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Progress Report for Period Covering December 17, 1969 - January 15, 1960
As reported in the previous Progress Report (December 16, 1959) a stock solution of Th 230 was prepared from pitchblende. Pulse height analysis of this solution indicated the presence of only Th 230 (93%), Th 227 (5%), Th 232 (1%), and Th 228 (1%). This solution was used to make up synthetic thorium solution of various concentration. These synthetic solutions were analyzed to establish a chemical yield for the procedure. Neither the precision nor the chemical yield of the procedure were considered to be satisfactory. In the next report period, we hope to complete the testing of the thorium procedure, both with regard to chemical yield and precision, as well as to determine decontamination factor from radium, uranium, and polonium. To do this, pure solutions of polonium, radium, and uranium will be prepared. The polonium and radium will be processed from pitchblende while the uranium will be made by purifying reagent grade uranyl nitrate.
Date:
January 15, 1960
Creator:
Petrow, Henry G.
Object Type:
Report
System:
The UNT Digital Library
Progress Report on the Surface Chemistry of Thoria : February 1, 1959 to January 31, 1960
The following progress report briefly covers research completed or in progress on (1) Catalytic combination of hydrogen and oxygen in thoria slurries, and (2) Adsorption of molybdenum trioxide and sodium sulfate on thoria as determined by infrared spectroscopy.
Date:
1960
Creator:
Wadsworth, Milton E. & Bradford, Harold R.
Object Type:
Report
System:
The UNT Digital Library
Strontium Sorption Studies Using Naturally Occurring Ion Exchange Materials
Four naturally occurring materials, namely, vermiculite, variscite, Tennessee rock phosphate, and Florida pebble phosphate, were studied to determine the feasibility of their use in columns for the sorption of strontium from high pH, intermediate-level wastes produced at ORNL. Excepting vermiculite, all materials were found to be effective in strontium removal.
Date:
December 5, 1960
Creator:
Thomas, K. T.; Jacobs, D. G.; Tamura, T. & Struxness, E. G.
Object Type:
Report
System:
The UNT Digital Library
Statue of Pilot Plant Section Equipment Development Program
A development program is being carried out in the pilot plant to improve the equipment involved in monitoring, metering and pumping process streams. The equipment under development includes an alpha monitor, a gamma monitor, a waste water monitor, a liquid flow rate meter, a canned rotor pump, a diaphragm pump, air lifts and a pressure tank pump. This report presents the present status of the testing program.
Date:
October 14, 1960
Creator:
Mackey, T. S.
Object Type:
Report
System:
The UNT Digital Library
Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab
A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy distribution of the reflected and transmitted energy current. All the answers except for energy deposition and reflected and transmitted energy current are optional.
Date:
October 26, 1960
Creator:
Aulender, S. & Trubey, D. K.
Object Type:
Report
System:
The UNT Digital Library
Determination of Free Acid in Highly Radioactive Solutions by Remotely Controlled Conductometric Titration
A conductometric titration method described by Goldstein was adapted for use in a remote analytical facility. The results obtained by mean of experiments made prior to this adaptation indicated that methanol is the most satisfactory medium in which to determine excess sulfuric acid in uranyl sulfate solutions that stimulate Homogeneous Reactor type fuel. When methanol is used, the complexation of hydrolyzable ions with sodium fluoride, as described by Pepkowitz, Sabol, and Dustin, is not required.
Date:
October 13, 1960
Creator:
Corcoran*, R. E.; Zittel, H. E.; Dinsmore, S. R. & Koskela, U.
Object Type:
Report
System:
The UNT Digital Library
Radioactive Drug Research, Final Summary Report, July 1949 to October 1959
Applications of radioisotopes in the preparation of labeled drugs are reviewed. Among the applications described are the preparation of carbon-14- labeled cardiac glycosides, and the biosyinthesis of carbon-14-labeled digitoxin, morphine, colchicine, atropine, podophyllotoxin, and nicotine. The fate and metabolism of many of these drugs were traced. Radiochemical procedures were developed for the synthesis of pure compounds of pharmacological interest labeled with carbon-14, sulfur-35, and tritium. Investigations were made on the phenomena of drug penetration into the central nervous system. Publications during the period are listed. (C.H.)
Date:
January 15, 1960
Creator:
Geiling, E. M. K. (Eugene Maximilian Karl), 1891-1971 & Roth, Lloyd J. (Lloyd Joseph), 1911-
Object Type:
Report
System:
The UNT Digital Library
Operation Pre-Gnome: Seismic Data from Natural Phenomena and High-Explosive Tests Near Carlsbad, New Mexico
Formulas derived from earlier work satisfactorily predicted low frequency ground effects resulting from the Pre-Gnome explosions, but they not predict high accelerations associated with high frequency ground waves. The Pre-Gnome experiments taken since indicated that accelerations and ground amplitudes are proportional to the explosive charge, but physical conditions limit extrapolation on this basis to relatively low yields. Predicted accelerations resulting from the 10 kt Gnome explosion in potash mines eight or more miles away will be somewhat less than from routine blasts in the mines. The compressional wave speed in the salt stratum of the area is about 14,000 feet per second.
Date:
January 12, 1960
Creator:
Carder, Dean S.; Murphy, L. M.; Cloud, W. K. & Pearce, T. H.
Object Type:
Report
System:
The UNT Digital Library
A Transport Calculation of the HFIR Beam Hole Currents
An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.
Date:
December 5, 1960
Creator:
Claiborne, H. C. & Rakavy, G.
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
A Statistical Model of Nuclear Level Spacings
A generalization of Wigner's simple model for the distribution of nuclear level spacings is studied. It is based on a stochastic process which reproduces the correct joing probability distribution of N enerfy levels for small spacings. The case N=3, which includes the effect of the correlation between adjacent spacings, is discussed in detail. The resulting distribution and the correlation coefficient are compared with experimental data. No definite conclusion can be drawn except to say that the effect of the correlations on the spacing distributions on the spacing distribution is very small.
Date:
December 4, 1960
Creator:
Dresner, L. & Inönü, E.
Object Type:
Report
System:
The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium
Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date:
December 27, 1960
Creator:
Gaitanis, M. J.
Object Type:
Report
System:
The UNT Digital Library
High Energy Storage Ceramic Capacitor. Quarterly Report No. 5 [for] January 1, 1958 -- March 31, 1958
The chief purpose of this contract is the development of ceramic materials with high dielectric constant and high dielectric strength values, and suitable for use of dielectrics in capacitors capable of storing large amounts of energy in small volumes. Work performed during the fifth quarter included (1) Material development and sample preparation; (2) Sample testing; (3) Optical studies of titanates; (4) Fabrication of large ceramics; and (5) Capacitor design.
Date:
October 31, 1960
Creator:
Lupfer, D. A.
Object Type:
Report
System:
The UNT Digital Library
Applications for Lanthanon Oxides and Other Compounds in the Ceramic Industry
Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.
Date:
January 28, 1960
Creator:
Ploetz, G. L.
Object Type:
Report
System:
The UNT Digital Library
An Aerodynamic Raindrop Sorter. Technical Progress Report No. 1.
A pilot model of an Aerodynamic Raindrop Sorter was constructed along the lines suggested by mathematical analysis. The function of the analyzer is to sort natural rain according to drop size and to collect the sorted drops for further analysis. The pilot model, a small wind tunnel inclined at 45 deg to the horizontal, demonstrated the feasibility of aerodynamic rain drop sorting over a wide range of drop sizes. (auth)
Date:
January 1960
Creator:
Dingle, A. Nelson & Brock, Fred V.
Object Type:
Report
System:
The UNT Digital Library
Research and Investigation Leading to Methods of Generating and Detecting Radiation in the 100 to 1000 Micron Wavelength Range of the Spectrum. Quarterly Progress Report No. 15 for 1 September to 1 December 1959
Purpose of this research is twofold:: (1) to uncover new principles or techniques from which a CW source of electromagnetic radiation for the low millimeter and submillimeter wavelength range can be developed; and (2) to develop suitable detectors, components, and measuring techniques for evaluating and using the radiation as a diagnostic tool for plasma physics
Date:
January 1, 1960
Creator:
Coleman, P. D.; Baird, J. R.; Enderby, C.; Hakki, B;; Kenyon, R. J.; Stafford, J. et al.
Object Type:
Report
System:
The UNT Digital Library
568 Report
Final report for a grant contract documenting information about the scope of the project and results.
Date:
1960
Creator:
Pollard, Ernest C. (Ernest Charles), 1906-1997
Object Type:
Report
System:
The UNT Digital Library
Compilation of Requests for Nuclear Cross Section Measurements
This report is a working document of the UB AEC Nuclear Cross Sections Advisory Group and is issued about twice a year for the purpose of stimulating important cross section measurements. The requests listed in this report have originated from various Atomic Energy Commission contractors, the Advisory Committee on Reactor Physics, and the Nuclear Cross Sections Advisory Group. The distribution is limited to members of the US Nuclear Cross Sections Advisory Group (NCSAG), the US Advisory Committee on Reactor Physics (ACRP), the Tripartite Nuclear Cross Sections Committee (TNCC), the European-American Nuclear Data Committee (EANDC), to US AEC off-site contractors, and to the requestors and measurers of the cross sections listed in this report. The contents of this document are not to be republished in part or in full without special permission of the chairman of the NCSAG, The unpublished data which appear in this report must not be quoted in publications without permission of the experimenter.
Date:
November 4, 1960
Creator:
Harvey, John A.
Object Type:
Report
System:
The UNT Digital Library
Removal of Radioiodine from Air-Steam Mixtures
A short-term study was made to investigate the removal of radioiodine vapor from air-steam mixtures as could occur immediately following a nuclear incident in a pressurized water reactor. Activated charcoal traps, designed to simulate a small section of a commercial charcoal canister, were tested at gas velocities of 23.9 to 74.9 ft/min over the temperature range of 75 to 118°C. The iodine removal efficiency was found to range from 99.80 to 99.4% with an average of 99.9%. One test performed at a temperature of 105°C and with gas velocity of 290 ft/min indicated that the iodine removal efficiency was reduced to 99.54%. Activated charcoal exhibits a high efficiency for iodine vapor removal under these test conditions and appears suitable for application in the decontamination of air-steam mixtures.
Date:
November 14, 1960
Creator:
Adams, R. E. & Browning, W. E. Jr.
Object Type:
Report
System:
The UNT Digital Library
Plasma Accumulation in a Device Fed by Energetic Ion Trapping
Simon (1960) has given a general steady state theory of plasma accumulation (without energy losses) in an OGRA device. Such a device is fed by injection of energetic molecular ions which dissociate to produce trapped protons. Initial trapping is achieved by dissociation in the background gas. Such a device is usually characterized by a critical input current of critical plasma density (a function of input current) above which plasma density builds up to a value limited by Coulomb-scattering losses. For a regime of operation of current interest at Oak Ridge National Laboratory (600-kev hydrogen molecular ion injection and dissociation, highly efficient ion-pumping action of the trapped plasma), extremely simple approximate formulas have been derived which describe with a fair degree of accuracy the critical current of density for plasma build-up.
Date:
November 10, 1960
Creator:
Mackin, R. J., Jr.
Object Type:
Report
System:
The UNT Digital Library
Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer
Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date:
November 21, 1960
Creator:
Fowler, T. B. & Tobias, Melvin
Object Type:
Report
System:
The UNT Digital Library
Experimental Determination of an Adequate Fission Chamber Location in the ORR Pool
An experiment was performed at the ORR in order to find a good fission chamber location. Two locations on the pool side of the reactor tank were explored with a one inch diameter fission chamber. The thermal neutron flux attention was found to vary nearly exponentially with distance, and no shadowing effect could be seen during a reactor startup. The fission products high gamma flux could be discriminated without difficulties. Both positions seem to be adequate to locate a reactor control fission channel.
Date:
November 4, 1960
Creator:
Roux, D. P. & Colomb, A. L.
Object Type:
Report
System:
The UNT Digital Library
Analog Study of the Reference Design of the Gas-Cooled ORR Loop No. 1
A stimulation study of the deign as of June 1960 of the gas-cooled ORR Loop No. 1 was made using the ORNL analog computer. The proposed method of temperature control is evaluated, and the dynamic behavior of the loop for accidents and component failures is presented in graphical form.
Date:
November 8, 1960
Creator:
Ball, S. J.
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