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Heavy Water Power Reactor Program Monthly Report: October 1961

Description: Report documenting progress on the Heavy Water Power Reactor Program including installation of silver-impregnated graphite seals upon completion of cold-testing of the dynamic ball valve seal test package using Teflon seals, the starting of creep-rupture tests of two materials at three test temperatures, and the drafting and design progress of several scanning and heat transfer machines.
Date: November 20, 1961
Partner: UNT Libraries Government Documents Department
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Calibration of Nude Ionization Gauges : Supplement No. 2 to ORNL-CF 61-5-109

Description: Whenever an ionization gauge without envelope (nude-type) is used on the same system with a conventional (tabulated) gauge different pressures are usually indicated by the type type of gauges. Three different models of nude Byart-Alpert type gauges have investigated: (1) Vactronic-N.I.G. (two), (2) Veeco RG-75 (denuded) and (3) Hughes-6578. Parallel calibrations of tublated RG075 gauges ere made in each case. Nude ionization gauges, when operated continuously for long periods of time in our tes… more
Date: November 24, 1961
Creator: Normand, C. E.
Partner: UNT Libraries Government Documents Department
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Electrical and Electronic Symbols & Drawing Committee

Description: This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain e… more
Date: November 1961
Creator: Bates, A.E.G
Partner: UNT Libraries Government Documents Department
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Servo System for Magnetic Controlled Constant Intensity Flat Top Beam Spill-Out

Description: A uniform intensity flat top spill-out cannot be obtained by manual control for two reasons: 1. The horizontal density of the internal beam of the Cosmotron is far from uniform. As a result, a manually controlled linear motion of the internal beam into a target will result in a non-uniform spill-out intensity. 2. Stability requirements of the Cosmotron magnet voltage are not easily met without feedback because of inherent component stability. The proposed servo system will sense the external be… more
Date: November 21, 1961
Creator: Cottingham, J. G.
Partner: UNT Libraries Government Documents Department
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Neutron Dosimetry in and Around Human Phantoms By Use of Nuclear Track Emulsion

Description: The power of nuclear track research emulsion as a fast neutron dosimeter is examined in the exposure of a human phantom to PuBe neutrons. Semiautomatic track scanning and high-speed data analysis obviate the major disadvantages of this dosimeter, and allow the following basic information to be obtained without a serious cost in time: the rulative proton recoil energy spectrum, the absolute differential proton track den sity spectrum, and the average proton recoil energy at various locations in … more
Date: November 30, 1961
Creator: Akagi, Hiroaki & Lehman, Richard L.
Partner: UNT Libraries Government Documents Department
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Some methods of surface analysis for the prediction of thermal resistance of metal contacts

Description: "Equations for the heat-transfer coefficient existing at the interface of two metals in contact are discussed. The results of applying the equations (with a graphical determination of the geometric parameters) to an iron--aluminum contact are presented. A method is given for performing the graphical analysis by means of a general purpose analog computer. Data are included that were obtained by applying this method to Blanchard ground stainless steel surfaces in contact. Statistical analysis was… more
Date: November 1, 1961
Partner: UNT Libraries Government Documents Department
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Fuel Element Transient Temperature Studies

Description: A method is presented for the analysis of transient temperatures in a homogeneous circular cylindrical fuel element in a coolant channel with no axial conduction and no heat loss to the channel wall. In addition, some results were obtained for mean fuel element temperatures in power transients for a simpler model, but accounting for details of the axial coolant temperature distribution in the unsteady state. (auth).
Date: November 1, 1961
Creator: Thompson, J. J.
Partner: UNT Libraries Government Documents Department
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Determination of the Stability Constants of Salicylato-Beryllium Complexes by a Distribution Method

Description: An investigation of the solvent extraction behavior of salicylato- beryllium complexes is reported. A simplified method for calculating the stability constants has been developed. The values obtained are beta /sub 1/ = 4.0 x 10/sup 12/ and beta /sub 2/ = 4 3 x 10/sup 22/ in 0.15 M sodium perchlorate. (auth)
Date: November 1, 1961
Creator: Szego, L. E.
Partner: UNT Libraries Government Documents Department
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A Comparative Study of Two Grades of BeO

Description: Pechiney and Brush UOX BeO differ markedly in fabrication behaviour, only Brush UOX being readily sinterable. A comparative study of the two powders has shown few outstanding differences in powder properties. Both are of high purity but contain free and combined moisture to the extent of about 1.5 per cent. Pechiney BeO has a larger mean crystallite size (0.2 — 0.3μ) than Brush UOX (0.1 — 0.15μ) and a larger range of crystallite size, and both contain a small proportion of crystallites of size … more
Date: November 1961
Creator: Reeve, Keith Desmond, 1928- & Ramm, E. J.
Partner: UNT Libraries Government Documents Department
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Analysis of Mixtures of Alcohols by Acylation

Description: From abstract: "Recently a general chemical method for the analysis of mixtures of alcohols appeared, using pyridine catalyzed acetylation and second order kinetics to determine the amount of the faster reacting component. The use of 0.25M isobutyric anhydride in pyridine containing 0.0025M perchloric acid as catalyst promotes the rate of the reaction and diminishes the time necessary to perform an analysis. A mathematical treatment of the data and kinetic plot reduces the number of kinetic poi… more
Date: November 1961
Creator: Fellows, William Dean & Fritz, James S. (James Sherwood), 1924-
Partner: UNT Libraries Government Documents Department
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Alpha Particle Radiolysis of Anion Exchange Resins

Description: Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."
Date: November 1961
Creator: Ahrens, Rolland W.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, October 1961

Description: This document details activities of the irradiation processing department during the month of October, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: November 17, 1961
Partner: UNT Libraries Government Documents Department
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Proposed production test for reducing minimum downtime

Description: The object of the production test described in this report is to evaluate the operational aspects of a proposed method for reducing minimum downtime. The excess xenon poisoning, which occurs during the first 32--38 hours after the shutdown of a reactor from present equilibrium levels, will be partially overridden by a central enriched zone whose added reactivity contribution would be compensated during normal operation by means of poison splines.
Date: November 29, 1961
Creator: Jaklevick, J. F.
Partner: UNT Libraries Government Documents Department
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Economics of reusable crucibles

Description: A high expense item in the operation of the button line has been the RS-6 crucible which can be used only once. The 234-5 Research and Development Laboratory has done some preliminary development on a reusable crucible. Before continuing their program, they have requested that an economic study be made to determine what potential savings could be realized if RS-6 were replaced with a reusable crucible. For the purpose of this study, the costs involved were broken down into three areas: Button l… more
Date: November 1, 1961
Creator: Curran, R. G.
Partner: UNT Libraries Government Documents Department
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Production test IP-455-A comparison of N reactor inner fuel tubes with different pre-irradiation warp conditions

Description: The objective of this production test is to compare the irradiation behavior of N Reactor inner fuel tubes (NIE1 elements) having negligible warp after beta heat treatment to the behavior of NIE1 elements with extensive warp after beta heat treatment which were straightened and beta heat treated a second time. The information from this test will be used in the development of a program to evaluate the irradiation behavior of NIE1 elements in various conditions of pre-irradiation warp and straigh… more
Date: November 2, 1961
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Rear face piping study at elevated bulk outlet temperatures KE Reactor

Description: Accumulation of data on rear face piping strain, piping vibration, water pressures; and water temperatures at KE Reactor was recently completed. A preliminary review of this data indicates that much of the pressure and temperature data could be significant to the study regarding the capability of the K Reactor rear face piping to accommodate the proposed increased water flow. In view of this, a copy of the pressure-temperature data is attached. The purpose of the test was two-fold: (1) to estab… more
Date: November 9, 1961
Creator: Frieling, D. H. & Hutton, P. H.
Partner: UNT Libraries Government Documents Department
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D-Reactor Graphite Burnout Interim Report: IP-25A(PT-105-532-E)

Description: The oxidation rate of the moderator in D-Reactor has been monitored from samples placed along the length of process tube channel 3478. During the interval from August 8, 1960, to August 10, 1961 were very high, up to 40%/KOD (1000 operating days). From the shape of the front-to-rear burnout profile, the oxidant appears to be oxygen and/or water.
Date: November 10, 1961
Creator: Ryan, B. A.
Partner: UNT Libraries Government Documents Department
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Results of Laboratory Heat Transfer Experiments for C-Reactor Overbore Fuel Channels

Description: The purpose of this report is to present experimental data concerning the heat transfer and fluid flow conditions within a C-overbore geometry process channel for the cases of steady state operation, flow plugging incidents, and inlet piping failure incidents.
Date: November 10, 1961
Creator: Waters, E. D. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
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PT-IP-344-A-FP, Evaluation of Al-Si bond characteristics

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can-bond separation following irradiation. Such evidence h… more
Date: November 10, 1961
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Process improvement transition authorization IP-14-I: D Reactor full pile loading of bumper fuel elements

Description: The purpose of this Process Improvement Transition Authorization (PITA) is to authorize full pile loading bumper fuel elements in the fringe zone will be reviewed and, if desirable, recommendations to curtail fringe loading may be made based on economic considerations.
Date: November 18, 1961
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Processing data for coextruded fuel elements in ETR, KER and MTR Loops

Description: The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR element assemblies and K-type I&E{sup 2} for the following production tests: ETR, 6{times}6 Loop; GEH-10, Nos. 52, 53, 54 and 55; KER Loops; PT-377; MTR Loop; GEH-4, Nos. 68, 69 and 70. The purpose in documenting the data is to provide a permanent record of processing conditions and dimensions which may be referred to for post irradiation analysis and possible future… more
Date: November 8, 1961
Creator: Robinson, R. K.
Partner: UNT Libraries Government Documents Department
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