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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.
open access

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.
open access

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.
open access

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
open access

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.
open access

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.
open access

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.
open access

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.
open access

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.
open access

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.
open access

The Half-Life and Gamma Ray Abundance of Cs-137

Description: The nuclide Cs-137 is a fission product commonly used for measurement of uranium burnup in irradiated uranium fuel by the fission product to uranium ratio method. In the application of this method, the largest single error introduced in the measurement of burnup is the uncertainty in the half-life of Cs-137. Because of the uncertainty in this value and its importance in nuclear fuel burnup analysis, a reinvestigation was undertaken to obtain a more accurate value using the mass spectrometric me… more
Date: June 2, 1962
Creator: Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
open access

High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

Description: The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date: January 2, 1962
Creator: Weidenbaum, B.
open access

Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores

Description: In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.
Date: March 2, 1953
Creator: Abrams, Charles S.; Moulton, Harry D. & Viklund, Hans I.
open access

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.
open access

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.
open access

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.
open access

Decontamination of the KER Rupture Experiment Loop Test Series B - Tests No. 1 and 2

Description: The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.
Date: November 2, 1959
Creator: Weed, R. D.
open access

A Simple Telephone Telemeter

Description: When following the performance of automatic and semi-automatic equipment that is left unattended for extended periods of time, it is often desirable to be able to check this equipment by remote means. A convenient vehicle for such a check is the telephone since nearly all locations have or can have a telephone extension installed. The check of the equipment may be made as simple or extensive as desired, with the outcome of the check represented by a relay condition, for example. The condition o… more
Date: November 2, 1959
Creator: Ratcliffe, C. A.
open access

Specific Gravity of Aluminum Nitrate Solutions

Description: Aluminum nitrate solutions are used as salting agents in the redox process and frequently in organic-aqueous extractions in the laboratory. Determination of specific gravity is a convenient means of estimating the concentration of such solutions. However, where an aluminum nitrate solution has been prepared by dissolving aluminum hydrate in nitric acid, the ratio of nitrate to aluminum may intentionally be other than stoichiometric, the solutions being described as acid, neutral, or acid defic… more
Date: September 2, 1959
Creator: Case, A. H. & Pollock, C. W.
open access

Rubber Ring Dosimeter Calibrations with the Plutonium Radiation Spectrum

Description: This work was initiated as an evaluation of the application pf rubber finger ring dosimeters to the control of extremity radiation exposure. The use of film dosimeters is a well known general practice throughout the radiation protection profession, however, film radiation exposure measurements associated with plutonium metal handling present a unique problem. The practical measurement of extremity dose depends upon the accuracy and reproducibility of results under the most severe conditions usi… more
Date: September 2, 1959
Creator: Swanberg, F., Jr & Andersen, B. V.
open access

PRTR Single Tube Prototype Mockup (STPM) Operational Characteristics

Description: The Single Tube Prototype Mockup (STPM) was constructed to be used as a tool to evaluate the mechanical problems involved in operating and maintaining many components of the Plutonium Recycle Test Reactor (PRTR). This report has been written to acquaint interested HAPO components with the capability of the STPM and for use as an aid in scheduling tests and/or to properly evaluate testing results obtained from the mockup.
Date: July 2, 1959
Creator: Scott, P. A.
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