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A Laboratory Gas-Circulating Pump

Description: A pump was developed for pumping carbon dioxide in a closed loop without introducing impurities. This pump will give flow rates of up to 3 liters/min and will develop a working pressure of over 70 mm Hg. No wear was observed after 2000 hr of testing. It is felt that this pump is more desirable for this application than those developed by other experimenters for two reasons: relatively inexpensive construction of the pump and the associated electronic circuit and the low coefficient of friction … more
Date: November 30, 1961
Creator: McNabb, B. Jr. & McCoy, H. E. Jr.
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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Primary Piping Static Test Design Request

Description: It is requested that a design be initiated for the primary piping static test. This test is necessary to provide information as to the reliability of the pipe subjected to reactor operating conditions. The test conditions are as follows: temperature - 2000 F (isothermal), pressure effective - 42 psi, and test time - 10,000 hours. It will be necessary to test two sizes of pipe as shown on the preliminary piping layout (2.250-inch O.D. x .095-inch wall and 3 1/2 SCH. 10 pipe). The test specimens … more
Date: November 30, 1961
Creator: O'Brien, R.W.
Partner: UNT Libraries Government Documents Department
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PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II

Description: Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphi… more
Date: November 30, 1961
Creator: Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Partner: UNT Libraries Government Documents Department
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Request for Design of a Fuel Element Assembly Soak Test

Description: It is requested that the design be completed for a full-scale fuel element soak test. The test assembly must be designed to permit the fuel element test specimen to be submerged in a lithium bath under a pressure of 60 psi. The maximum temperature of the lithium is to be 2000 F. A total of four test units will be required to complete the test program. Two specimens will be exposed to a thermal cycle between 2000 F and 1400 F with the remaining two specimens being exposed to a thermal cycle betw… more
Date: November 30, 1961
Creator: Spahl, R.J.
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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Waste Treatment and Disposal Progress Report for August and September 1961

Description: Work is being carried out to develop and demonstrate on pilot plant scale integrated processes for treatment and disposal of radmoactive wastes. High-level waste calcination, low-level waste treatment, economic and hazards evaluation, engineering evaluation, disposal in deep wells, disposal in natural salt formations, Clinch River studies, fundamental studies of minerals, and White Oak Creek basin study are discussed. (M.C.G.)
Date: November 29, 1961
Creator: Blanco, R. E. & Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Experimental Stress Analysis of Egcr Pressure Vessel. Part 1. Experimental Determination of Stresses in Model. Part 2. Interpretation of Experimental Results and Examination for Structural Intergity

Description: Structural evaluations of the upper head of the EGCR pressure vessel were made. The configuration throughout the cluster region in the vessel was found to be structurally adequate. The primary and primary-plus-secondary stress intensities for the burst-slug detection and gas outlet nozzles were found to be within the allowable limits. However, the complete design evaluations of these units cannot be made until the temperature distributions are known. (auth)
Date: November 28, 1961
Creator: Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R.; Greenstreet, B. L.; LaVerne, M. E. et al.
Partner: UNT Libraries Government Documents Department
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Non-Destructive Analysis of Uranium in Graphite Fuel Elements by Neutron Activation

Description: A method is presented for the determination of uranium (as U/sup 238/) in uraniuni-loaded graphite fuel elenients by a non-destructive, direct radioactivity analysis technique. A 200-cbannel pulse-height analyzer, equipped with a 3 in. x 3 in. NaI(Tl) crystal, is used to measure the Np/sup 239/ radioactivity of the neutron-irradiated samples. The amount of U/sup 238/ in the test samples is deterimined quantitatively by comparing the Np/sup 239/ radioactivity induced in each sample with the Np/s… more
Date: November 28, 1961
Creator: Bate, L. C.; Hampton, W. J. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Single Element Flow Tests for Type 3 (SM-2) Fuel Elements in SM-1, SM-1A, and PM-2A Cores

Description: Channel-to-channel flow distribution within Type 3 (SM-2, stationary and control rod fuel elements modified for use in the SM-1, SM1-1A, and PM-2A core support structures and control rod tubes was measured in single element flow testing. Plots of channel-to-channel flow distribution and element pressure drop at various element flow rates are given. Flow distribution for the top-orificed SM-1A and PM-2A stationary elements was within the plus or minus 12% deviation from element average utilized … more
Date: November 27, 1961
Creator: Krause, P. S.
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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Evaluation of Wire Scanner for SM-1

Description: Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location,… more
Date: November 22, 1961
Creator: Kemp, S. N.
Partner: UNT Libraries Government Documents Department
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Helium Inleakage Through Porous-Walled Fuel Elements

Description: Theoretical and experimental studies indicated that the effective permeability coefficient for graphite is lowered by a helium stream in-sweeping through the graphite pores. This phenomenon was considered in the design of HTGR fuel elements. A portion of the helium gas which is drawn into each fuel element as a purge stream may enter through porous wall sections, supplementing the purge gas entering at the top of each fuel element. The purge stream leaves each fuel element through a header syst… more
Date: November 21, 1961
Creator: Turner, R. F.
Partner: UNT Libraries Government Documents Department
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SERVO SYSTEM FOR MAGNETIC CONTROLLED CONSTANT INTENSITY FLAT TOP BEAM SPILL- OUT

Description: It is noted that a uniform flat-top beam spill-out cannot be obtained in the Cosmotron by manual control. A servo system is proposed which will control this spill-out by sensing the external beam intensity, and correcting the magnet voltage to keep this intensity constant. This servo must operate through the transfer function of the main ignitron system and the flat-top filter. An analysis of these special transfer functions is presented. (J.R.D.)
Date: November 21, 1961
Creator: Cottingham, J.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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Effect of Mortar Properties on Strength of Masonry

Description: Report issued by the National Bureau of Standards over studies conducted on the effects of mortar on the strength of masonry. Materials, methods, and results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: November 20, 1961
Creator: Fishburn, Cyrus C.
Partner: UNT Libraries Government Documents Department
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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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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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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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NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961

Description: Fifty-seven papers and l7 abstracts of papers are presented in the report. Fifty two of the papers are abstracted separately; in addition, a single abstract is written to cover the section on Plasma Physics Theory, which contains 3 papers and 8 abstracts of papers. The two brief papers not abstracted separately are concerned with fast neutron detection, and homogeneous critical assemblies of 3%enriched UF/sub 4/-paraffin systems. (T.F.H.)
Date: November 17, 1961
Partner: UNT Libraries Government Documents Department
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New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry

Description: Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)
Date: November 17, 1961
Creator: Kofink, W.
Partner: UNT Libraries Government Documents Department
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OPTIMUM FILL VOLUMES IN POT CALCINATION OF RADIOACTIVE WASTES

Description: The 15,000 MW nuclear economy assumed for the long range study of pot calcination costs reported earlier was used as a basis for calculating optimum fill volumes. An algebraic expression was developed for cost as a functmon of the normalized radius of the central void space in a partially filled vessel. Minima of this expression were found for acmdmc and neutralized wastes in 6, 12, and 24in.-diameter vessels. Optimum fill volumes decreased as vessel diameter increased, varying for acidic waste… more
Date: November 17, 1961
Creator: Perona, J.J.
Partner: UNT Libraries Government Documents Department
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Research Study on Neutron Interactions in Matter as Related to Image Formation

Description: From abstract: "In this report we present data obtained with the optical simulation apparatus on image quality as a function of the parameters of neutron scattering and image detector resolution...Also included in this report is a brief description of a large area (5 inch diameter) neutron beam exposure facility being set up at the reactor for the phase three work."
Date: November 17, 1961
Creator: Watts, H. V. & Terrell, C. W.
Partner: UNT Libraries Government Documents Department
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