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Summary of Corrosion Data for HRT Mockup Operational Period Ending November 5, 1956

Description: The operation of the HRT mockup was on 0.042m UO2SO4, 0.024m H2SO4, and 0.005m CuSO4 at 280 C and 1400 psi pressure. with the O2 content at near 500 ppm. The pump showed bearing wear and high corrosion. The letdown heat exchanger was removed from the mockup and sectioned. The metallographic examination revealed corrosion. Results of corrosion runs on Ti, zircaloy-2, and stainless steel are given.
Date: May 22, 1957
Creator: Wacker, R. E. & Griess, J. C.
Item Type: Refine your search to only Report
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Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work

Description: This report supersedes ORNL CF-57-2-1, which was an extension and revision of ORNL CF-54-6-72. Details concerning a recommended system of flow-plan symbols and drawing are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. The system is a modification of the Instrument Society of American Recommended Practice … more
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. G. & Lieberman, B.
Item Type: Refine your search to only Report
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TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation

Description: A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date: March 18, 1957
Creator: Long, J. T.
Item Type: Refine your search to only Report
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Temperature Effects on the Measurement of Aqueous Liquid Level by the Differential Pressure Method and Recommendations for Placement of Taps on the HRT Replacement Heat Exchanger

Description: Increasing temperature in an aqueous liquid system results in a decrease in liquid density and an increase in vapor density. When level is measured by the differential pressure method, temperature increase results in a decrease in the effective span f the instrument and a shift in zero. When the instrument reference leg is uncompensated, both zero and span shifts occur with the effects being most pronounced at the high levels. When the reference leg is compensated, zero shifts are eliminated (i… more
Date: April 26, 1957
Creator: Moore, R. L.
Item Type: Refine your search to only Report
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Test of Stainless Steel Freeze Jacket to be Used on 1/2-inch High Pressure and High Temperature Process Lines

Description: In order to test the operation of a freeze jacket in air with the process fluid closely following the conditions found in the high pressure circulation loop of a homogeneous reactor, or, 2000 psi and 300C, a test loop was built and used in conjunction with existing refrigeration equipment. The freeze jacket was made of 5/16-in. type 346 stainless steel tubing wrapped around and welded to a 1/2-in. stainless steel process line. It was concluded that for these reactor operating conditions, only a… more
Date: January 21, 1957
Creator: Draper, B. D.
Item Type: Refine your search to only Report
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Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop

Description: Tests have been completed on a combination heater-cooler unit for use in in-pile loops designed to operate in beam hole HN-1 of the ORR facility. The unit is designed to use air-water mixtures as the coolant. the coolant flows through a spiral of 3/8-inc. diameter tubing cast in aluminum around the 3/8-in. IPS loop pipe. four 1000-w calrod-type electric heating elements are cast into the aluminum, along with the cooling coils to provide loop heating.
Date: June 28, 1957
Creator: Mauney, T. H. & Savage, H. C.
Item Type: Refine your search to only Report
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Testing of Adsorptive Capacity of Charcoal Beds : HRT Test No II-A 10 b

Description: During the pre-startup phase of the HRT operations, moisture was accidentally introduced into the charcoal bed adsorbers in the off-gas system. Tests have been made to determine the effect of wetting upon the adsorptive properties of the charcoal. The work was divided into two phases, testing of fresh charcoal in the laboratory and testing of the HRT charcoal beds in situ. It is recommended that the beds be dried by heating them to about 40 C and purging each with one to two liters/min of dry i… more
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R.R.
Item Type: Refine your search to only Report
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Thermal Characteristics of a Delta Array Heat Exchanger

Description: The heat transfer and fluid friction characteristics have been determined for a liquid flowing parallel to the tube bundle of a heat exchanger consisting of one hundred and two 1/16-inch O.D. tubes arranged in a delta or triangular array. These results may be expressed by empirical equations.
Date: January 28, 1957
Creator: Wantland, J. L.
Item Type: Refine your search to only Report
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Thermal Conductivity of Beryllium : Literature Survey

Description: Lewis in 1929 determined the thermal conductivity of beryllium metal for the first time. The next measurement reported in the open literature on the thermal conductivity of beryllium was by Powell in 1953. Measurements were also made by Grenell, Linebrink, and Johnson at Battelle Memorial Institute in 1947. Their values are in good agreement with those of Powell.
Date: February 12, 1957
Creator: Powers, W. D.
Item Type: Refine your search to only Report
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Thorex Pilot Plant ; System for Concentrating Second Uranium Cycle Product

Description: A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of the total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29… more
Date: January 28, 1957
Creator: Albrecht, W. L.
Item Type: Refine your search to only Report
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Thorium oxide Slurry Falling Ball Viscometer : Final Co-op Report, Winter, 1957

Description: A falling ball viscometer under development at ORNL, employing a flow system and an electromagnetically operated dash-pot pump, was evaluated for possible use with aqueous ThO2 slurry systems under reactor irradiation. Interchangeable check valve inserts were designed and fabricated to investigate several pump designs. Magnetic flux concentrations which originally prevented circulation of the ferritic stainless steel viscometer ball through the electromagnetic pump were eliminated by substituti… more
Date: April 10, 1957
Creator: Novak, P. E.
Item Type: Refine your search to only Report
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Trip to Selas Corporation of America

Description: On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date: June 18, 1957
Creator: Franco-Ferreira, E. A.
Item Type: Refine your search to only Report
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Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Item Type: Refine your search to only Report
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Uranium-235 Abundance by Gamma Spectrometry

Description: Techniques are described for determining U-235 abundance by measurement of the intensity of 0.18 Mev gamma radiation. One method involves measurement of the ratio of the intensity of 0.18-Mev radiation to that of 0.1 Mev radiation. The preferred technique consists of chemical separation of uranium followed by direct counting of 0.18-Mev photons. Application has been made in analysis of uranium samples of abundances in the range of 0.05% to 93%. Accuracy appears to be better than 3% if the abund… more
Date: January 2, 1957
Creator: Reynolds, S. A. & Eldridge, J. S.
Item Type: Refine your search to only Report
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Uranium Recovery for Spent Fuel by Dissolution in Fused Salt and Fluorination

Description: A promising nonaqueous process for the recovery of uranium from spent fuel elements is under development at Oak Ridge National Laboratory. This process consists of dissolution of the fuel element in a fluoride melt by hydrofluorination at 600 to 700°C, direct fluorination with fluorine for the production and volatilization of UF6, with further decontamination of the product UF6 from fission product activity being secured in a NaF absorption-desorption step. Good decontamination is obtained in t… more
Date: January 29, 1957
Creator: Cathers, G. I.
Item Type: Refine your search to only Report
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Volatility Pilot Plant : Design of a NaF Packed Tower for Removing HF from Fluorine

Description: A 4-ft-7-in. adsorption column packed with 1/8 in. sodium fluoride pellets was designed to reduce the hydrogen fluoride content of the fluorine being used by the Volatility Pilot Plant from 5% to less than 0.01%. It will be a non-isothermal packed bed with the bas inlet heated to 100 C to avoid plugging and the exit cooed to 25 C for more complete HF removal.
Date: March 7, 1957
Creator: Watson, J. S.
Item Type: Refine your search to only Report
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The Volatilization of Fission Products by Melting of Reactor Fuel Plates

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and… more
Date: July 15, 1957
Creator: Parker, Geogre W. & Creek, George E.
Item Type: Refine your search to only Report
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