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13 Matching Results
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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
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
High Temperature Short-Time, Uranium Carbide-Metal Reactions
Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Date:
March 1963
Creator:
Christensen, J. A.
System:
The UNT Digital Library
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
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
System:
The UNT Digital Library
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.
Date:
March 1962
Creator:
Knecht, R. L. & Pankaskie, P. J.
System:
The UNT Digital Library
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)
Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.
Date:
March 1963
Creator:
Milhollen, M. K.
System:
The UNT Digital Library
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
Magnetic Force Welding Sintered Aluminum Powder Materials
Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Date:
March 1962
Creator:
Mills, L. E.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date:
March 1963
Creator:
Scott, P. A.
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Date:
March 1961
Creator:
Sharp, R. E.
System:
The UNT Digital Library
Fretting Corrosion in the Plutonium Recycle Test Reactor
Report that summarizes out-of-reactor tests undertaken to determine operating conditions, estimate damage from and extent of fretting corrosion, and describe continuing tests planned to monitor and eliminate this corrosion.
Date:
March 1964
Creator:
Winegardner, W. K.
System:
The UNT Digital Library
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