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Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965
Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
An Engineering Test Program to Investigate a Loss of Coolant Accident
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 1, 1964
Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements
Solid State Division Annual Progress Report, May 31, 1964
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride
Zirconium Processing Capability of the Idaho Chemical Processing Plant
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly
Aerospace Nuclear Safety: October 1 - 4, 1963
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
Final Summary Report of the Gas-Cooled Reactor Experiment-1
Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)
EOCR Control Rod and Driver Fuel Hydraulic Tests
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