The Preparation of Beta Silicon Carbide (open access)

The Preparation of Beta Silicon Carbide

This report explores the production of beta silicon carbide, a low-temperature, cubic modification of cubic silicon carbide. The temperature, heating time, type of starting material, and proportion of starting materials were all varied in order to test yields of beta silicon carbide.
Date: December 29, 1952
Creator: Gambino, J. R.; Mixer, W. G., Jr.; Wagner, H. E. & Harman, Cameron G.
System: The UNT Digital Library
Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements (open access)

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.
System: The UNT Digital Library
Mechanical Properties of Zirconium-Tin Alloys (open access)

Mechanical Properties of Zirconium-Tin Alloys

Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."
Date: December 22, 1952
Creator: Schwope, A. D. & Chubb, Walston
System: The UNT Digital Library
The Rolling of Uranium (open access)

The Rolling of Uranium

The following report discusses the method of rolling uranium rods and strips under various rolling conditions and the roll-separating force measured.
Date: December 30, 1952
Creator: Saller, Henry A.; Keeler, J. R. & Donley, R. J.
System: The UNT Digital Library
Topical Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Topical Report on Refining of MgX and Other Uranium-Bearing Materials

This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
Date: December 31, 1950
Creator: Ewing, R. A.; Belcher, R. L.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
The Rolling of Thorium Rod (open access)

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.
System: The UNT Digital Library
A Study of Thorium-Base Alloys (open access)

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-
System: The UNT Digital Library
Progress Report on the Concentration of Pitchblende (open access)

Progress Report on the Concentration of Pitchblende

Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date: December 31, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Development of Methods for End Capping PWR Fuel Elements (open access)

Development of Methods for End Capping PWR Fuel Elements

The following report discusses the development of methods for sealing the ends of metallic-cored fuel rods.
Date: December 28, 1955
Creator: Vagi, J. J. & Martin, D. C.
System: The UNT Digital Library
Further Studies with the GCRE Critical-Assembly (open access)

Further Studies with the GCRE Critical-Assembly

This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
System: The UNT Digital Library
Delta-Phase Zirconium Hydride as a Solid Moderator (open access)

Delta-Phase Zirconium Hydride as a Solid Moderator

Abstract: "In a study of the preparation and properties of delta-phase zirconium hydride it was found that large, sound bodies of the hydride can be prepared by direct combination of the elements if the rate of the reaction is retarded by limiting the supply of available hydrogen. Specimens up to 1-in. diameter were prepared using this technique. Because delta phase zirconium hydride does not readily form eutectics with iron-and nickel-base alloys below 1800 F these materials may be utilized for clodding the hydride. Delta-phase zirconium hydride is unaffected by exposure to liquid NaK or to nitrogen gas at temperatures below 1000 F. The hot hardness of delta-phase zirconium hydrid is about 130 kg per mm-2 at room temperature and 40 kg per mm-2 at 1500 F. The mean coefficient of thermal expansion (68 to 1337 F) is 6.5 x 10^-6 per deg F. The thermal conductivity varies from 5.7 Btu/(ft)(hr)(F) at 300 F to 5.1 Btu/(ft)(hr)(F) at 1300 F."
Date: December 18, 1957
Creator: Vetrano, James B.
System: The UNT Digital Library
The Cladding of Delta-Phase Zirconium Hydride (open access)

The Cladding of Delta-Phase Zirconium Hydride

Abstract: A study has been made of the cladding of solid and powdered delta-phase zirconium hydride is both red and flat shapes with stainless steel. The program included investigations of metallurgical bonding, both with and without the sore of metallic barrier materials. Types 304 and 347 stainless steel were used for cladding material. The intermediate barrier-layer materials used were niobium, molybdenum, a combination of copper and molybdenum, and a combination of copper and niobium. The pressure-bonding techniques, involving the use of gas pressure at elevated temperatures, was employed in this study. Variable times and temperatures with a constant pressure of 10,000 poi were utilized by produce bonding. In this study, the best results were archived is cladding delta-phase zirconium hydride directly with Types 304 or 347 stainless steel. Good bonds were obtained by pressure bonding at 1600 F for 3 or 4 hr subsequent to pressure bonding at 1900 F for 1 to 2 hr at a pressure of 10,000 poi. Partial bonding was achieved between niobium and zirconium hydride and molybdeum and girconium hydride.
Date: December 27, 1957
Creator: Paprocki, Stan J.; Hodge, Edwin S. & Boyer, Charles B.
System: The UNT Digital Library