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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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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Mammalian Radiation Genetics

Description: "This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in … more
Date: August 11, 1952
Creator: Russell, W. L.
Partner: UNT Libraries Government Documents Department
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Organo-Phosphorous Compounds for Solvent Extraction

Description: From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher … more
Date: August 14, 1952
Creator: Higgins, C. E.; Baldwin, W. H. & Ruth, J. M.
Partner: UNT Libraries Government Documents Department
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Protective Equipment Evaluation Program Quarterly Progress Report: July-September 1951

Description: This quarterly progress details the ongoing work of the Protective Equipment Evaluation Program at the Oak Ridge National Laboratory. Topics discussed include aerosol generation, penetration studies, particle size measurement, and an appendix with analytical methods.
Date: August 6, 1952
Creator: Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Heat Transfer and Pressure Loss in Tube Bundles for High Performance Heat Exchangers and Fuel Elements

Description: From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this… more
Date: August 12, 1952
Creator: Cohen, G. H.; Fraas, A. P. & LaVerne, M. E.
Partner: UNT Libraries Government Documents Department
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Laboratory Development of the MTR-RaLa Process for the Production of Barium140

Description: From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).
Date: August 19, 1952
Creator: Blanco, R. E., (Raymond Eugene), 1918-1987; Kibbey, A. H.; Pannell, J. H.; Shank, E. M.; Farmer, J. E.; Helton, D. M. et al.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

Description: In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report July 1959

Description: Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Partner: UNT Libraries Government Documents Department
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Temperature and Rate of Heat Removal of UO2 Test Elements

Description: The method of calculation of various quantities relating the temperature and the rate of heat removal of UO2 test elements is presented. Graphs of the appropriate quantities as a function of the rate of heat removal are included.
Date: August 5, 1959
Creator: Perry, A. M.
Partner: UNT Libraries Government Documents Department
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Core Levitation in the EOCR in Case of Main Coolant Pipe Failure

Description: This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will pr… more
Date: August 4, 1959
Creator: Fontana, M. H.
Partner: UNT Libraries Government Documents Department
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Calculation of Transport Cross Sections

Description: Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
Partner: UNT Libraries Government Documents Department
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The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions

Description: Preliminary measurements of the corrosion of titanium were made in 13 M HNO3-0.05 M fluoride using 0.1 M H3BO3 as a liquid and vapor phase complexing agent. Titanium Ax-55 was attacked at average rates of 0.58 and 0.33 mils/month in the liquid and vapor. In dissolver solutions containing 0.5 and 1.0 M titanium, all rates were less than 0.1 mils/month.
Date: August 6, 1959
Creator: Kitts, F. G.
Partner: UNT Libraries Government Documents Department
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Radiators for Space Power Plants

Description: An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the… more
Date: August 7, 1959
Creator: Fraas, A. P.
Partner: UNT Libraries Government Documents Department
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