Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963 (open access)

Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.
Date: December 30, 1963
Creator: unknown
System: The UNT Digital Library
Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964 (open access)

Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.
Date: April 27, 1965
Creator: unknown
System: The UNT Digital Library
Construction Completion Report: CAI-816, 100-N Reactor Plant (open access)

Construction Completion Report: CAI-816, 100-N Reactor Plant

Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
System: The UNT Digital Library
Pyrophoricity of Uranium in Reactor Environments (open access)

Pyrophoricity of Uranium in Reactor Environments

Report discussing information relative to the pyrophoricity of uranium for the purpose of reactor core fire safety. The report includes physical and chemical properties of uranium.
Date: January 22, 1960
Creator: Zima, G. E.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis

Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.
Date: March 1962
Creator: Wittenbrock, N. G.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Date: May 1963
Creator: Hanthorn, H. E.
System: The UNT Digital Library
Ultrasonic Resin Level Detector (open access)

Ultrasonic Resin Level Detector

This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
System: The UNT Digital Library
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1 (open access)

Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
System: The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility (open access)

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date: June 1961
Creator: Muraoka, J.
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1 (open access)

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date: February 1961
Creator: Pessl, H. J.
System: The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
System: The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor (open access)

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date: June 1961
Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System: The UNT Digital Library
Final Design Report: DR-1 Gas Loop (open access)

Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G (open access)

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date: March 1961
Creator: Freshley, M. D.
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
System: The UNT Digital Library
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements (open access)

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Date: April 1961
Creator: Koler, R. K.
System: The UNT Digital Library
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy (open access)

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date: June 1961
Creator: Todd, R. H.
System: The UNT Digital Library
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964 (open access)

Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964

Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date: April 15, 1965
Creator: Platt, A. M.
System: The UNT Digital Library
Conversion of UNH to UO3 : Terminal Report (open access)

Conversion of UNH to UO3 : Terminal Report

Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
Date: January 10, 1951
Creator: Maness, R. F. & Clagett, F.
System: The UNT Digital Library
Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices (open access)

Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."
Date: April 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
System: The UNT Digital Library
Critical Mass Studies of Plutonium Solutions (open access)

Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System: The UNT Digital Library