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Determination of Suitable Insulation for a 1-5/16" Helium Filled Annulus in the ORR Helium In-Pile Loop, Design No. 4

Description: Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1… more
Date: August 17, 1959
Creator: Knight, R. B. & Helms, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shut-Down Cooling of ORR

Description: The purpose of this memo is to present information which may be used in estimating the magnitude of the shut-down cooling problem in the ORR at various power levels. Using previously estimated data for the MTR (IDO-16443), a rough estimate of the space distribution of heat release after shut-down is presented.
Date: August 14, 1959
Creator: Cole, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Surface-Exchange Method for Determination of Surface Area of UO2 Powder

Description: Applicability of the surface-exchange method of determination of surface area of UO2 powder has been investigated. Preliminary results indicate that the method offers a rapid and easy determination of surface area with a precision of ~ 10%.
Date: August 6, 1959
Creator: Ferguson, R. L. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the "Active Deposit" of Thoron

Description: A description is given of the properties of the nuclides included in the "active deposit" of thoron. A method is presented for obtaining a quantitative measurement of the activity of the transient-equilibrium mixture.
Date: August 17, 1959
Creator: Reynolds, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phase Stability of Homogenous Reactor Hot Fuel Solutions

Description: Portions of two samples of HRT fuel solutions were sealed in silica capillary tubes approximately three weeks after they were removed from the reactor and the temperature at which each solution separated into two liquid layers was determined.This report gives the results of these observations.
Date: August 18, 1959
Creator: Barton, C. J.; Gill, J. S.; Hebert, G. M.; Marshall, W. L. & Moore, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: The Fluoride Volatility Process was developed to recover uranium from fused salt reactor fuels. After two testing runs had been completed processing was interrupted because of a UF6 leak. After all faulty connections and seals had been made gas-tight, processing of the ARE fuel was resumed and carried to completion. This report covers processing of the ARE fuel through the last four runs plus a summary of the entire ARE reprocessing program.
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Welded Seal-Ring Vacuum Closures

Description: This is a preliminary report dealing with the development of bakeable high-vacuum flanges for the ORNL PIG Facility. A number of flange designs are discussed together with fabrication, inspection, testing, and installation and maintenance information.
Date: August 21, 1959
Creator: Michelson, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods for Applying Transmission and n-vs-E Corrections in the Determination of n2200 by the Macklin-deSaussure Experiment

Description: A careful determination of n2200 from results of the Macklin-deSaussure manganese bath experiment involves corrections for (1) the weak but non-zero transmission of sub-cadmium neutrons through the uranium or plutonium foils, and (2) the small variation of n with energy in the sub-cadmium region. This report presents the derivation of a single general expression for applying both these corrections, and then describes two IBM 704 codes (MTC and GTC) which were written especially to facilitate th… more
Date: August 17, 1959
Creator: Halbert, Edith C.; Maskewitz, Betty F. & Wynn, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Dump Valve Trim in the Valve Test Loop and the Performance of Dump Valves in the HRT

Description: The Homogeneous Reactor Test requires an emergency valve for rapidly releasing the contents of each the core and blanket high-pressure system to its low-pressure system. This report describes the testing of dump valve trim in the Valve Test Loop and the performance of dump valves in the HRT to date.
Date: August 3, 1959
Creator: Hise, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Countercurrent Solid-Liquid Contactor for Continuous Ion Exchange

Description: From abstract: "A continuous countercurrent solid-liquid contactor has been developed which retains the desirable features of the conventional fixed bed and gains the advantages of countercurrent flow. It can be adapted to many solid-liquid mass-transfer processes such as ion exchange, silica gel adsorption, and ore leaching."
Date: September 19, 1952
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A New Anionic Solvent Extraction Technique

Description: From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The X-Ray Spectra of Polonium Atomic Number 84

Description: From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley… more
Date: April 15, 1952
Creator: Peed, W. F.; Burkhart, L. E.; Staniforth, R. A. & Fauble, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Gaps on Pile Reactivity

Description: From abstract: "The variation of the reactivity of a pile as a function of width of a transverse gap is obtained. The method involves first finding the boundary condition satisfied by the flux at the gap face. This, in principle, provides enough information for a complete solution of the pile equations. A method for calculating the reactivity change is presented. The calculated reactivity is compared with experiment and a brief discussion of the validity of the approximations is given."
Date: July 14, 1952
Creator: Tamor, S. & Ergen, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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