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Preliminary MSRE Gamma Ray Source and Biological Shielding Survey

Description: The major gamma ray sources and some of the resultant biological shielding requirements have been evaluated at both full power operation and following shut down for the Molten Salt Reactor Experiment. The sources include gamma rays due to the fission events in the reactor and those associated with activation of materials. Shielding estimates were made for the reactor system cells and for some maintenance facilities.
Date: April 28, 1961
Creator: Vroom, D.W.
Partner: UNT Libraries Government Documents Department
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HRT Mockup Runs CS-25 and CS-26

Description: Two runs, CS-25 and CS-26, were carried out in the HRT (Homogenous Test Reactor) Mockup at Oak Ridge National Laboratory to define permissible solution compositions for operation in the HRT.
Date: April 26, 1961
Creator: Jones, J.E., Jr.
Partner: UNT Libraries Government Documents Department
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Neutron Losses to Pa-233 in the Aqueous Homogenous Breeder Reactor

Description: Neutron losses to Pa-233 in the blanket of the AHBR were computed and compared for two cases: (1) concentration of Pa-233 is maintained uniform by continuous mixing, (2) batches of fertile material are shifted periodically from high- to low-flux regions of blanket. It was found that, if the fertile material is cycled through three radial positions in three days, the loss of neutrons to Pa-233 is no more than one per cent greater than if it is mixed continuously.
Date: April 26, 1961
Creator: Miller, J.W. & Alexander, L.G.
Partner: UNT Libraries Government Documents Department
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Some Temperature Aspects of the HFIR Control Plate System

Description: This study examines the effects of water flow rate through the control region on local bulk water temperature and on control plate surface temperature, radial thermal expansion, and thermal stress. Flow rates of 1200, 800 and 400 gpm are considered for each of three control plate positions typical of startup, mid-cycle, and end-of-cycle. Based on the factors investigated in this study, the calculations indicate that a flow rate as low as 400 gpm may be reasonable.
Date: April 18, 1961
Creator: Haack, L.A.
Partner: UNT Libraries Government Documents Department
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Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, had operated for the bulk of the test programs in the temperature range 1000-1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-inch), the location of damaged areas varying with impeller geometry.
Date: April 10, 1961
Creator: DeVan, J.H.
Partner: UNT Libraries Government Documents Department
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Preparation and Specifications of Miniature Fermi Reactor Core B Fuel Specimens for Irradiation Testing

Description: The preparation of miniature plate specimens containing dispersions of 33.2 wt % UO2 in type 347 stainless steel for irradiation testing is described. These plates stimulate the prototype roll-bonded stainless steel clad composite plates intended for the Core B fuel element of the Enrico Fermi sodium-cooled reactor. The significant characteristics of the fabricated irradiation specimens are tabulated. The samples will be used to determine the irradation behavior of 33.2 wt % UO2 at temperatur… more
Date: April 21, 1961
Creator: Cherubini, J.H. & Williams, R.C.
Partner: UNT Libraries Government Documents Department
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Evaluation of Electroless Nickel Brazed Tube Bundles

Description: Two arrays of stainless steel tubes and ferrules which had been electroless nickel brazed were submitted for metallographic evaluation. These represented the first and second attempts of Ferrotherm of Cleveland to fabricate fuel bundles using the procedures outlined by Westinghouse Atomic Power Department for the Yankee Power Reactor.
Date: April 26, 1961
Creator: Crouse, R.S.
Partner: UNT Libraries Government Documents Department
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Temperature Transients Due to Density Changes on Changing Power Level in the HRT

Description: Changing the power level in the HRT leads to small average density changes in the high pressure system which produce noticeable changes in the nuclear average temperature. It is calculated that taking the reactor from zero power to 5Mw in one-half hour will lead to a temperature rise of about 0.7 degrees C, followed by a gradual fall over a two-hour period to about 1.3 degrees C below the temperature at zero power.
Date: April 6, 1961
Creator: Tobias, M.L. & Vondy, D.R.
Partner: UNT Libraries Government Documents Department
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MSRE Preliminary Physics Report

Description: This report is a compilation of the results of reactor physics calculations to date for the currently proposed Molten Salt Reactor Experiment (MSRE) core design. Estimates have been made of the reactor characteristics using the core model and calculation methods discussed in Reactor Model and Calculation Methods; these results are presented in Table 1 and discussed in Results. Consideration is given to the problems of fission product buildup, fuel salt and Xe-135 retention by the core graphite… more
Date: April 19, 1961
Creator: Nestor, C.W., Jr.
Partner: UNT Libraries Government Documents Department
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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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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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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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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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