Technical Report Archive & Image Library (TRAIL) - 17 Matching Results

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Chemical Development Section C Progress Report for December 1960 and January 1961

Description: Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nit… more
Date: June 2, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Experiment Off-gas System for the EGCR-LITR Capsule Experiment

Description: A proposed modification to the experiment off-gas system for the EGCR-LITR Capsule Experiment is evaluated by comparing the atmospheric radiation doses to laboratory personnel that could result in the event of an experiment failure while utilizing the present off-gas system to those doses that would result if various modifications to the existing system were effected. The modifications considered include the addition of an iodine vapor adsorber and a krypton-xenon adsorber. The addition of an i… more
Date: September 2, 1960
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction of the elements with Tris-2-Ethylhexyl- and Trihexylphosphine oxides from Acidic Solutions

Description: This technical report is the second of a series which concerns the separation of ions by solvent extraction with trialkyl phosphine oxides (TOPO). This investigation has consisted in the extraction of various ions from acidic solutions with extractants that are representative of these ore specific phosphine oxides - triphenylphosphine oxide (THPO) and tris-2-ethylhexylphosihine oxides (TEHPO). In general it is observed that: (a) the order of increasing capacity of extraction is THPO > TOPO >TEH… more
Date: January 2, 1957
Creator: Ross, W. J. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel-Cycle Analysis and Proposed Fuel and Burnable Poison Distribution and Loading for the HFIR and HFCE-2

Description: Further calculations have been made to determine the desired radial fuel distribution in the HFIR and in the forthcoming HFIR critical experiment. In the process the design of the core was changed to include a 1-cm-thick annular space of water between the two nearly equally thick fuel annuli, a metal-to-water ratio in the fuel annuli of 1.0 (0.050 in. thick plates and coolant channels ) was specified, and the active length of the core was increased from 18 to 20 in. Results of the calculations … more
Date: February 2, 1961
Creator: Cheverton, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Cost for Aqueous Homogeneous Reactors

Description: By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year do… more
Date: June 2, 1959
Creator: Culler, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Corrosion Samples -- Additional Data on Specimens Removed Prior to Run No. 20.

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, com… more
Date: February 2, 1961
Creator: Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Semiannual Progress Report

Description: From July through December, a total of 1750 hr of computer time was used by programmers in "debugging" and in running problems. With the acquisition of a second operator, the evening shift was initiated. A night-shift operator is presently being trained, and third-shifts operations will probably begin after completion of the magnetic-tape memory. / Engineering time is regularly scheduled for 4 hr each morning and 1/2 hr late in the afternoon. An electronic technician is on duty during evening-s… more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Semiannual Progress Report for Period Ending April 10, 1956

Description: Progress report of the Oak Ridge National Laboratory Metallurgy Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output and summaries of general corrosion, dynamic corrosion, mechanical properties, nondestructive testing, welding and brazing, fabrication, physical chemistry of corrosion, HRP metallurgy, the package power reactor program, APPR absorber, metallurgical materials and processing, metallography, ceramics, fundam… more
Date: November 2, 1956
Creator: Frye, J. H., Jr.; Manly, W. D. & Cunningham, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ORIC R-F Model III Progress Report

Description: The ORIC (Oak Ridge Relativistic Isochronous Cyclotron) radiofrequency system for which Model III represents the resonator is the third system which has received enough consideration to warrant construction of a model. The purpose of the model is to check the calculations for the frequency range and excitation power of the resonator. After an introductory description of the r-f system and model, the detailed calculations of the properties of the model will be given followed by the data from me… more
Date: June 2, 1959
Creator: Worsham, R. E. & Mosko, S. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure Rise in HRT Shield Due to Reactor and Replacement heat Exchanger Rupture

Description: .Recalculations were made of HRT cell pressures in the event of a simultaneous rupture of the reactor core vessel and the fuel and blanket heat exchangers. These calculations will be applicable after the replacement fuel heat exchanger is installed. The pressure rise in the cell is plotted as a function of time. A maximum cell pressure of 34 psig is achieved ~7 sec after rupture.
Date: April 2, 1957
Creator: Bolger, J. C.; Maak, R. O. & Gift, E. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Relative Biological Hazards of Radiations Expected in Homogeneous Reactors TBR and HPR

Description: An evaluation of the relative health hazards of radioisotopes produced in nuclear reactors is reported. The most important hazards were indicated to be I131, the Sr90 - Y90 chain, the Ce144 -Pr144 chain, Sr 89, the Ba140-La40 chain, Y91, the Zr95-Nb95 chain, Pr143, La140 , and Pa233. The most critical body organs affected by air-borne contamination are the thyroid gland, the bone marrow, the lungs, and the gastrointestinal tract. Where possible, continuous daily removal of gaseous and solid fis… more
Date: December 2, 1955
Creator: Arnold, E. D. & Gresky, A. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Run 300A-B Slurry Run of 300A Pump and Loop

Description: The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300… more
Date: July 2, 1959
Creator: Moyers, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrophotometric Determination of Microgram Quantities of Osmium With Diphenylcarbazide by G. Goldstein

Description: A method was developed for the spectrophotometric determination of 30 to 100 ug of osmium as OSO4 is extracted with CHCl3 and diphenylcarbazide is then added to the organic extract. A blue-violet reaction product is formed, the absorbancy of which is measured at 560 mu. A suitable reagent concentration is from 3 to 5 ml of 0.2% diphenylcarbazide in a volume of 25 ml and the preferred solvent for the reagent is ethanol. Beer's law is followed over a range of 8 to 130 ug of osmium with a coeffic… more
Date: June 2, 1959
Creator: Menis, Oscar
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status Report- Application of Electroless-Nickel Brazing to Tabular Fuel Elements for the N. S. Savannah

Description: The feasibility of using electroless nickel, a chemical deposit containing about 10 wt% phosphorous in nickel, as the brazing alloy for assembling tubular stainless steel fuel elements of the type specified in Core I of the N. S. Savannah was investigated. This material was nelected primarily because of the case of braze-metal preplacement by chemical deposition of the alloy on type 304 stainless steel ferrule spacers, prior to fuel-bundle assembly. Brazed joints produced by this method were ge… more
Date: June 2, 1959
Creator: Lamartine, J. T. & Thurber, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Cycling Test of 3 1/2-in. and 4-in. Freeze Flanges

Description: A total of 104 thermal cycles between 250°F and 1350°F were imposed on a 3 1/2-in. and a 4-in. freeze flange to determine their susceptibility to thermal fatigue. The flange clamping arrangement was modified and various gaskets were used during the cycling in an effort to reduce the gas leakage problem.
Date: February 2, 1961
Creator: Moyers, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Partner: UNT Libraries Government Documents Department
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