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OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations
Lawrence Radiation Laboratory Chemistry Division Quarterly Report: March - May 1953
In-Pile Test of Prototype ML-1 Fuel Elements
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia
Physics Division Annual Progress Report, January 31, 1964
Procedures for Fabricating Aluminum-Base ATR Fuel Elements
Oak Ridge National Laboratory Radioisotopes Procedures Manual
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C
Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961
Liquid Metal Fuel Reactor: Research and Development Program
Welding Plutonium-Containing Fuel Elements
Molten-Salt Reactor Program Quarterly Progress Report: April 1959
Electronuclear Research Division Annual Progress Report, December 31, 1963
Irradiation Effects in the EGCR Fuel
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy
Reference Design Report LMFRE-1: June 1958, Liquid Metal Fuel Reactor Experiment
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