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Applied Health Physics Annual Report for 1963
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
Health Physics Division Annual Progress Report, July 31, 1969
Instrumentation and Controls Division Annual Progress Report, September 1, 1968
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968
Physics Division Semiannual Progress Report, September 10, 1955
Solid State Division Semiannual Progress Report, August 30, 1955
Physics Division Annual Progress Report, January 31, 1964
Mechanical Properties of Some Refractory Metals and their Alloys
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
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
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables
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 2.4
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.5
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.6
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.7
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.8
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.9
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.10
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