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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress details ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.
Date: October 23, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, William B.
Partner: UNT Libraries Government Documents Department
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The Application of Tracer Techniques to the Determination of Uranium Extraction Coefficients

Description: Abstract: This report deals with the development of a method using tracer technique for determining uranium extraction coefficients on solutions of low uranium concentration. It was found that extraction coefficients could be determined on systems containing as low as one part per million uranium using 1900 level uranium as the tracer. Results of several extraction series are presented in which aluminum nitrate is used as the salting agent and dibutyl carbitol the organic extractant.
Date: January 23, 1947
Creator: Lee, D. A.; Woodard, R. W. & Clewett, G. H.
Partner: UNT Libraries Government Documents Department
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Automatic Mass Spectrometer for Monitoring Uranium Isotope Concentrations

Description: Abstract: An automatic recording mass spectrometer has been designed; two instruments have been constructed and have operated reliably for more than seven years as process monitors.
Date: January 23, 1963
Creator: Langdon, A.; Evans, E. C. & Tabor, Charles Dewey
Partner: UNT Libraries Government Documents Department
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The Brookhaven Chemonuclear in-Pile Test Loop

Description: Technical report outlining the plan to develop the Brookhaven chemonuclear in-pile test loop because the interest in utilizing reactor radiation energy (fission-fragment recoil and neutron-gamma) for production of chemicals has developed to the point where a loop to study chemonuclear system in a reactor under dynamic conditions is necessary.
Date: April 23, 1962
Creator: Tucker, Walter D.; Waide, C.; Bezler, P. & Steinberg, Meyer, 1924-
Partner: UNT Libraries Government Documents Department
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Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Description: Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Partner: UNT Libraries Government Documents Department
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Caustic Treatment of Zircon in the Preparation of Pure Zirconium Compounds

Description: From abstract: This investigation was conducted in order to develop a process whereby the most abundant zirconium ore, namely zircon, could economically be put into solution and purified adequately for use in hafnium separation processes employing liquid-liquid extraction. Secondary aims concerned the preparation of pure zirconyl chloride, zirconyl nitrate, zirconyl sulfate, and zirconium oxide from the zircon ore.
Date: June 23, 1953
Creator: Spink, Donald R. & Wilhelm, Harley A.
Partner: UNT Libraries Government Documents Department
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Co60 Vitamin B12 Binding Capacity of Human Leukocytes

Description: This report examines the "vitamin B12 binding capacity of leukocytes obtained from three normal subjects and 19 persons with various hematologic disorders."
Date: April 23, 1962
Creator: Myer, Lee M.; Cronkite, Eugene P.; Miller, Inez F.; Mulsac, Claire W. & Jones, Irving
Partner: UNT Libraries Government Documents Department
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Continuous injection processing

Description: From introduction: "In this report we consider a few non-adiabatic processes. The types to be discussed will be limited because of two reasons: first, complete descriptions are available for some processes; second, as time goes on alternative injection methods undoubtedly will be discovered, so this list must necessarily be incomplete."
Date: September 23, 1955
Creator: Linlor, William I., 1915-
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steels in Purex Acid Concentrators

Description: The corrosion resistance of four types of austenitic stainless steels to Purex process first and second acid concentrator bottoms was determined. Although the compositions of the two solutions were very similar, tests in simulated solutions of both compositions were conducted to strengthen the basis for the conclusions which were to be made.
Date: April 23, 1953
Creator: Sanborn, Kenneth L.
Partner: UNT Libraries Government Documents Department
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Cost Estimate for the Food Irradiation Reactor

Description: Study conducted for the U. S. Army Reactors Branch of reactors for the irradiation of food.
Date: August 23, 1956
Creator: Jaffe, R. J.; Larson, A. M., Jr.; Leyse, C. F.; Mason, E. E. & Sliger, R. W.
Partner: UNT Libraries Government Documents Department
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The Decay of Induced Activity in Portland, Barytes, and Brookhaven Cements

Description: The following report describes results from a study of three types of cement (Barytes, Brookhaven, and Portland) exposed in the ORNL Reactor for periods of seven and twenty-eight days.
Date: August 23, 1950
Creator: Bowman, W. H.; James, D. L. & Roarty, J. D.
Partner: UNT Libraries Government Documents Department
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Demand Computer for Project SIR

Description: Abstract: "A description of the demand computer and its functions is given. Methods of testing and adjusting, and gain and response curves for the system and its parts are included."
Date: March 23, 1953
Creator: Raber, R. A.
Partner: UNT Libraries Government Documents Department
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Dependence of Thermal Utilization and Resonance Escape Probability Upon Fuel Element Density in D₂O Cooled and Moderated Systems

Description: Abstract: "The effect of variation in fuel element density upon f, p in a D2O cooled and moderated lattice of cylindrical fuel elements is investigated. The CP-3 lattice is chosen as a reference. The effect of a source term in the fuel element is considered. f, p are calculated as functions of "a", the ratio of the modified fuel element density to the original (fuel only) density. Curves showing f(a), p(a) are included. It is concluded that a 1 per cent decrease in the product, f(d), p(a) is no… more
Date: April 23, 1952
Creator: Garvey, J. E. & Stevens, F.
Partner: UNT Libraries Government Documents Department
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Determination of Possible Failed Blanket Elements Using the FEDAL System. Section I. First Performance. Core I, Seed 1. Test Results DL-S-2810S, RNI-24

Description: The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power … more
Date: November 23, 1959
Creator: Pazuchanics, Nicholas & Kearns, Walter
Partner: UNT Libraries Government Documents Department
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The Determination of Thorium in Uranium-Thorium Alloys, Using Cupferron

Description: Technical report describing that the use of controlled amounts of carbonate, acting both as complexing agent buffer led to a fairly satisfactory procedure for the determination of Th in Th-U alloys, using cupferron. The alloy, dissolved in NHO2, in the presence of HF, is treated with H2SO4 and the mixture is evaporated in SO2 fumes. The solution is diluted and (NH4)2CO2 is added. Th is precipitated from this solution with cupferron. The precipitate is weighed as ThO2 after ignition. An accura… more
Date: November 23, 1945
Creator: Eckert, A. C. & Bane, R. W.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Partner: UNT Libraries Government Documents Department
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Drilling in the Flatirons Locality, Monument Valley, Arizona

Description: From introduction: A subsurface exploration program was undertaken to investigate the concentration of uranium and vanadium in or near the base of the Shinarump member of the Chinle formation in the Flatirons locality, and to develop criteria whereby adjacent unexplored areas could be evaluated as to potential production capacity from study of geological and mineralogical features at the host rook outcrop. An earlier study of the area by C. G. Evensen of the U. S. Atomic Energy Commission had s… more
Date: August 23, 1957
Creator: Gray, Irving B.
Partner: UNT Libraries Government Documents Department
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