essentially bare sphere 27 inches in diameter. This report presents the results of two multigroup-diffusion-theory calculations for the above experiments performed by C. B. Mills and associated at Los Alamos. Assumer cross sections, material concentratio… more
Date: July 21, 1959
Creator: Nestor, C. W., Jr
Partner: UNT Libraries Government Documents Department
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A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses

Description: Extraction systems involving chelating agents are widely used in radiochemical separations on a control basis due to the economy in time and equipment. In the case of waste streams, the element of interest is, by definition, at a very low concentration in the presence of gross fission product activities. The resultant large sample size necessary for a reliable analytical results creates a marked radiation hazard to laboratory personnel.
Date: July 21, 1959
Creator: Campbell, M. H.
Partner: UNT Libraries Government Documents Department
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Stack Effluent Monitor Operation and Maintenance

Description: The Stack Effluent Radioisotope Monitor is an instrument which continuously measures and records the amounts of each of several different radioactive isotopes in the stack effluent of the Redox Facility. An informal report, HW-56151, describing the theory of operation and the circuits was prepared and is available to Hanford personnel from the technical files. The formal report, HW-56151 Rev, containing essentially the same information, is available from the Office of Technical Services, Depar… more
Date: July 21, 1959
Creator: Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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