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Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work
Experiments on the Release of Fission Products from Molten Reactor Fuels
Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores
Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work
Supplement to: Curve Plotting Routine for the Oracle (57-4-56)
A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia
Radioactive Waste Disposal and Miscellaneous Work : Annual Report for Calendar Year 1956
Section 9.0 to Status Report on the Disposal of Radioactive Wastes
Effect of Core Corrosion Sample Assembly on HRT Critical Concentration
The Volatilization of Fission Products by Melting of Reactor Fuel Plates
Nuclear Computations for HRE-3 Design : Equilibrium Results
Radiation Level in the Stator Region of the HRT Fuel Circulation Pump
Compilation of Various Undocumented Classified Memoranda on Sherwood Program
Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop
Status Report on the Disposal of Radioactive Wastes
Determination of Trace Amounts of Sulfur in Fluoride Salts
Fused Salt Compositions
Hedstrom Plot for the Calculation of Laminar Flow Pressure Drop for the Bingham Plastic Materials with Hedstrom Numbers from 0 to 10(15)
Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl2-UCl3 Bath
Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products
Trip to Selas Corporation of America
The Relationship of Aqueous ThO2 Slurry Physical Properties of the Engineering Design of a Reactor System
Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957
Spectrophotometric Determination of Cerium with Tiron
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