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Technical Report Archive and Image Library
423
TRAIL Microcard Collection
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Technical Report Archive and Image Library
423
TRAIL Microcard Collection
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Report (U.S. Atomic Energy Commission)
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Fast Flux Test Facility Studies Progress Report
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Irradiation Performance of Thoria-Urania Fuel Materials Quarterly Technical Report
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Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead
Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
X-Ray Fluorescence Tables: Program Description
Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders
Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils
Stress Corrosion Cracking in Uranium-Molybdenum Alloys
A Versatile Spectrometer Magnet Power Supply
The Design and Performance of Levitation Melting Coils
Salt Bath Heat Transfer Rates for Uranium Plate
Evaluation of Diethers as Uranium Extractants
Cubic Spline, a Curve Fitting Routine
Experimental Radiation Measurements in Conventional Structures: Part 1, Radiation Measurements in Two Two-Story and Three One-Story Typical Residential Structures Before and After Modification
Aerial Radiological Monitoring System Part 4: Equipment and Procedures Through Fiscal Year 1966
Determining the "State of Charge" of Nickel-Cadmium Batteries by Farad Capacitance Measurements
High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology
Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
Fast Flux Test Facility Studies Progress Report: April 1965
A Sequence for Predicting Waste Transport by Ground Water
Geophysical Seismic Evaluation Study at Hanford
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel
INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
PRTR second generation shim assembly
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps
The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962
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