Technical Report Archive & Image Library (TRAIL) - 186 Matching Results

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Cross Section Program at ORNL

Description: Short reports to the members of the Nuclear Cross Section Advisory Group from three groups: (1) High voltage group; (2) Fast chopper time-of flight spectrometer; and (3) Electronuclear research division.
Date: January 21, 1957
Creator: Harvey, J. A. & Fowler, J. L. (Joseph L.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cracks in HRT Flange Bolts and Ferrules

Description: When it was discovered that two HRT flange bolts of a lot of 16 spares contained serious cracks, a program was launched to (1) determine the cause for the cracking, and (2) find methods for non-destructive testing the remainder of the 672 bolts shipment, a large portion of which had been installed in the HRT. Concurrently, inspection of 8 ferrules removed from an HRT flange revealed hairline cracking in 4 of them. Magnaglo, a magnetic particle inspection method using a fluorescent dye, proved t… more
Date: January 29, 1957
Creator: Hammond, J. P.; Adamson, G. M. & Kegler, T. M., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimated Gamma Radiation Levels at Access Holes in the HRT Shielding

Description: An estimate has been made of the gamma radiation levels at access holes in the HRT Shielding when the plugs have been removed to service or maintain the reactor. In every case the radiation level at the holes was greater than the maximum permissible exposure rate of 0.3 roentgens per week. The radiation through the holes can be attenuated to some extent by flooding the reactor cell up to the flange to be disconnected. However, shielding would still be required and it is more practical to provid… more
Date: January 24, 1957
Creator: Collins, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957

Description: A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the soluti… more
Date: January 31, 1957
Creator: Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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HRT Temperature Measurement System - Issue No. 3

Description: The following temperature measurement tabulation consists of two parts. Part I lists all HRT thermocouples, their location, the junction box thru which the leads pass, and their termination, if on an instrument. Part II lists all temperature read out instruments and their location. A total of 577 thermocouples are listed in this tabulation. The roughly 77,000 ft of wire used in connecting them up cost $6,799. Temperatures are read on 24 instruments. Cost of these was approximately $15,688. Acce… more
Date: January 17, 1957
Creator: Grimes, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test

Description: Chloride-induced stress-corrosion cracking has been encountered in the Homogeneous Reactor Test during the preliminary testing. The rector is constructed of austenitic stainless steels. It is unique in that it will operate at 250 to 300 C with an aqueous uranyl sulfate solution fuel containing 200 to 500 ppm of dissolved oxygen. The cracking has occurred in a secondary system used for detecting leaks in the flanged joints of the primary systems and in the grooves of flanges in the primary syste… more
Date: January 31, 1957
Creator: Bohlmann, E. G. & Adamson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

Description: The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Chemical Processing of Two-Region Aqueous Homogenous Reactors

Description: A promising scheme for the chemical processing of a thorium breeder reactor of the two-region aqueous homogeneous type consists of the following operations: concentration of insoluble fission and corrosion products from the core system into a small volume of fuel solution, combining this slurry with irradiated thorium oxide slurry taken from the blanket, recovery of D2O by evaporation, dissolution of the thorium and uranium in HNO3, and, after a suitable cooling period, recovery of the uranium … more
Date: January 29, 1957
Creator: Ferguson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Irradiation of Thorium and Uranium Oxides Slurries

Description: Thorium and thorium-uranium oxide slurries were irradiation in the Low Intensity Test Reactor (LITR) at temperatures up to 300C in small stirred autoclaves. Stirring was accomplished by means of an electromagnetically operated lunger. Stirrer operations was monitored suing an oscilloscope. Relative slurry viscosities were determined both in and out-of-pile using calibration curves of apparent viscosity versus stirrer rise time. Post-irradiation examination of selected slurries indicated no gros… more
Date: January 29, 1957
Creator: Krohn, N. A. & McBride, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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Determination of Submicron Particle Sized by an Activation Analysis - Centrifugation Method

Description: The feasibility of determining particle sizes in the submicron range by employing an activation analysis - centrifugation method has been demonstrated. It is believed that this method is now applicable to the analysis of thorium oxide for submicron particles. The same techniques are, in most instance, usable in determining particle sized in other sample materials.
Date: January 29, 1957
Creator: Bate, L. C. & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Catalysts for Recombination of Radiolytic Gases Over Thorium Oxide Slurries

Description: Catalysts for use in recombining the gases produced by the radiolytic decomposition of water in thorium oxide slurries under neutron irradiation were investigated in out-of-pile tests using stoichiometric mixtures of hydrogen and oxygen. Most favorable results were obtained with a molybdenum oxide catalyst. Satisfactory rate also were attained with palladium and silver oxides. Copper, nickel, vanadium and chromium compounds were less effective.
Date: January 29, 1957
Creator: Morse, L. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgical Examination of HRT Leak Detector Tubing and Flanges

Description: After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It… more
Date: January 31, 1957
Creator: Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Source Shield Calculations

Description: Calculations indicate that the proposed shielding arrangement will give a dose rate at the surface of the water tank of about 100 mrem per hr., practically all gammas. This is adequate for transportation and handling, but if the radiation actually proves to be this high, a storage location isolated from normal working areas must be provided. The isolation area need not be large, however, since the calculated dose rate at 10 feet from the shielded sources is only 3.5 mrem pr hr. For the short ti… more
Date: January 8, 1957
Creator: Haubenreich, P. N. & Rivenbark, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Eddy-Current Measurement of Clad Thickness on Mark X MTR Fuel Plates

Description: At the request of the Alloy Preparation Group, the Nondestructive Test Development Group investigated the feasibility of determining the clad thickness on Mark X MTR Fuel Plates. As the use of induced eddy-currents was considered to be the most promising approach, a prototype instrument and probe coil utilizing this principle was developed to measure clad thickness. The results of the investigation conducted with this instrument indicate that the clad thickness of this type of fuel plats can be… more
Date: January 23, 1957
Creator: Oliver, R. B.; Allen, J. W. & Nance, Roy A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Delay Time Prior to Dumping the HRT

Description: Some refined calculations have been made, relative to a proposed delay prior to a dump, to determine the expected D2 concentration in the vent stream from the pressurizer gas bleeds during a dump of the Homogeneous Reactor Test (HRT). These calculations indicate that for vent valves have a Cv of 0.07 (venting time from 2000 psia to D2O saturation pressure of approximately 12 minutes), a delay period is not required since the D2 concentration is well below lower explosive limit. For vent valves … more
Date: January 10, 1957
Creator: Gift, E. H. & McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure

Description: Few data exist for the thermal conductivity and viscosity of gases at very high pressure. The possibility of using gases for heat transfer media at pressures up to 100 atmospheres and above raised the problem of estimating variations in the conductivity and viscosity at high pressure. Generalized plots are presented which are based on the work of Enskog, Eucken, and Hirschfelder et al. Some pertinent data from Hirschfelder et al and from Hilsenrath et al are presented.
Date: January 17, 1957
Creator: Lyon, Richard Norton
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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High Pressure Recombination Loop Progress Report

Description: The operation and design of a high pressure recombination loop for the recombination of H2, D2, and O2 produced by the radiolytic decomposition of water which is used a solvent for fuel in the homogeneous reactors are presented.
Date: January 4, 1957
Creator: Harley, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Secondary Refrigerant for HRT Refrigeration System

Description: The criteria for selection of an HRT secondary refrigerant system refrigerant to replace Freon-11 are given. The properties of Amsco which make it desirable are tabulated and it is compared with triethyl phosphate (the second choice) and Freon-11.
Date: January 24, 1957
Creator: Robertson, R. C. & McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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HRT Sampler Development

Description: A prototype sampler for obtaining samples of high radioactive UO2SO4 solution for use in the HRT is presented. It was successfully operated in conjunction with a low pressure water system and a high pressure, high temperature UO2SO4 system.
Date: January 22, 1957
Creator: Hannaford, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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