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NACA Research Memorandums
141
Atomic Energy Commission Reports
53
Hanford Works Reports
22
Oak Ridge National Laboratory Reports
22
HW (Series)
17
NACA Technical Reports
17
University of California Radiation Laboratory Reports
10
ORNL (Series)
8
GJBX
6
United States Department of Energy Grand Junction Office Reports
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Principles and Techniques of Ultrasonic Inspection
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.
Object Type:
Report
System:
The UNT Digital Library
Terminal Report to U.S. Atomic Energy Commission [for] December 20, 1954 to July 9, 1955
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}}}
Object Type:
Report
System:
The UNT Digital Library
HRT Corrosion Samples -- Additional Data on Specimens Removed Prior to Run No. 20.
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, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. Also included in the report is a summary of the HRT operating schedule during exposure of the specimen and of the status of examinations for those specimens removed from the reactor prior to run 20.
Date:
February 2, 1961
Creator:
Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Object Type:
Report
System:
The UNT Digital Library
Fuel-Cycle Analysis and Proposed Fuel and Burnable Poison Distribution and Loading for the HFIR and HFCE-2
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 indicated that the largest ratio of maximum meat thickness to minimum meat thickness occurred in the inner fuel annulus and was equal to 3.6, while the maximum fuel concentration occurred in the outer fuel annulus and was equivalent to about 0.7 g of U-235/cm^3 of meat. The total U-235 loading for this core was 8.01 kg, which results in a core lifetime of about 14 days.
Date:
February 2, 1961
Creator:
Cheverton, R. D.
Object Type:
Report
System:
The UNT Digital Library
Thermal Cycling Test of 3 1/2-in. and 4-in. Freeze Flanges
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.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Section C Progress Report for December 1960 and January 1961
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 nitrate from the solvent for recycle by contact with a lime slurry.
Date:
June 2, 1961
Creator:
Brown, K. B.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Experiment Off-gas System for the EGCR-LITR Capsule Experiment
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 iodine vapor adsorber to the off-gas system, which presently includes an absolute filter, reduces the atmospheric dose to the thyroid from 510 mr to 1.4mr. The total body dose is also reduced from 2.2 to 1.3 mr. The total body dose can be further reduced to 0.7 mr if a large krypton-xenon adsorber is included. Basd upon these calculated atmospheric radiation doses it is concluded that the addition of an activated charcoal iodine vapor adsorber will reduce the atmospheric hazard to an acceptable level.
Date:
September 2, 1960
Creator:
Adams, R. E. & Browning, W. E.
Object Type:
Report
System:
The UNT Digital Library
Run 300A-B Slurry Run of 300A Pump and Loop
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 gpm.
Date:
July 2, 1959
Creator:
Moyers, J. C.
Object Type:
Report
System:
The UNT Digital Library
Spectrophotometric Determination of Microgram Quantities of Osmium With Diphenylcarbazide by G. Goldstein
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 coefficient of variation of about 4%. After a 2-hour color-development period the molar absorbancy in less than 2 hours were unsuccessful. A study was made of the effects of foreign elements and only Ru(VIII) was found to interfere.
Date:
June 2, 1959
Creator:
Menis, Oscar
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Cost for Aqueous Homogeneous Reactors
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 doubling time at an estimated fuel cycle cost of 1.5 mills/kwh at a 2000 Mw electricity station with an on-site processing plant.
Date:
June 2, 1959
Creator:
Culler, F. L.
Object Type:
Report
System:
The UNT Digital Library
Status Report- Application of Electroless-Nickel Brazing to Tabular Fuel Elements for the N. S. Savannah
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 generally characterized by a relatively ductile solid-solution region at the thinnest portions of the fillet. This ductile zone should minimize the possibility of complete propagation of hairline cracks, which form in the brittle, eutectic regions of fillet.
Date:
June 2, 1959
Creator:
Lamartine, J. T. & Thurber, W. C.
Object Type:
Report
System:
The UNT Digital Library
ORIC R-F Model III Progress Report
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 measurements of the model characteristics.
Date:
June 2, 1959
Creator:
Worsham, R. E. & Mosko, S. W.
Object Type:
Report
System:
The UNT Digital Library
Suggestion for High Pressure Letdown Device
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
Object Type:
Report
System:
The UNT Digital Library
Pressure Rise in HRT Shield Due to Reactor and Replacement heat Exchanger Rupture
.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.
Object Type:
Report
System:
The UNT Digital Library
Uranium-235 Abundance by Gamma Spectrometry
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 abundance is between 0.7% and 100%. Findings in the self-absorption of 0.18 Mev radiation in uranium oxide are presented.
Date:
January 2, 1957
Creator:
Reynolds, S. A. & Eldridge, J. S.
Object Type:
Report
System:
The UNT Digital Library
Extraction of the elements with Tris-2-Ethylhexyl- and Trihexylphosphine oxides from Acidic Solutions
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 >TEHPO. (b) No ion is extracted by THPO or TEHPO that is not extracted by TOPO under certain conditions. (c) The effect of hydrogen ion concentration is greater in TEHPO systems than it is in the other two, which indicated greater selectivity of extraction with TEHPO.
Date:
January 2, 1957
Creator:
Ross, W. J. & White, J. C.
Object Type:
Report
System:
The UNT Digital Library
[Digitized Accelerogram and Earthquake Tables]
Computer printout listings of three data tables (Digitized Accelerogram, Recording Station, and Earthquake) organized alphabetically by country.
Date:
February 2, 1981
Creator:
Crouse, C. B.; Hileman, J. A.; Turner, B. E. & Martin, G. R.
Object Type:
Dataset
System:
The UNT Digital Library
The Half-Life and Gamma Ray Abundance of Cs-137
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 method.
Date:
June 2, 1962
Creator:
Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
Object Type:
Report
System:
The UNT Digital Library
High Performance UO2 Program Third Quarterly Progress Report: October-December 1961
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.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores
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.
Object Type:
Report
System:
The UNT Digital Library
Metallurgy Division Semiannual Progress Report for Period Ending April 10, 1956
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, fundamental physico-metallurgical research.
Date:
November 2, 1956
Creator:
Frye, J. H., Jr.; Manly, W. D. & Cunningham, J. E.
Object Type:
Report
System:
The UNT Digital Library
Relative Biological Hazards of Radiations Expected in Homogeneous Reactors TBR and HPR
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 fission products from the reactor environment can be shown to permit very significant reductions in the total hazards. Homogeneous reactors, such as the Thermal Breeder Reactor and the Homogeneous Plutonium Producer Reactor, specifically studied in this report, are designed with daily removal cycles and may be considered potentially safer than heterogeneous reactors.
Date:
December 2, 1955
Creator:
Arnold, E. D. & Gresky, A. T.
Object Type:
Report
System:
The UNT Digital Library
Mathematics Panel Semiannual Progress Report
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-shift operations. / Installations of the magnetic-tape memory units is complete, and the units are expected to go into operation in the near future. Work is continuing on the new input-output system.
Date:
March 2, 1955
Creator:
Householder, A. S. & Sangren, W. C.
Object Type:
Report
System:
The UNT Digital Library
Decontamination of the KER Rupture Experiment Loop Test Series B - Tests No. 1 and 2
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.
Object Type:
Report
System:
The UNT Digital Library