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Metallurgical Examination of HRT Leak Detector Tubing and Flanges

Description: 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… more
Date: January 31, 1957
Creator: Adamson, G. M; Hammond, T. M.; Kegley, T. M. & White, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stress-Corrosion Cracking Problems in the Homogeneous Reactor Test

Description: 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 syste… more
Date: January 31, 1957
Creator: Bohlmann, E. G. & Adamson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, August 1959. Chemical Technology Division

Description: The concentration gradients of uranyl ion in aqueous and organic solutions were analyzed, two Druhm runs were terminated due to malfunction, calculations of particle temperature were performed, materials handling flowsheets were completed, and a literature survey is being conducted.
Date: December 31, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E. (Marvin E.), 1926-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Paper Presented At UCC Mass Transfer Meeting Held In Buffalo, New York; Transfer Of Uranyl Ion Across A Water - TBP Interface

Description: The steady state transfer of uranyl nitrate across a quiescent interface between water and tri-n-butyl phosphate in kerosene was studied in an attempt to elucidate the mechanism of transfer in solvent extraction operations.
Date: March 31, 1960
Creator: Chester, C. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Californium Production in the High Flux Isotope Reactor

Description: Californium-252 and other isotope production rates resulting from irradiating Pu-242 in the proposed High Flux Isotope Reactor were estimated. The effect of curium recycle was investigated and optimum irradiation cycles determined.
Date: August 31, 1959
Creator: Claiborne, H. C. & Lietzke, Marjorie P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of Radial Neutron-Flux Distribution in EGCR Lattice Cell

Description: The Neutron-flux distributions in an EGCR cell containing seven rod clusters of 2.0 and 2.6% enriched uranium oxide have been obtained by using a one-velocity, one-dimensional P-3 solution to the neutron-transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experimental and calculated distributions. Flux traverses in the outer rod perpendicular to a diameter of the cluster are also presented.
Date: August 31, 1959
Creator: DeBoer, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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UO2 Fuel Cluster Study

Description: The reactor physics aspects of a number of different UO2 cluster geometries were determined as a function of various parameters. These parameters included number of rods in cluster, cladding materials, cladding thickness, cored and uncored rods, lattice pitch, rod size, and inter-rod spacing. Lifetime calculations were made on the basis of batch loading and uniform exposure for 5000 and 7500 Mwd/MT-UO2.
Date: December 31, 1959
Creator: Delene, J. G. & Row, T. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comment On Calculations By Lietzke And Stoughton On Concentrations Of Species In Aqueous UO2SO4 Solutions As A Function Of Temperature

Description: Using the same techniques as Lietzke and Stoughton, the solubility of silver sulfate in uranyl sulfate solutions was measured and analyzed. A general IBM-704 computer code was written which could calculate the concentration of all the species assumed to be present in the solutions.
Date: March 31, 1960
Creator: Greeley, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 soluti… more
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Letdown Rates and Oxygen Injection Rates on Xenon Poison Level and Excess Oxygen Concentration in the HRT

Description: 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 absor… more
Date: May 31, 1957
Creator: Haubenreich, P. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R. J. & Wischow, R. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbon Steel in High Temperature Water

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comments on the Determination of the Particle Size Distribution of Thorium Oxide

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study Of Outage Experience With Selected Boiler And Turbine Generator Units

Description: Because of consideration that is being given to the feasibility of building small nuclear power plants to operate for one to three years with no attention or maintenance it was decided to appraise the degree of reliability that might be anticipated in conventional systems. A preliminary study was made of outages in both common header turbine generator and the unit-type boiler-turbine generator plants. Data from portions of the operating periods for the 187 unit TVA system and the 14 unit ORGDP … more
Date: March 31, 1960
Creator: Myers, M. L. (Millard L.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Progress Report for October Through December, 1959

Description: The status of the Eurochemic (European Company for the Chemical Processing of Irradiated Fuels) Organization and the preliminary plant design are summarized. This report covers the progress during the period October through December 1959, gives the status of the program as of January 1, 1960, and outlines the anticipated assistance from the United States for the next 6 months.
Date: March 31, 1960
Creator: Nicholson, E. L. & Shank, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unit Operations Section Monthly Project Report March 1960 - Chemical Technology Division

Description: Progress is reported on fuel cycle development, HR thorium blanket studies, ion exchange, power reactor fuel processing, solvent extraction studies, volatility and waste processing.
Date: May 31, 1960
Creator: Whatley, M. E. (Marvin E.), 1926-; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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