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NACA Research Memorandums
173
Atomic Energy Commission Reports
61
NACA Technical Reports
30
Hanford Works Reports
20
HW (Series)
16
Oak Ridge National Laboratory Reports
15
University of California Radiation Laboratory Reports
12
AEC research and development report
6
AECU (Series)
6
BNL (Series)
6
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Methods used in the NACA tank for the investigation of the longitudinal-stability characteristics of models of flying boats
Report presents the results of tests of longitudinal stability characteristics of models of several flying boats conducted in the NACA Tank No. 1. These investigations were made for the purpose of (1) determining suitable methods for evaluating the stability characteristics of models of flying boats, and (2) determining the design parameters which have an important effect on the porpoising. This report is mainly concerned with the construction of suitable models, the apparatus, and methods used in the tests. The effect of changes in some design parameters is discussed.
Date:
September 9, 1942
Creator:
Olson, Roland E. & Land, Norman S.
Object Type:
Report
System:
The UNT Digital Library
Recovery of U from Pyrolytic Carbon-Coated UC2 Spheroids
100% recovery of uranium from pyrolytic carbon-coated spheroids of uranium dicarbide has been accomplished by an aqueous electrolytic process at the small scale laboratory level. This result was obtained in a system which circulated 1 molar nitric acid through a thin bed of the spheres. The bed was supported between a glass frit and the anode, with which the bed was in contact. The anode was a spiral of platinum wire; the cathode was a grid of titanium wire. Current density was about 0.2 amp/cm2 based on geometric surface area calculated from the average particle size of 150 microns. Initial flow rate was about 1.3 ml/cm2/sec. Reaction temperature was 72-82°C; time was 15 hours. At 1/5 the above current density and at the same temperature recovery was smaller and was independent of concentration of nitric acid over the range 1-4 molar; also recovery in 1 molar ammonium nitrate was about the same as in 1 molar HNO3. About a 100-fold increase in recovery was obtained by going from a convection stirred cell at 90°C to the pumped type of cell at 54°C using ammonium nitrate as the electrolyte.
Date:
September 9, 1963
Creator:
Katz, H
Object Type:
Report
System:
The UNT Digital Library
The Blast Cleaning Process as an Aid to Visual Weld Inspection
Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.
Date:
March 9, 1960
Creator:
Hanson, G. R.
Object Type:
Report
System:
The UNT Digital Library
Calculation of Transport Cross-Sections of Uranium
In recent months, experiments investigating the total, non-elastic, transport, etc., cross-sections of U-238 have been performed. It is the purpose of this memo to examine these data and to obtain from them information which will be of use in refinements pile calculations. In cases, e.g. transport cross-sections, where experimental data do not suffice, the theory developed pertaining to the continuum model of the nucleus has been depended upon. One of the fundamental requirements of this model is that the spacings of the energy levels in the compound nucleus are small compared to their widths and that consequently many levels are excited by the incoming particles. As a result there are many more modes of decay and the continuum model is an average over these levels.
Date:
January 9, 1953
Creator:
Oleksa, S.
Object Type:
Report
System:
The UNT Digital Library
Recovery of Uranium by Ion Exchange or by Uranous Phosphate Precipitation from Sulfuric Acid Leach Solutions Produced from Australian Davidite Ore Concentrates
Uranium ore from Radium Hill, South Australia was leached with hot sulfuric acid solutions and the uranium recovered from solution by uranous phosphate precipitation or by use of anion exchange resins.
Date:
June 9, 1952
Creator:
George, D'Arcy R.
Object Type:
Report
System:
The UNT Digital Library
Line Broadening by Electrons : the Validity of Simple Theories
A comparison of the simple impact theories of line broadening by electrons with the detailed computations of Kivel, Bloom, and Margenau.
Date:
May 9, 1955
Creator:
Meyerott, Roland Edward & Margenau, Henry, 1901-1997.
Object Type:
Report
System:
The UNT Digital Library
Temperature Calculations For UOâ‚‚ Fit Tolerance Experiment
Prevailing dimensional tolerance for sintered UO₂ reactor fuel components to be enclosed in metal jackets are expensively small. For instance, the PWR fuel pellet, as of November, 1955, consisted of a centerless ground UO₂ cylinder 0.3560" (+0.0005", -0.000") in diameter and 0.3527" (±0.0008") long. This pellet was designed to fit in a Zircaloy tube 0.3585" (+0.0005", -0.0000") inside diameter. The use of UO₂ shapes as pressed, or extruded, and sintered with diameter variations controlled to a tolerance of ±0.003" to ±0.005" would represent a fabrication cost saving worth considering. It is reasonable to assume that the annulus between a sintered UO₂ shape and its container will vary as a function of time of irradiation. Shrinkage from the can walls occurs with relatively low density (i.e., 85% of theoretical) sintered irradiation (cf. MTR Test GEH-4-3C). Contrary to this effect, the thermal expansion coefficient of UO₂ is about twice that of Zircaloy. Of possibly greater significance is the inevitable fractuce of dense UO₂ due to thermal stress. Such cracking effectively relocates the annular heat transfer gap to the interior of the oxide where the higher temperatures enhance the heat transfer coefficient. Thus, possibly the worst condition, with respect to heat transfer, is …
Date:
May 9, 1956
Creator:
Roake, W. E.
Object Type:
Report
System:
The UNT Digital Library
Periodic Intercalibration of Temperature Sensing Elements. Section I. First Performance. Test Results DL-S-243 (T-641306)
The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Determination of temperature sensing element and instrumentation drifts could not be made due to a lack of comparative data. Five temperature intercalibrations were performed using the calibrating Tc resistance thermometers as a standard. The data obtained from the nuclear instrumentation was too erratic to form any conclusions.
Date:
November 9, 1959
Creator:
Lawrence, Roger J.
Object Type:
Report
System:
The UNT Digital Library
Periodic Intercalibration of Temperature Sensing Elements. Section I. Second Performance. Test Results DL-S-243 (T-641303)
The purpose of the test was to determine the direction and magnitude of any drift in the temperature sensing elements and the receiver-indicating units for the primary loop and pressurizer resistance thermometers. To obtain intercalibration data for various temperature sensing elements in the primary coolant system. To obtain data on the difference between the calculated signal generated by the BF-3 counters, considering the known rate of decay of the PO-BE source, and the measured values. Of the 62 core thermocouples observed 19 were either reading less than 400 F or were reading in excess of 20 F from the calibrating thermometer temperatures. In each case the thermocouple was considered defective. The remainder were within 2 per cent of the calibrating thermometers. The primary loop (Norwood Indicators) resistance thermometers all read with 0.2 percent of the calibrating thermometers. No conclusion could be made for the pressurizer temperature instruments or the boiler Tb resistance thermometers, except that the 1A boiler temperature varied 10 F to 20 F from the 1Band 1C boiler temperatures. A laboratory calibration of this instrument will be made. The data obtained from the source range nuclear instrumentation was too erratic to form any conclusion. No drift evaluation on …
Date:
November 9, 1959
Creator:
Lawrence, Roger J.
Object Type:
Report
System:
The UNT Digital Library
The Use of an Electronic High Vacuum Pump on Various Types of Mass Spectrometers
A commercially available electronic high vacuum pump has bee tested on various types of mass spectrometers used at the Oak Ridge Gaseous Diffusion Plant. Considerable savings in operating and maintenance costs can be realized from the use of this pump. the greatest savings result from the elimination of the cold trap required for the diffusion pump whether it is cooled by liquid nitrogen or by mechanical refrigeration. additional savings results from the fact that the pump currently is usually an adequate indication of the pressure in the spectrometer tube and that a continuously running mechanical fore pump is not required.
Date:
October 9, 1959
Creator:
High, R. D. & Schede, R. W.
Object Type:
Report
System:
The UNT Digital Library
Higher harmonics of Radial Vibrations in Short Hollow Cylinders of Barium Titanate
This paper discusses the forbidden and allowed harmonics of a hollow cylinder of barium titanate vibrating in the radial mode.
Date:
March 9, 1955
Creator:
Stephenson, C.V.
Object Type:
Report
System:
The UNT Digital Library
Control Rod Positions for Criticality. Section I. 5032-EFPN. Eigth Performance. Core I, Seed 1. Test Results DL-S-149, T-550130
The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at ambient temperatures. The critical rod bank position and bank worths for four different control rod bank rod configuration were determined after 5032 EFPH's of operation. The value were corrected to a reactor coolant temperature of 145 F and a pressure of 400 psig. The bank worths were corrected to 145 F so that the results of the performance could be compared with the results of previous performances.
Date:
December 9, 1959
Creator:
McTish, James M.
Object Type:
Report
System:
The UNT Digital Library
Hardness of Various Valve Seat and Bearing Materials for Possible Use in Thora Slurry Systems
The hardness of several materials that have been considered for use as valve scats and bearings in thorium oxide slurry systems were measured and are reported for comparison with thorium oxide.
Date:
December 9, 1960
Creator:
Moyers, J. C. & Randell, H. A.
Object Type:
Report
System:
The UNT Digital Library
Specifications for Fuel Assemblies for Core I of the Experimental Gas-Cooled Reactor
These specifications for the fuel assemblies for Core I of the Experimental Gas-Cooled Reactor (EGCR) have been developed for use in procuring the first core loading. A fuel assembly for EGCR consists of a cluster of seven cylindrical fuel elements spaced and supported within a graphite sleeve. Each fuel element consists of a stainless steel tube containing a column of hollow UO2 pellets and having a spacer brazed at the midsection to control the spacing between fuel elements in a cluster. A master specification for the fuel assembly, a supplementary specification for each of the components, and a specification on record keeping during manufacture are included.
Date:
December 9, 1960
Creator:
Coobs, J. H.; Wick, E. A. & Evans, R. M.
Object Type:
Report
System:
The UNT Digital Library
The HRT Refrigerating System
The HRT refrigeration system was designed to use Freon-11 (CCI3F) as the refrigerant material in the secondary loop. A Van de Graaff irradiation of this material indicated that serious corrosion problems were probable if Freon were used in the proposed metal system. A survey was made of candidate refrigerants, and Amsco 125-82 and triethyl phosphate were selected for irradiation and physical-property determinations.
Date:
January 9, 1957
Creator:
Silverman, M. D.
Object Type:
Report
System:
The UNT Digital Library
Milbank Quadrangle Basic Data
Tables presenting well water, stream sediment, and field data for samples collected from a geochemical survey of the Milbank Quadrangle in Minnesota, North Dakota, and South Dakota.
Date:
June 9, 1981
Creator:
National Uranium Resource Evaluation Program
Object Type:
Dataset
System:
The UNT Digital Library
On the Translation of Boolean Expressions
A program translates an algebraic language like Algol into the machine language of an electronic computer must perform the following functions.
Date:
February 9, 1961
Creator:
Grau, A. A. & Bottenbruch, H. H.
Object Type:
Report
System:
The UNT Digital Library
Generalized Heat Conduction Code for the IBM-7090 Computer
The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be punched on cards.
Date:
February 9, 1961
Creator:
Fowler, T. B.
Object Type:
Report
System:
The UNT Digital Library
[Average Record Data Listings for Nulato Quadrangle]
Average record data listings taken during aerial gamma-ray and magnetic surveys of the Nulato quadrangle in Alaska.
Date:
May 9, 1980
Creator:
Aero Service (Firm)
Object Type:
Dataset
System:
The UNT Digital Library