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GAP: The IBM 704 Grid Analysis Program

Description: GAP is an IBM 704 program for analyzing simply-supported rectangular beam grillages in which the beams intersect at right angles. The grillage need not be symmetrical and may have both uniformly distributed and concentrated loads. Also, the individual beams may have arbitrary cross sections. Strain energy methods are used to determine the bending, shearing, and torsional effects in a given grid structure. Deflections and moments can be found directly by the program, and series coefficients are … more
Date: May 2, 1960
Creator: Witt, F. J.
Partner: UNT Libraries Government Documents Department
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Power Reactor Fuel Reprocessing: Mechanical Phase

Description: The major events of the Mechanical Phase of the Power Reactor Fuel Reprocessing program during August 1959 are summarized here.
Date: September 2, 1959
Creator: Klima, B. B.
Partner: UNT Libraries Government Documents Department
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Bibliography on the Toxicology of Beryllium

Description: The references in this bibliography were taken from: Index Medicus, January 1942-June1954; Current List of Medical Literature, July 1954-November 1956; Nuclear Science Abstracts, July 1948-December 1956. References ae arranges in chronological order beginning with the most recent,
Date: January 2, 1957
Creator: Riese, Gretchen R.
Partner: UNT Libraries Government Documents Department
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Supplement No. 1. Projections of Costs, 1959-1975 for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement 1 shows a year by year projection of costs for the period 1959-1975.
Date: July 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. ( A.C.)
Date: March 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Exploration of Radiometric Methods

Description: The compilation of possible analyses in aqueous solution is nearly complete. A chart has been constructed showing the elements which may be determined radiometrically. The radiometric general scheme of analysis has been roughly blocked out. The next-planned phase is to select specific reagents and determine the details of such analysis.
Date: April 2, 1959
Creator: Driscoll, William J. & Scott, Benjamin F.
Partner: UNT Libraries Government Documents Department
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Low-Energy [pi] Mesons in the Cosmic Radiation

Description: The intensity of 𝜋 mesons in the atmosphere is investigated in the energy region 𝐸kin≲50 Mev at sea level and at mountain altitudes. Positive 𝜋 mesons coming to rest in an absorber-scintillator are identified by the characteristic 𝜋−𝜇 decay. They are detected electronically and recorded photographically. The value 1.45±0.09 is adopted for the negative-to-positive ratio at small energies. The omnidirectional intensities 𝐽𝜋+ of slow positive 𝜋 mesons at sea level (91m), Echo Lake, Colorado (326… more
Date: February 2, 1959
Creator: Fotino, Mircea
Partner: UNT Libraries Government Documents Department
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Radiation Shielding for the Cambridge Electron Accelerator

Description: The radiation shielding requirements for the 6.0-Bev electron synchrotron are analyzed and the plans for fulfilling these requirements are presented. The special problems include 1) overhead shielding for the target areas, 2) overhead shielding for the tunnel containing the magnet ring, 3) local and overhead shielding for X-rays from the linac injector, 4) shielding for the adjacent public street, 5) shielding between the target area and the experimental building, 6) local shielding for experim… more
Date: May 2, 1957
Creator: Livingston, M. Stanley (Milton Stanley)
Partner: UNT Libraries Government Documents Department
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Sodium Boiling Calculations

Description: The equations are derived for making rough calculations of the pressure drop required to produce a given mass flow through a subassembly for a given heat generation for cases where the vapor volume fraction is 0.9 or less. The ratio of vapor velocity to liquid velocity is left as a parameter that is varied form unreasonably low to unreasonably high values.
Date: July 2, 1957
Creator: Nicholson, R. B.
Partner: UNT Libraries Government Documents Department
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Principles and Techniques of Ultrasonic Inspection

Description: Ultrasonic inspection for subsurface flaws is widely used in American industry. This report reviews the general principles and specific techniques of ultrasonic testing. The information is based on a review of the technical literature plus the experience of the Quality Assurance Department at Sandia Corporation in applying this nondestructive testing technique to quality evaluation programs.
Date: July 2, 1953
Creator: Psillas, H. C. & Ballard, D. W.
Partner: UNT Libraries Government Documents Department
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Terminal Report to U.S. Atomic Energy Commission [for] December 20, 1954 to July 9, 1955

Description: A survey of reactors believed to be suited for most effect competition with conventionally fueled power plants in the continental USA. Basic design data are summarized for a light-water-moderated boiling reactor and aqueous homogeneous reactors.
Date: December 2, 1955
Creator: {{{name}}}
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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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.
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.
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.
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
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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Suggestion for High Pressure Letdown Device

Description: A letdown valve design is described which reduces erosion of the sealing surfaces. It also provides for water flushing of the sealing surface before closing.
Date: April 2, 1957
Creator: Lyon, Richard Norton
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.
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.
Partner: UNT Libraries Government Documents Department
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