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An Evaluation of the Present Status of Swirl-Flow Heat Transfer

Description: Available swirl-flow data for pressure drop, heat transfer under both nonboiling and boiling conditions, and burnout have been collected and compared on common bases. Though different sets of data are in some disagreement, semiquantitative overall trends are discernible. It is shown that swirl flow allows attainment of greater heat-transfer rates under a variety of conditions, both without boiling and at burnout, than are characteristic of axial flow at the same pumping power.
Date: April 24, 1961
Creator: Gambill, W.R. & Bundy, R.D.
Partner: UNT Libraries Government Documents Department
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FPV-1, An IBM-7090 Code

Description: This IBM-7090 code has been programmed to be run under control of the monitor system. FPV-1 calculates the neutron flux level at a surface due to a finite cylindrical diffusing neutron source.
Date: April 18, 1961
Creator: Tsagaris, M.E. & Delene, J.G.
Partner: UNT Libraries Government Documents Department
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On the Activities in the Plant Off-Gas

Description: Measurements were made of the activities in the Laboratory off-gas and efficiencies of the gas cleaning facility were calculated. Sampling was done isokinetically and, by the use of filter paper and charcoal traps, particulates and adsorbable gases were collected.
Date: April 19, 1961
Creator: Fujii, S.; Manneschmidt, J.F.; Mackey, T.S. & Woodall, E.W.
Partner: UNT Libraries Government Documents Department
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Re-evaluation of the Activated Charcoal Fission Gas Adsorber for the Leak Detection System of the GC-ORR Loop No. 1

Description: The nitrogen leak detection system charcoal trap for the GC-ORR Loop No. 1 is re-evaluated under modified operating conditions and using recent laboratory data concerning the adsorption of krypton and xenon from very slowly moving gas streams. This experiment is being conducted in support of the Experimental Gas-Cooled Reactor (EGCR) being built at Oak Ridge and is designed to study the operating characteristics of UO2 fuel specimens clad with stainless steel.
Date: April 14, 1961
Creator: Adams, R.E. & Browning, W.E., Jr.
Partner: UNT Libraries Government Documents Department
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Neutron Multiplication Experiments with Enriched Uranium Metal in Slab Geometry

Description: The determination of critical dimensions of both individual units and arrays of units of fissionable material, in simple shapes and with minimal interference from supports, etc., has been a continuing program at Oak Ridge National Laboratory. In the experiments presently reported, uranium metal slabs were assembled, and although not made critical, produced sufficient source neutron multiplication to allow quite precise estimation of the critical thickness.
Date: April 10, 1961
Creator: Mihalczo, J.T. & Lynn, J.J.
Partner: UNT Libraries Government Documents Department
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Use of 4Pi High-Pressure Ionization Chambers as Secondary Standards for Calibration of Gamma-Ray Sources

Description: This memorandum is intended to serve as a nearly final draft of a section of a future report on an experiment to determine the spectrum of gamma-rays given off during U-235 fission. For this purpose it is necessary to give adequate details to expose the major bases of the spectrometer calibration in the lower energy regions.
Date: April 17, 1961
Creator: Peelle, R.W.
Partner: UNT Libraries Government Documents Department
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Operation of the EGCR Purification System Prototype

Description: Tests were conducted on a small-scale model of the experimental gas-cooled reactor (EGCR) at the Oak Ridge National Laboratory to determine the effectiveness of the system in removing gaseous impurities from circulating helium. Results indicated that hydrogen, carbon monoxide, and methane could be satisfactorily removed by oxidation in a catalytic converter.
Date: April 3, 1961
Creator: MacPherson, R.E.
Partner: UNT Libraries Government Documents Department
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Evaluation of Iodine Vapor Absorbers for the Low Intensity Test Reactor (LITR) Off-gas Systems

Description: The Low Intensity Test Reactor (LITR) was a light water moderated and cooled, beryllium reflected, heterogenous, enriched uranium reactor developed at the Oak Ridge National Laboratory. A proposed addition of an iodine vapor adsorber to the off-gas system of the LITR is evaluated by comparing the atmospheric radiation doses to laboratory personnel that could result in the event of a partial reactor core meltdown in one case while utilizing the present off-gas system and in the other case with … more
Date: April 12, 1961
Creator: Adams, R.E. & Browning, W.E., Jr.
Partner: UNT Libraries Government Documents Department
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Nuclear Characteristics of Possible Replacement Reactors for the HRT

Description: This data in this report summarize nuclear characteristics on several variables for possible replacement reactors for the Homogenous Test Reactor (HRT) at the Oak Ridge National Laboratory.
Date: March 28, 1961
Creator: Vondy, D.R. & Tobias, M.
Partner: UNT Libraries Government Documents Department
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Progress Report for February-March 1961 - Chemical Development Section C, Chemical Technology Division

Description: This report summarizes certain activities by the Oak Ridge National Laboratory's Chemical Technology Division, which focused on chemical separation processes relevant to nuclear fuel reprocessing, from February to March 1961. It includes data from experiments exploring the recovery of thorium and uranium from granitic rock, fission product (cesium) recovery, final cycle plutonium recovery by amine extraction, and the separation of transplutoniums from lanthanides.
Date: August 15, 1961
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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Progress Report - Pneumatic Temperature Measuring System

Description: This research report details developments in the effort to predict the speed of response of the basic pneumatic probe at the Oak Ridge National Laboratory.
Date: March 3, 1961
Creator: Hochreiter, H.M.
Partner: UNT Libraries Government Documents Department
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TrU Facility - Alpha Box Accessories - Manipulator Operable Spherical Joint Clamp

Description: A special clamp has been designed and developed which is manipulator operable and which will clamp a standard spherical (glass) joint. This version of the clamp can be pre-adjusted to securely lock on the joint, owing to the incorporation of an adjustable seat for the over-center clamp.
Date: July 22, 1961
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department
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TrU Facility - Alpha Box Accessories - Spherical Joint Clamp

Description: This report details the specifications of a clamp designed to be remotely manipulator operator and which clamps a standard spherical (glass) joint. This clamp was needed and will be used in conjunction with operational equipment within an alpha-tight box used in connection with the Transuranium process in the TrU Facility.
Date: March 28, 1961
Creator: Klima, B.B.
Partner: UNT Libraries Government Documents Department
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HECT II Compressor Pressure Drop Test

Description: In applications where more than one HECT II compressor is used in a loop, in either parallel or series arrangement, it becomes important to know the pressure drop across an inoperative compressor for both the "turbine stationary" and the "turbine free" conditions over a considerable flow range of the flowing medium. This report contains the results of pressure drop tests conducted with air at 14.7 psia and 80 degrees F.
Date: March 30, 1961
Creator: Flint, F.A.
Partner: UNT Libraries Government Documents Department
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CANE Sequenced Sampler for Project Gnome: Design Proposal

Description: A design is proposed for sampling apparatus to draw a sequence of samples from a filtered gas stream from a contained explosion. The apparatus is to be designed, fabricated, and installed in Project Gnome under the ORNL CANE Problem.
Date: March 15, 1961
Creator: Landry, J.W.
Partner: UNT Libraries Government Documents Department
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Analysis of HRT Behavior

Description: This report, published for distribution by the Oak Ridge National Laboratory, outlines the methods being used in attempts to establish a mechanism which will account for the fluctuations observed in the power trace of the HRT.
Date: March 13, 1961
Creator: Kasten, Paul R.
Partner: UNT Libraries Government Documents Department
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Measured Circulation Rates in the HRT

Description: This report details circulation rate calculations for the fuel and blanket high-pressure systems using measured pressure drops across heat exchangers at the Oak Ridge National Laboratory. Accurate values for flow rates through the core and blanket are important in the analysis of reactor operation and solution behavior.
Date: March 20, 1961
Creator: Kolb, J.O.
Partner: UNT Libraries Government Documents Department
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HFIR Pool Criteria

Description: This report presents a summary of the current status of design studies concerning biological shielding and heat removal requirements of the HFIR reactor pool, clean pool, and the critical facility pool. The purpose of this report is to provide a basis for proceeding with Title II design of the HFIR pool and pool coolant systems.
Date: March 16, 1961
Creator: Winters, C.E.
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 19

Description: This report details damage and impacts to operations and maintenance resulting from failures of the blanket circulating pump and fuel circulating pump at the Oak Ridge National Laboratory during a startup on February 5, 1959. The reactor was critical for 18 hours.
Date: March 16, 1961
Creator: Beall, S.E.
Partner: UNT Libraries Government Documents Department
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Fission Product Transport Through Graphite Matrices

Description: The transport of fission products from points of origin in unclad graphite matrix-types fuels to the reactor circulating system involves, as one of the steps, diffusion through the graphite matrix to the fuel element surface. An important problem is the determination of the effective transport rates of the various mobile elements (e.g., Xe, Kr, I, Br, Cs, Rb, and Te) and their daughter products of interest (Sr, La, Ba, Ca, Nb, Y and Te) through various graphites suitable for use as fuel elemen… more
Date: March 21, 1961
Creator: Korsmeyer, R. B.
Partner: UNT Libraries Government Documents Department
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