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Progress letter No. 11 for January 1, 1960 through January 31, 1960
A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date:
February 15, 1960
Creator:
Baron, Edeard H.
Object Type:
Report
System:
The UNT Digital Library
Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961
During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date:
February 16, 1960
Creator:
Russell, Elizabeth Shull, 1913-2001
Object Type:
Report
System:
The UNT Digital Library
Progress Report for Period Covering January 15, 1960 - February 15, 1960
Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date:
February 15, 1960
Creator:
Petrow, Henry G.
Object Type:
Report
System:
The UNT Digital Library
Results of Experiments Made With U.S.B.M. Electrocerium
Data obtained in test of Bureau of Mines electrocerium are presented. The cerium was subjected to spectrochemical analysis, x-ray diffraction analysis, thermal analysis, metallographic tests, and high-pressure experiments.
Date:
February 26, 1959
Creator:
Miner, William N.
Object Type:
Report
System:
The UNT Digital Library
Particle Extraction III
A device to extend the operation of a beam extraction system is described for low energies where the radiation loss per turn is ineffective. The device consists of a noisy radiofrequency field which excites the radial betatron oscillation
Date:
February 16, 1959
Creator:
Robinson, Kenneth W.
Object Type:
Report
System:
The UNT Digital Library
Some Preliminary Considerations Concerning the Expected Ovel-All Expansion of Barium Titanate Ceramic
A preliminary mathematical study is made of the maximum expected expansion of barium titanate ceramic. It is noted that there is insufficient physical evidence for a complete answer and some possible mathematical models are discussed and compared.
Date:
February 7, 1955
Creator:
Kleinecke, D. C.
Object Type:
Report
System:
The UNT Digital Library
Echelle Spectroscopy. Seventeenth Quarterly Progress Report
This is the seventeenth quarterly report on our echelle project, as numbered above. Our work this quarter has to some extent been directed towards the Spectroscopy Symposium held at Argonne National Laboratory on February 15, 16, and 17. This report consists principally of brief abstracts of the two papers given at this meeting. Progress since the last quarterly report included completion of the echelle comparator calibration, and the successful production and photographing of the desired spectra of praseodymium and erbium in strong magnetic fields. Considerable interest was aroused by these papers, not only because rare earth spectra are being analyzed, but because of the general applicability of our experimental techniques in producing the spectra.
Date:
February 15, 1956
Creator:
Harrison, George Russell, 1898-1979
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
Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow
A relationship is derived the mean square fluctuating current of a hot wire anemometer and the sic turbulent Reynolds stresses in the stream-coordinate system without employing the usual low turbulent intensity approximation. The relatively simple result is a consequence of assuming proportionality between the wire current reading and the perpendicular velocity component instead of the non-linear dependence required by King's law. The assumption is valid for instruments equipped with the proper linearizing circuitry. The stream-coordinate Reynolds' stresses are then related to the cylindrical polar Reynolds stresses.
Date:
February 21, 1961
Creator:
Wichner, R. P. & Peebles, F. N.
Object Type:
Report
System:
The UNT Digital Library
HFIR Beryllium Reflector Preliminary Design Report
This report considers the HFIR reflector design criteria and presents a summary of the reflector design. The reflector type chosen as complying best with the established criteria consists of a 3 in. thick removable beryllium annulus utilizing four concentric cylinders with cooling water flowing through the annuli between cylinders, and an outer 9 in. thick permanent beryllium annulus with axial circular coolant holes. Reflector support structures and experimental facilities are described and probable beryllium replacement costs are indicated.
Date:
February 21, 1961
Creator:
Hilvety, Neil
Object Type:
Report
System:
The UNT Digital Library
Interim Report - Status of Small Pipe and Tube Disconnects for MSRE Auxiliary Lines
To date, three types of metal-to-metal seal disconnects have been subjected to thermal cycling and make-break tests. In addition, a commercial disconnect has been procured for testing.
Date:
February 21, 1961
Creator:
Holz, P. P.
Object Type:
Report
System:
The UNT Digital Library
Apparent Observations Ionic Sound Waves in an Arc Plasma
Oscillations have been observed in a magnetically supported cylindrical rod of plasma. This rod of plasma can be the discharge occurring in the defining aperture of a Mode II, pressure gradient arc. Similar oscillations can also occur in the column of a Mode I arc. These oscillations appear to be the mechanism that drives the Mode II blowup phenomena.
Date:
February 13, 1961
Creator:
Alexeff, I. & Neidigh, R. V.
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
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
Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves
Equilibrium krypton and xenon adsorption isotherms were obtained for four varieties of charcoal and for Linde Molecular Sieves Types 4A and 5A, generally at 0, 25, and 60°c. Such data are of interest in connection with design and evaluation of adsorbers for radioactive noble gas fission products. The isotherms were fitted, by linear regression analysis, to straight-line forms of the Freundlich and Langmuir equations. The Freundlich linear equation gave the better fit and the parameters of this equation are presented for each of the isotherms. Also presented are the constants for an equation representing the temperature dependence of arbitrary adsorption coefficients, the coefficients having been calculated from the Freundlich isotherm parameters. Some aspects of the applicability and accuracy of these results are discussed.
Date:
February 14, 1961
Creator:
Ackley, R. D. & Browning, W. E., Jr.
Object Type:
Report
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
Processing of Beryllium Oxide Fuels
Preliminary results from experiments on the dissolution of beryllium metal and sintered UO2-BeO fuel pellets are reported. In all cases the pellets were fired in hydrogen at 1650-1800°C. Uranium, from UO2-BeO pellets containing more than 60% UO2, is readily leached with boiling 6-13 M HNO3 in about 6 hr. The BeO in these pellets dissolves only slowly in nitric acid; however, in 8 M HNO3-0.2M NaF, it dissolves at about the same rate as the UO2. Sintered pellets containing less than 10% UO2 do not dissolve rapidly in common aqueous reagents. The highest rates are obtained in boiling acidic fluoride solutions; e.g., sintered BeO and BeO-8% UO2 are dissolved initially at a rate of about 1.7 mg min-1cm-2 (13 mils/hr) in boiling 5.8 M NH4HF2.
Date:
February 13, 1961
Creator:
Warren, K. S. & Perris, L. M.
Object Type:
Report
System:
The UNT Digital Library
A Useful Solution for Short Cylindrical Shells and Other Applications
The general solution to the basic differential equation d^4w/dy^4 +4w= -4f(y) is transformed from the primary form treated in most texts to an alternate form in which each integration constant corresponds to one edge condition at y=0. The relationships between the integration constants of the two forms are derived and the values for the transformed functions are tabulated. The particular solution is derived in general and given in unique form for various functional forms of f(y). Matrix notation is used throughout the derivations; however, a knowledge of matrix theory is not need for application of the results.
Date:
February 14, 1961
Creator:
Moore, S. E.
Object Type:
Report
System:
The UNT Digital Library
Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.
The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release. Two of the most important variables not investigated in the present report are the influence of metal cladding and the difference in internal nuclear heating as opposed to external radiant heating. In addition a significant uncertainty exists in the understanding of diffusion through large masses such as might result from a scaled-up melt down in a reactor.
Date:
February 8, 1961
Creator:
Parker, G. W.; Creek, G. E. & Martin, W. J.
Object Type:
Report
System:
The UNT Digital Library
A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems
The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall temperature increases the amount of mass transfer, at least above 1300 deg F. The effect of the total temperature difference across the system on the amount of mass transfer was determined.
Date:
February 11, 1957
Creator:
DeVan, J. H. & West, J. B.
Object Type:
Report
System:
The UNT Digital Library
Capillary Flowmeter
The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method which requires a flowmeter capable of measuring flows of .5 cc or less of water per hour. The experiment flowmeter constructed performed almost exactly as the design calculations predicted.
Date:
February 20, 1957
Creator:
Hise, E. C.
Object Type:
Report
System:
The UNT Digital Library
Time Behavior of Fuel Concentrations in Single-Region Reactors Containing U-233, U235, Th-232 and Fission Product Poisons
Analytical expressions were obtained for the time behavior of fuel concentrations and fuel-feed rates in single-region, spherical, UO3-ThO2-D2O reactors.
Date:
February 26, 1957
Creator:
Gilbert, Nathan & Kasten, Paul R.
Object Type:
Report
System:
The UNT Digital Library
Preparation of Thorium Oxide from ORNL Thorex Thorium Nitrate
Thorium nitrate, recovered from irradiated thorium metal processed in the ORNL Thorex Pilot Plant, was converted to thorium oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)
Date:
February 13, 1957
Creator:
McDuffee, W. T. & Yarbro, O. O.
Object Type:
Report
System:
The UNT Digital Library