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FMPC Solvent Treatment Area: Process Design

Description: Report presenting the process design for a solvent treatment area of the Feed Materials Production Center near Fernald, Ohio. The report discusses the basis for the detailed mechanical design and layout of this section of the refinery. Discussed in the report is the function of the section, the process for solvent treatment, utility requirements, and equipment list.
Date: July 6, 1951
Creator: Pfeiffer, Carl & Maerker, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process Engineering Report on Production of Thorium at Iowa State College

Description: Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
Date: January 16, 1952
Creator: Bulkowski, H. H.; Holby, G. V.; Pfeiffer, C.; Maerker, J. B. & Winn, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FMPC Solvent Treatment Area - Process Design

Description: This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date: July 6, 1951
Creator: Pfeiffer, Carl & Maerker, John B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of exploration at Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, July 1951-February 1952: an interim report

Description: "his interim report presents the grade and tonnage data collected during exploration at the Lost Creek schroeckingerite deposit, Sweetwater County, Wyoming, Between July 1951 and February 1952. Discussions of he geologic results of exploration (lithology, mineralogy, structure, origin, etc.) are not included in this report and consequently the detailed lithology and structure have been omitted from the illustrations (figs. 1-7)"
Date: July 1952
Creator: Sheridan, Douglas M.; Collier, John T. & Sears, Richard S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium Recovery Plant Design Report: Topical Report

Description: This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date: April 15, 1959
Creator: Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials Testing Reactor Project Handbook

Description: The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date: May 7, 1951
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Shielding Design Manual

Description: The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date: March 1956
Creator: Rockwell, Theodore, III
Item Type: Refine your search to only Book
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Description: Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Fabrication of Subassemblies for the Supercritical-Water Reactor

Description: In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UOâ‚‚ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Description: Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Ductility of Brazed Stainless Steel Joints

Description: 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 1… more
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Description: Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause obs… more
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electroplated Metals on Uranium for Aluminum Cladding

Description: 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 outg… more
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Description: Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 … more
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation and Consolidation of Electrolytic Thorium

Description: Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium fr… more
Date: June 15, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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