New Production Reactor Thermal Shielded Studies (open access)

New Production Reactor Thermal Shielded Studies

The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
Object Type: Report
System: The UNT Digital Library
Summary and Technical Specifications for the Dresden Nuclear Power Station (open access)

Summary and Technical Specifications for the Dresden Nuclear Power Station

This report supersedes the similarly titled report dated December 31, 1958. It describes briefly features of the Dresden plant and proposes technical specifications.
Date: December 31, 1958
Creator: General Electric Company
Object Type: Report
System: The UNT Digital Library

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Lubbock NTMS Quadrangle, Texas: Appendix C

Data collected as part of a hydrogeochemical and stream sediment reconnaissance of the Lubbock, Texas NTMS quadrangle including laboratory data on well water and stream sediments as well as field data.
Date: August 31, 1979
Creator: National Uranium Resource Evaluation Program
Object Type: Dataset
System: The UNT Digital Library
Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators (open access)

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

"A comparison of the grafting of a 2:1 molar mixture of methacrylic acid and styrene to both polypropylene film and fabric using CO60 source and electron accelerator as sources of ionizing radiation is made on the basis of mutual or simultaneous grafting and post-irradiation grafting.
Date: January 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources (open access)

Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources

"Rates of acetylene polymerization induced by Kr/sup 85/ in d-c fields were up to 15 times greater than those observed when no fields were imposed. Work to determine the relations between acetylene pressure, Kr/sup 85/ concentration, and the field intensity is continuing. In other activities, equipment is being designed to study the effects of megacycle electric fields on radioinduced chemical reactions."
Date: October 31, 1961
Creator: Graessley, William W. & Zufall, John W.
Object Type: Report
System: The UNT Digital Library
Hydrogeochemical and Stream Sediment Detailed Geochemical Survey for Thomas Range-Wasatch, Utah (open access)

Hydrogeochemical and Stream Sediment Detailed Geochemical Survey for Thomas Range-Wasatch, Utah

The following report provides results from a geochemical survey for Thomas Range-Wasatch, Utah. Field and laboratory data are presented for 15 groundwater and 79 stream sediment samples.
Date: August 31, 1980
Creator: Butz, T. R.; Bard, C. S.; Witt, D. A.; Helgerson, R. N.; Grimes, J. G. & Pritz, P. M.
Object Type: Report
System: The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reactions (open access)

Synthesis of Semiconductor Materials by Radiation Induced Reactions

""Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. Studies were continued on the radiation- and thermalinduced decomposition of sikane at 325 and 350 deg C. A preliminary value of G= 33 was obtained for silane."
Date: October 31, 1961
Creator: {{{name}}} & Goldman, Richard
Object Type: Report
System: The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reations (open access)

Synthesis of Semiconductor Materials by Radiation Induced Reations

"Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. The work performed during the period of this report consisted of the following: 1. Preparation of samples of trichlorosilane and hydrogen and subsequent thermal and irradiation studies, and analysis of these samples. 2. Preparation of mixed samples of silane and argon and subsequent thermal and irradiation studies and and analysis. 3. Outlining of future investigations to be conducted on this project."
Date: October 31, 1961
Creator: Held, Kelman & Goldman, Richard
Object Type: Report
System: The UNT Digital Library
Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959 (open access)

Attempted Modification of Susceptibility of Tumors to X-Radiation : Final Report for August 1 1957 to August 31, 1959

Attempts to secure a high degree of synchronization of cell division of the Krebs mouse ascites carcinoma, by combined use of aminopterin and citrovorum factor, and by use of colchicine and N-acetyl colchinol, were unsuccessful. In the course of the work, a new method for securing smears of ascites tumor cells was out, which we believe will be found useful
Date: December 31, 1959
Creator: Beck, Lyle Vibert, 1906-
Object Type: Report
System: The UNT Digital Library
Absorption of Organic Acids on Thoria (open access)

Absorption of Organic Acids on Thoria

The adsorption of acetic and oleic acids on the surface of thoria was studied by means of infrared spectroscopy. An infrared analysis of the adsorbates before and after adsorption using differential double bean methods indicated that the adsorption of organic acids on thoria surfaces occurs by an esterification reaction between the organic acid and the hydroxylated thoria surface. Ammonia vapor will not adsorb on thoria, indicated the basic character of the hydroxylated surface.
Date: December 31, 1959
Creator: Bradford, Harold R. & Wadsworth, Milton E.
Object Type: Report
System: The UNT Digital Library
High Energy Storage Ceramic Capacitor. Quarterly Report No. 5 [for] January 1, 1958 -- March 31, 1958 (open access)

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
Annual Report of Research Progress (open access)

Annual Report of Research Progress

This technical report constitutes a brief review of the work undertaken, entirely or in part, under the Contract AT(30-1)-1772 with eh United States Atomic Energy Commission. The work published during 1959 is listed at the end of this report and copies of the reprints or reports are attached where available. These investigations have been concerned with the examination of defect production and behavior as it may be observed by high frequency ultrasonic attenuation and velocity (modulus) changes in such materials as quartz, silicon, germanium, alkali halides (especially NaCl and XCl), high purity aluminum, and glass containing boron. The irradiations used are cobalt 60 gamma-ray irradiation and the reactor irradiation obtained in the Brookhaven National Laboratory graphite reactor.
Date: December 31, 1959
Creator: Truell, Rohn, 1913-1968
Object Type: Report
System: The UNT Digital Library
Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test (open access)

Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test

Chloride-induced stress-corrosion cracking has been encountered in the Homogeneous Reactor Test during the preliminary testing. The rector is constructed of austenitic stainless steels. It is unique in that it will operate at 250 to 300 C with an aqueous uranyl sulfate solution fuel containing 200 to 500 ppm of dissolved oxygen. The cracking has occurred in a secondary system used for detecting leaks in the flanged joints of the primary systems and in the grooves of flanges in the primary systems. Tubing used in the leak-detection system was found to be contaminated with chloride introduced during manufacture.
Date: January 31, 1957
Creator: Bohlmann, E. G. & Adamson, G. M.
Object Type: Report
System: The UNT Digital Library
Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957 (open access)

Quarterly Report of the Solution Corrosion Group for the Period Ending January 31, 1957

A second test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel has been completed. The joint and bellows have now received 104 thermal cycles and 148 mechanical deflections. The joint and bellows have functioned properly; corrosion damage has been negligible, except for a small area on the bellows which has undergone pitting attack. Long-term runs with uranyl sulfate solutions of the concentration proposed or use in the HRT have shown the solution to be stable at 300 C. Substituting heavy water for normal water caused no difference in either corrosion or solution stability. Experiments in which chromic acid was used to pretreat stainless steel have shown that, under certain conditions, the pretreated film can exist in uranyl sulfate solutions at flow rates in excess of the critical velocity for relatively long periods of time. The practicability of using titanium inserts in high turbulent areas of stainless steel loops to minimize corrosion has been demonstrated. The corrosiveness of beryllium sulfate solutions containing dissolved uranium trioxide has been determined at 250 and 280 C. Laboratory studies with regard to stress-corrosion cracking have shown that high stressed type 347 stainless steel will crack …
Date: January 31, 1957
Creator: Griess, J. C. F.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Object Type: Report
System: The UNT Digital Library
Carbon Steel in High Temperature Water (open access)

Carbon Steel in High Temperature Water

Resistance of carbon steel to corrosion in oxygenated high-temperature (250C) water was unexpectedly good at high oxygen concentration. Pertinent literature, critically examined, and toroid experiments indicted that at low oxygen concentration attack did increase with concentration, but as oxygen concentration was sufficiently increased, more protective films were formed on the metal. Some corrosion factors in the application of carbon steel to nuclear reactors systems are discussed.
Date: January 31, 1957
Creator: Moore, G. E.
Object Type: Report
System: The UNT Digital Library
Metallurgical Examination of HRT Leak Detector Tubing and Flanges (open access)

Metallurgical Examination of HRT Leak Detector Tubing and Flanges

After several failures had occurred in the HRT leak detector system, several lengths of this tubing were removed for metallurgical examination. The tubing was of type 304 stainless steel and was 1/4" in diameter with a 0.065 wall. The tubing had been purchased as three different lots, the first in 45 ft. lengths and the other two as standards lengths. Tubing from the first lot was used primarily for the shield penetration and, therefore, sections of it are present in all lines of the system. It appears that chloride contamination entered the system in a portion of the first lot of tubing used for the shield penetration. The exact source of the chloride cannot be determined, but after considering the results and visiting the manufacturer's plant, it appears most likely the contamination was during the manufacturing process.
Date: January 31, 1957
Creator: Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Object Type: Report
System: The UNT Digital Library
Comments on the Determination of the Particle Size Distribution of Thorium Oxide (open access)

Comments on the Determination of the Particle Size Distribution of Thorium Oxide

Factors affecting the results of thoria particle size distribution measurements by sedimentation procedures currently and recently employed are considered. The effects of thoria concentration, solvent, dispersant, thoria properties, and other factors are discussed.
Date: March 31, 1957
Creator: Moore, G. E.
Object Type: Report
System: The UNT Digital Library
Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT (open access)

Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT

Calculations indicate that it is impossible, even at high oxygen injection rates, to insure an excess of oxygen in the HRT fuel solution if the bubble letdown rate is more than 1 or 2 liters per minute. If, on the other hand, no bubbles are allowed to form, a reasonable excess oxygen concentration can be maintained with an oxygen injection rate which would not tax the capacity of the off-gas system. The xenon poison will be reduced to less than 2% by liquid letdown alone, and if an iodine absorption bed is installed below the catalytic recombiner, the xenon poison should be less than 1% without any bubble letdown. Therefore, it is recommended that sufficient copper be added to prevent the formation of gas bubbles and that the oxygen injection rate be limited to a value which would permit adequate holdup times in the present charcoal adsorption beds, assuming this quantity is sufficient to meet corrosion requirements.
Date: May 31, 1957
Creator: Haubenreich, P. N.
Object Type: Report
System: The UNT Digital Library
High Energy Storage Ceramic Capacitor. Quarterly Report No. 4 [for] August 19, 1957 -- December 31, 1957 (open access)

High Energy Storage Ceramic Capacitor. Quarterly Report No. 4 [for] August 19, 1957 -- December 31, 1957

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 fourth quarter included (1) Material development and sample preparation; (2) Sample testing; (3) discussion of ceramic density measurements; (4) Optical studies of titanates; (5) Fabrication of large ceramics; and (6) Capacitor design.
Date: October 31, 1960
Creator: Lupfer, D. A.
Object Type: Report
System: The UNT Digital Library
Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Dallas NTMS Quadrangle, Texas (open access)

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Dallas NTMS Quadrangle, Texas

From abstract: Results of a reconnaissance geochemical survey of the Dallas Quadrangle, Texas are reported. Field and laboratory data are presented for 284 groundwater and 545 stream sediment samples. Statistical and areal distribution plots of uranium and possible uranium-related variables are displayed. A generalized geologic map of the survey area is provided.
Date: July 31, 1981
Creator: National Uranium Resource Evaluation Program
Object Type: Report
System: The UNT Digital Library