Degree Level

Protective Coatings for Molybdenum (open access)

Protective Coatings for Molybdenum

Report discussing studies on various types of protective coatings for a molybdenum sheet. Procedures, materials, and results of each coating are included.
Date: February 17, 1953
Creator: Powell, Carroll F.; Jones, R. P.; Secrest, A. C.; Sherwood, E. M. & Campbell, Ivor E.
Object Type: Report
System: The UNT Digital Library
Creep Strength of Uranium Alloys at 1500 and 1800 F (open access)

Creep Strength of Uranium Alloys at 1500 and 1800 F

Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates were obtained in composites of 90 wt % molybdenum-10 wt % UO2 by a stress of 12,000 psi."
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Object Type: Report
System: The UNT Digital Library
The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures (open access)

The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

Abstract: "The solubility of oxygen in uranyl sulphate solutions and in water at 212, 275, and 325 F, and at oxygen partial pressures up to 1500 psia was investigated. The results are presented in tabular and graphic form. The solubility is proportional to the partial pressure of oxygen. The ratio of solubility in the uranyl sulphate solution to solubility in water at the same temperature and pressure is a function of the concentration of the salt in solution."
Date: June 10, 1953
Creator: Pray, H. A. & Stephan, Elmer F.
Object Type: Report
System: The UNT Digital Library
The Ductility of Brazed Stainless Steel Joints (open access)

The Ductility of Brazed Stainless Steel Joints

Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Object Type: Report
System: The UNT Digital Library
The Application of Ceramics to Hanford Fuel Elements (open access)

The Application of Ceramics to Hanford Fuel Elements

From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
Date: September 4, 1953
Creator: King, B. W.; Tripp, H. P. & Duckworth, W. H.
Object Type: Report
System: The UNT Digital Library
Terminal report on the Radiolanthanum Laboratory (open access)

Terminal report on the Radiolanthanum Laboratory

A report which intends to acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the radiolanthanum process and to define the terminal status of the design of this laboratory and its equipment.
Date: July 21, 1950
Creator: Figenshau, J. K.
Object Type: Report
System: The UNT Digital Library
Apparent viscosity of simulated underground metal waste slurries (open access)

Apparent viscosity of simulated underground metal waste slurries

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
Date: June 20, 1950
Creator: Allen, A. W.
Object Type: Report
System: The UNT Digital Library
The Properties of High-Uranium Alloys Containing Zirconium or Chromium (open access)

The Properties of High-Uranium Alloys Containing Zirconium or Chromium

From abstract: "Various physical and mechanical properties have been determined for high- and low-carbon base uranium, uranium-chromium, and uranium-zirconium alloys. These data complement those obtained at ANL on the same materials."
Date: February 21, 1955
Creator: Saller, Henry A. & Rough, Frank A.
Object Type: Report
System: The UNT Digital Library
Extrusion Cladding of Fuel Element (open access)

Extrusion Cladding of Fuel Element

From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."
Date: March 22, 1955
Creator: Slunder, C. J.; Fiorentino, R. J. & Hall, A. M.
Object Type: Report
System: The UNT Digital Library
Aluminum Cladding Long Uranium Plates by Solid-State Bonding (open access)

Aluminum Cladding Long Uranium Plates by Solid-State Bonding

From introduction: This report covers an investigation of solid-state bonding as a technique for aluminum cladding uranium plates of 3 by 0.180-in. cross section in lengths up to 14 ft.
Date: March 29, 1955
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
Object Type: Report
System: The UNT Digital Library
Electrodeposition of Aluminum on Uranium (open access)

Electrodeposition of Aluminum on Uranium

Abstract: "Aluminum electroplating was studied in a search for new methods of cladding uranium fuel elements. Uranium electroclad with 12 mils of aluminum over a 0.5-mil (or nickel plus copper) electroplate resisted corrosion for more than 100 hr in boiling water. This quality of protection was effected by hot pressing the electroclad uranium with 5.1 tons per sq in. for 5 min at 950 F. The electroclad uranium with hot-pressed samples paralleled those of later experiments with hot-pressed wrought aluminum claddings on uranium. In both cases, the uranium was electroplated with thin (0.5 mil) layers of metals to prevent aluminum-uranium diffusion, to aid bonding, and to assist in corrosion protection. This aluminum electroplating study helped to define the importance of the intermediate coating between the aluminum and the uranium, the effect of good bonds between the various layers, and the effects of hot pressing in protecting uranium with an aluminum cladding."
Date: March 30, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding (open access)

Electroplated Metals on Uranium for Aluminum Cladding

Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Apparatus for visual study of corrosion by hot water (open access)

Apparatus for visual study of corrosion by hot water

Report describing an apparatus for visual study of corrosion of uranium by hot water. A windowed autoclave was designed and constructed to permit visual study of the reaction under conditions simulating a cladding failure in service.
Date: 1955
Creator: Grieser, Daniel R. & Simons, Eugene M.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment (open access)

Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment

Introduction: "The uranium-5 w/o chromium alloy has been intensively investigated for use in a power reactor in the as-cast condition. However, when cast sample fuel elements were subjected to irradiation, their stability was found to be unsatisfactory. In order to improve the behavior of the alloy, a program of grain refinement by heat treatment was begun. The effect of chill casting on the heat-treated grain size was also investigated."
Date: May 13, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Low-Melting Alloys for Cast Fuel Elements (open access)

Low-Melting Alloys for Cast Fuel Elements

The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.
Date: May 19, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Ceramic Investigations of UO₂ (open access)

Ceramic Investigations of UO₂

This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Object Type: Report
System: The UNT Digital Library
Annealing of crystal distortion in irradiated graphite (open access)

Annealing of crystal distortion in irradiated graphite

From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
Date: 1955
Creator: Austin, Alfred E. & Harrison, Ralph J.
Object Type: Report
System: The UNT Digital Library
The Roll Cladding of Uranium With Aluminum (open access)

The Roll Cladding of Uranium With Aluminum

Report discussing a study regarding rolling as a technique for making uranium fuel elements that are flat-plate and aluminum-clad.
Date: August 3, 1954
Creator: Saller, Henry A.; Paprocki, Stan J. & Delaney, J. F.
Object Type: Report
System: The UNT Digital Library
Diameter Measurements of Slugs Before and After Prolonged Heat Treatment (open access)

Diameter Measurements of Slugs Before and After Prolonged Heat Treatment

Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."
Date: February 16, 1948
Creator: Bennett, Carl A. & Lane, J. J.
Object Type: Report
System: The UNT Digital Library
Redox Process Chemistry: Freezing Point Data for UNH - NH₄NO₃ - HNO₃ - H₂O Systems (open access)

Redox Process Chemistry: Freezing Point Data for UNH - NH₄NO₃ - HNO₃ - H₂O Systems

Report presenting data on freezing point for UNH - NH₄NO₃ - HNO₃ - H₂O Systems. A range of concentrations of systems was used and data is presented.
Date: July 7, 1948
Creator: Harmon, M. K. & Cooper, V. R.
Object Type: Report
System: The UNT Digital Library
General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948 (open access)

General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948

Introduction: "This report covers progress on the testing of the General Engineering and Consulting Laboratories Turbine Pump No. 1 from May 1, 1948 to Jun 15, 1948. All testing prior to April 30, 1948 has been described in Redox Experiment Testing Report No. 1 (Document HW-9474) and No. 2 (Document HW-9694)."
Date: June 21, 1948
Creator: Stringer, J. T. & Allen, A. W.
Object Type: Report
System: The UNT Digital Library
Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions (open access)

Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions

The following report studies an estimation of the amount of Pu(III) and Pu(IV) present in the IBP Stream, with the purpose of establishing an analytical, method suitable for routine control analysis. A method is discussed that is based on carrying Pu(IV) upon a zirconium phanylarsonate precipitate.
Date: June 30, 1948
Creator: Ice, C. H.
Object Type: Report
System: The UNT Digital Library
Redox Equipment Testing Report No. 4 (open access)

Redox Equipment Testing Report No. 4

A report which covers progress on the testing of the General Engineering and Consulting Laboratory Turbine Pump No. 1 from June 16, 1948, to July 31, 1948.
Date: August 9, 1948
Creator: Cooper, V. R. & Allen, A. W.
Object Type: Report
System: The UNT Digital Library
Boron stainless steel for drop rods (open access)

Boron stainless steel for drop rods

From introduction: "The present investigation of the properties of boron stainless steel is an outgrowth of a project started in 1947. The problem is to replace the present steel used for drop rods in the Hanford piles with a material much less subject to corrosive attack from the humid atmosphere existing at the location of the rods."
Date: September 7, 1948
Creator: Callen, A. C. & Heckman, A. L.
Object Type: Report
System: The UNT Digital Library