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Union Carbide Corporation Reports
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Health and Safety Laboratory Environmental Quarterly Report: June 1, 1977 - September 1, 1977
Health and Safety Laboratory Environmental Quarterly Report: October 1, 1977, Appendix
In-Pile Test of Prototype ML-1 Fuel Elements
Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units
Corn Pone: A Multigroup, Multiregion Reactor Code
Calculation of Suspension Peptization
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
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
Health Physics Division Annual Progress Report, January 31, 1955
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
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
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