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Production of Zirconium at Y-12 (open access)

Production of Zirconium at Y-12

Abstract: "A general description is given of the permanent zirconium plant at Y-12. Equipment is described and materials of construction are listed. Photographs illustrating principal equipment and reduced construction drawings are also presented. Operating conditions and costs information are listed."
Date: November 17, 1955
Creator: Ramsey, J. W. & Whitson, W. K., Jr.
Object Type: Report
System: The UNT Digital Library
Status Report and Plant Proposals for Zirconium Purification (open access)

Status Report and Plant Proposals for Zirconium Purification

From abstract: "This report contains a summary of the latest improvements in zirconium purification as developed by the Y-12 research, pilot plant, production, and engineering groups, all of whom have been generously cooperating in this project."
Date: November 18, 1955
Creator: Leaders, W. M.
Object Type: Report
System: The UNT Digital Library
Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant (open access)

Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as ninety percent hafnium, can be made available with little additional cost.
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Object Type: Report
System: The UNT Digital Library
Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report (open access)

Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Object Type: Report
System: The UNT Digital Library
FUDGE 4A: A Computer Program for Gamma Dose Rate Distribution from Rectangular Sources (open access)

FUDGE 4A: A Computer Program for Gamma Dose Rate Distribution from Rectangular Sources

Report issued by the Brookhaven National Laboratory discussing the recently modified FUDGE 4A computer program. As stated in the introduction, "this report presents the details and technical information required for the proper use of FUDGE 4A" (p. 1). This report includes tables, and illustrations.
Date: August 1968
Creator: Galanter, Leonard & Krishnamurthy, Krishnaswamy
Object Type: Report
System: The UNT Digital Library
Power Plant Operating and Maintenance Costs (open access)

Power Plant Operating and Maintenance Costs

Report issued by the Brookhaven National Laboratory discussing costs of power plant operations. As stated in the objective, "the objective of this study was to determine and evaluate operating and maintenance costs for nuclear power plants" (p. 1). This report includes tables, and illustrations.
Date: April 1970
Creator: Susskind, H. & Raseman, C. J.
Object Type: Report
System: The UNT Digital Library
Operating Manual for the PSE&G Hydrogen Reservoir Containing Iron Titanium Hydride (open access)

Operating Manual for the PSE&G Hydrogen Reservoir Containing Iron Titanium Hydride

Report issued by the Brookhaven National Laboratory discussing the operation of a hydrogen reservoir. As stated in the introduction, "information is provided on how the reservoir functions and how it can be safely operated. The equipment is described and basic operating procedures are given along with precautionary measures" (p. 1). This report includes tables, illustrations, and photographs.
Date: February 1974
Creator: Strickland, G. & Reilly, J. J.
Object Type: Report
System: The UNT Digital Library
High-Pressure Gamma Loop for Brookhaven National Laboratory (open access)

High-Pressure Gamma Loop for Brookhaven National Laboratory

Report issued by the Brookhaven National Laboratory discussing high-pressured gamma loops. As stated in the introduction, "this latest endeavor involved three test cells, a gamma irradiation pool and supporting equipment, as well as an enlarged high-pressure gamma loop facility" (p. 1). This report includes tables, and illustrations.
Date: June 1963
Creator: Brookhaven National Laboratory
Object Type: Report
System: The UNT Digital Library
Shipboard Cobalt-60 Radiopasteurizer for Marine Products (open access)

Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
Object Type: Report
System: The UNT Digital Library
Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator (open access)

Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator

Report issued by the Brookhaven National Laboratory discussing progress of waste concentration studies. As stated in the introduction, "the present report covers all experimental hot runs up to the time the still was turned over to the Waste Control Section for intermediate handling of laboratory D waste" (p. 1). This report includes tables, illustrations, and photographs.
Date: August 15, 1951
Creator: Horrigan, R. V.; Fried, H. M.; Manowitz, B.; Kuhl, O.; Baranosky, J. A.; Bellanca, S. et al.
Object Type: Report
System: The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies (open access)

Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
Object Type: Report
System: The UNT Digital Library
Stepwise Calculation for the Determination of the Number of Transfer Units in Countercurrent Extraction Columns (open access)

Stepwise Calculation for the Determination of the Number of Transfer Units in Countercurrent Extraction Columns

Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."
Date: September 12, 1949
Creator: Burns, W. A. & Eschbach, E. A.
Object Type: Report
System: The UNT Digital Library
Special Irradiation of Temperature-Indicating Liquid: Final Report--Production Test 105-266-P (open access)

Special Irradiation of Temperature-Indicating Liquid: Final Report--Production Test 105-266-P

A report discussing an experiment conducted to determine the effect of radiation on the melting point of Tempilaq, a commercially available, temperature-indicating liquid.
Date: August 18, 1949
Creator: Carbon, M. W.
Object Type: Report
System: The UNT Digital Library
The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts (open access)

The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts

Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.
Date: January 27, 1950
Creator: Thorburn, R. C.
Object Type: Report
System: The UNT Digital Library
Potential Applications of Nuclear Energy for Process and Space Heat in the United States (open access)

Potential Applications of Nuclear Energy for Process and Space Heat in the United States

A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date: October 1958
Creator: Geiringer, Paul Ludwig & Goodfriend, Morton J.
Object Type: Report
System: The UNT Digital Library
A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal (open access)

A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Design Study of Fluid Engine Power Systems (open access)

The Design Study of Fluid Engine Power Systems

From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Object Type: Report
System: The UNT Digital Library
A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys (open access)

A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys

From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date: March 1964
Creator: Burns and Roe
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

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
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

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
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
Nuclear Metals Annual Progress Report: 1956-1957 (open access)

Nuclear Metals Annual Progress Report: 1956-1957

Annual report for the U.S. Atomic Energy Commission Research Division describing work completed by programs at Nuclear Metals, Inc.
Date: November 20, 1957
Creator: Nuclear Metals, Inc.
Object Type: Report
System: The UNT Digital Library
The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet (open access)

The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet

From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.
Date: February 14, 1958
Creator: Yans, F. M.; Donaldson, A. D. & Kaufmann, A. R.
Object Type: Report
System: The UNT Digital Library
Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant (open access)

Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant

From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
Date: July 30, 1962
Creator: Nowak, W. B. & Wessling, B. W.
Object Type: Report
System: The UNT Digital Library