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Dynamic Corrosion and Mass Transfer of Chrome Steel by Bismuth
From introduction: "This report summarizes the experimental data obtained at the San Pablo Laboratory on the corrosion of 5% Cr - 0.5% Mo steel by bismuth under conditions that allow mass transfer to occur. The bismuth is circulated through a temperature gradient by means of a thermosiphon loop."
Date:
December 14, 1951
Creator:
Egan, C. J.
Object Type:
Report
System:
The UNT Digital Library
Short Time Corrosion Tests of Bronze, Mild Steel, T-304 Stainless Steel and 2S Aluminum in 10% Potassium Tetraborate Solution
Report summarizing corrosion tests meant to determine the corrosion rates of bronze, mild steel, T-304 stainless steel and 2S aluminum in 10% potassium tetraborate solution. Tests were completed under the boiling point of each solution except for 2S aluminum, which was tested at 40C, the approximate temperature in a pile.
Date:
December 14, 1951
Creator:
Katayama, Y. B.
Object Type:
Report
System:
The UNT Digital Library
The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia
Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date:
December 15, 1951
Creator:
Perlman, M. L. & Bigeleisen, J.
Object Type:
Report
System:
The UNT Digital Library
The Vanadium-Uranium Constitutional Diagram
Abstract: "Vanadium-uranium equilibrium studies were made on alloys prepared from high-purity vanadium and good biscuit uranium. No intermetallic phases occur in the system. Additions of vanadium lover the uranium melting point and transformations producing a eutectic at 1240 +/- 5 C and eutectoid reactions at 727 +/- 5 and 652 +/- 5 C. The maximum solubility of uranium in vanadium is about 4 atomic per cent (15 weight per cent)."
Date:
December 15, 1951
Creator:
Saller, Henry A. & Rough, Frank A.
Object Type:
Report
System:
The UNT Digital Library
Expressions for Conversion Ratio in a Th-U²³⁵ Converter
"This memo shall be an attempt to write down in a consistent manner some expressions for conversion ratio so that a comparison can be made with regard to a uniformly loaded core versus a flattered zone surrounded by an unloaded region. The discussion will be limited to the type of loading that is at present being considered for the reactor - a checkerboard array of MTR fuel elements and feed elements; the unloaded reactor will consist of fuel elements only."
Date:
December 19, 1951
Creator:
Cohen, E. Richard, 1922- & Benton, A.
Object Type:
Report
System:
The UNT Digital Library
The Rolling of Thorium Rod
Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."
Date:
December 19, 1951
Creator:
Saller, Henry A.; Keeler, J. R. & Donley, R. J.
Object Type:
Report
System:
The UNT Digital Library
Thorium and Thorium Alloys Preliminary Corrosion Tests
Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]
Date:
December 19, 1951
Creator:
Olsen, Arnold R.
Object Type:
Report
System:
The UNT Digital Library
Corrosion of Stainless Steel Type 309SCB in 200 Area Dissolver Solution Containing Mercuric Ion
The following report provides data from corrosion tests meant to evaluate the performance of Type 3098Cb stainless steel in BiP04 process dissolver solution containing mercuric ion.
Date:
December 20, 1951
Creator:
Sanborn, K. L.
Object Type:
Report
System:
The UNT Digital Library
Densitometric Determination of Iron in Plutonium
"The attached report summarizes the work performed in the establishment of an improved spectrographic method for determining iron in plutonium."
Date:
December 20, 1951
Creator:
Daniel, J. L.
Object Type:
Report
System:
The UNT Digital Library
The Polarographic Determination of Titanium in Plutonium Solutions
A polarographic method for the determination of titanium in the presence of plutonium has been devised. Hydrochloric acid solutions of plutonium and titanium are reduced with zinc, made one molar in tartaric acid, and further reduced in the polarographic cell with liquid zine amalgam. Plutonium is thus reduced to the non-interfering (III) oxidation state and a well defined anodic wave for the oxidation of titanium (III) to titanium (IV) is obtained. The height of this wave is directly proportional to the titanium concentration for plutonium-titanium solutions containing 20 grams plutonium per liter. The precision for the analyses of duplicate samples has been calculated at the 95 percent confidence level to be 2.9 percent for those containing 0.025 to 0.050 gm titanium per liter and 1.1 percent for those containing 0.089 to 0.51 gm titanium per liter.
Date:
December 20, 1951
Creator:
Smith, Maynard E. (Maynard Elliott)
Object Type:
Report
System:
The UNT Digital Library
A Study of Thorium-Base Alloys
Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
Date:
December 26, 1951
Creator:
Goldhoff, R. M.; Ogden, Horace R. & Jaffee, Robert Isaac, 1917-
Object Type:
Report
System:
The UNT Digital Library
Diffusion Equation Green's Functions for Box Problems
The use of diffusion theory to attempt to reproduce the chemical data of Hicks and Stevenson for the spatial distribution of neutrons in a solid block of uranium that is bombarded by 190 Mev neutrons is described.
Date:
December 27, 1951
Creator:
Adelman, F.; Lepore, J. & Rosenblum, M.
Object Type:
Report
System:
The UNT Digital Library
Supplement to Document HW-21374 -- Multiplication Constants for Hanford Type Lattices: Graphite of Variable Density
Report discussing "the effect on the multiplication constant of using graphite of various density." Results are tabulated and plotted.
Date:
December 28, 1951
Creator:
Dahlberg, Richard C.
Object Type:
Report
System:
The UNT Digital Library
Potentiometric Titration of Milligram Quantities of Uranium in the Presence of Iron
Report discussing "the reduction of uranium(VI) with a slight excess of chromous sulfate followed by a potentiometric titration of the uranium(IV) with standard ceric sulfate in an atmosphere of carbon dioxide." This method cannot be used at room temperature.
Date:
December 29, 1951
Creator:
Hahn, Richard Balser & Kelley, Myron T.
Object Type:
Report
System:
The UNT Digital Library
The Electrical Conductivity of Uranyl Sulfate and Uranyl Fluoride in Aqueous Solution
The following report records the investigation of the conductivity of uranyl sulfate and uranyl fluoride in aqueous solution at several temperatures and in various concentrations."
Date:
December 1952
Creator:
Brown, Robert D.; Bunger, W. B.; Marshall, W. L. & Secoy, C. H.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements
Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."
Date:
December 1, 1952
Creator:
Harman, Cameron G.; Ferrell, Edward Francis.; Wagner, H. E. & Quirk, J. F.
Object Type:
Report
System:
The UNT Digital Library
Neoprene and Nickel Linings : NYX Test No. 1.3.4
Abstract: "Stainless steel valves, pumps, and heat exchangers were not available for NYX start-up. Cast iron and steel equipment was protected against corrosion by lining with neoprone and nickel plate. The linings failed under flow conditions and their use was discontinued. Chromate inhibitor was used to reduce rusting for the reminder of the test program."
Date:
December 1952
Creator:
Poss, Fred J. & Longtin, Bruce
Object Type:
Report
System:
The UNT Digital Library
Scintillation Counting of Natural Uranium Foils
Report discussing studies of uranium scintillation counting, which discriminates against certain types of decay and fission activity.
Date:
December 1952
Creator:
Axtmann, Robert C. & Stutheit, James S.
Object Type:
Report
System:
The UNT Digital Library
Dissolution of NaK
Abstract: "A rapid yet safe method for the dissolution of sodium-potassium alloys prior to chemical or instrumental analysis has been devised. The alloy is submerged beneath the surface of an inert organic reagent and dissolved at a controlled rate by adding methanol drop-by-drop. A blanket of inert gas is maintained over the reaction flask. The procedure has been successfully used to dissolve samples of NaK in the range of 0.05 to 25 grams."
Date:
December 2, 1952
Creator:
White, J. C.; Talbott, C. K. & Brady, L. J.
Object Type:
Report
System:
The UNT Digital Library
Initial Investigation of the Mechanical Properties of Uranium at Elevated Temperatures
Introduction: "Knowledge of the mechanical properties of uranium at elevated temperature is essential in order to understand and predict the fabrication characteristics and pile behavior of this metal. This report presents the experimental data obtained from beta heat-treated specimens which were originally machined from one production, alpha-rolled uranium rod."
Date:
December 2, 1952
Creator:
Hueschen, R. E. & Pitt, C. H.
Object Type:
Report
System:
The UNT Digital Library
The Decomposition of Light and Heavy Water Boric Acid Solutions by CP-3' File Radiations
The behavior of light and heavy water solutions of boric acid toward pile radiations has been investigated as a function of boric acid concertation. A study has also been made of the effect of hydrogen, hydrogen peroxide, and potassium iodide on the radiation stability of boric acid solutions.
Date:
December 3, 1952
Creator:
Hart, Edwin J. (Edwin James), 1910-; McDonell, William R. & Gordon, Sheffield
Object Type:
Report
System:
The UNT Digital Library
Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions
Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."
Date:
December 5, 1952
Creator:
Wagner, R. M.
Object Type:
Report
System:
The UNT Digital Library
Heat Exchanger Design Charts
From introduction: "The ORNL-ANP liquid-to-liquid heat exchanger design and development effort has been based on an exceptionally high performance matrix of closely-spaced small diameter tubes that permits practically pure counter-flow operation. In the course of full-scale aircraft power plant design work a number of charts for this type of heat exchanger has been prepared. These charts were intended in part to show the effects of the various parameters in a readily understandable form, and in part to simplify and to reduce markedly the chore of making detailed design calculations. These charts have proved so helpful it seemed very worthwhile to assemble them into a report along with brief explanations and sample calculations."
Date:
December 7, 1952
Creator:
Fraas, A. P. & LaVerne, M. E.
Object Type:
Report
System:
The UNT Digital Library
MTA Quarterly Progress Report - June, July, August, 1952
MTA quarterly progress report for June-August 1952
Date:
December 8, 1952
Creator:
University of California Radiation Laboratory
Object Type:
Report
System:
The UNT Digital Library