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Atomic Energy Commission Reports
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Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
Fast Flux Test Facility Studies Progress Report: April 1965
A Sequence for Predicting Waste Transport by Ground Water
Geophysical Seismic Evaluation Study at Hanford
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel
INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
PRTR second generation shim assembly
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965
Numerical Results for EGCR Moderator-Element Stress Problems
In-Pile Test of Prototype ML-1 Fuel Elements
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel
Applied Health Physics Annual Report for 1963
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
Physics Division Annual Progress Report, January 31, 1964
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor
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 2.3 Chromel-Alumel Thermocouples
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
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