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Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work
Status Report on the Disposal of Radioactive Wastes
The Effect of Fluctuations in the Widths on Neutron Reaction Cross Sections
Operating Instructions for the UNIVAC Program OCUSOL-A : a Modification of the Eyewash Program
Cross Sections for OCUSOL-A Program
Specifications for Cleanliness Requirements High Level Volatility Lab. 4507
Effect of Slurry Physical Properties on Heat Exchangers and Pump Characteristics
Observed performance of the Fuel Sample Cooler
Observed Net Heat Loss from the HRT High-Pressure System
The Disposal of Power Reactor Waste Into Deep Wells
HRT Letdown Valves
September, 1956, Measure of Radiation level of HRE Fuel System Components (After Storage for 27 Months)
Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems
The Reaction of Zirconium with Uranium Dioxide
HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10
Fuel Exposures in Heterogeneous Thorium Breeder Reactors
Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957
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
Spectrophotometric Determination of Cerium with Tiron
Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop
Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)
Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl2-UCl3 Bath
Trip to Selas Corporation of America
Fused Salt Compositions
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