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Lawrence Radiation Laboratory Physics Division Quarterly Report: November 1953 - January 1954
Factors Affecting Fluidization of Uranium Trioxide Powders
Halogen Collector Test Program
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1
Final Design Report: DR-1 Gas Loop
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Magnetic Force Welding Sintered Aluminum Powder Materials
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
High Temperature Short-Time, Uranium Carbide-Metal Reactions
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)
Fretting Corrosion in the Plutonium Recycle Test Reactor
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
High-Density Concrete for Gamma and Neutron Attenuation
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.3 Chromel-Alumel Thermocouples
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.5
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.7
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.8
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