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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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A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL

Description: Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]
Date: December 4, 1950
Creator: Booksbank, W. A., Jr.; Emmons, A. H.; Gost, J. W. & Reynolds, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

[3D Viewer]

Description: Black cardboard viewer with plastic lenses, "for printed stereo photographs." It has scored portions and instructions for folding the cardboard to create a standing viewer to look through the lenses and keep the image at a distance.
Date: 1965
Creator: Stereo Magniscope, Inc.
Item Type: Refine your search to only Physical Object
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Final Safeguards Report, Volume 6: Environmental Analysis OF NS "Savannah" Operation at Camden

Description: "An analysis is presented of the accidental release of activity following the operation of the NS "Savannah" at the New York Shipbuilding Corporation docks in Camden, New Jersey. Although a number of accidents are considered, the report is primarily concerned with the environmental activity levels and subsequent exposures which would result from the "maximum credible accident" (p. v).
Date: January 24, 1961
Creator: Cottrell, W. B.; Parker, F. L.; Mann, L. A. & Schmidt, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status and Future Program of Homogeneous Reactor Fuel Processing Studies

Description: The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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