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Technical Report Archive and Image Library
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TRAIL Microcard Collection
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Technical Report Archive and Image Library
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Report (U.S. Atomic Energy Commission)
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Nuclear Safety Program Annual Progress Report for Period Ending December 31, 1967
Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974, Appendix
Feasibility Study of a High Temperature Integral Liquid Metal Fuel Reactor for Low Cost Power
The Decomposition of Diphosphopyridinenucleotide (DPN) and Adenosinetriphosphate (ATP) by Ultraviolet Light
Preliminary Economic Report on the Application of Atomic Power to Merchant Ships
Preliminary Economic Report on the Application of Atomic Power to Merchant Ships. Part 2. Oil Tanker Ships
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Hydrology of Waste Disposal, National Reactor Testing Station, Idaho: Annual Progress Report, 1962
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements
Preliminary Investigations for an Advanced Engineering Test Reactor: Addendum
Simplified Ionization Chamber
Uranium Production - Process Designs for Leached Zone Plants Volume 3. Alumina Recovery Section
Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report, April-June, 1959
Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium
Beta-Gamma Dose Rates from U232 in U233
A Versatile Spectrometer Magnet Power Supply
The Design and Performance of Levitation Melting Coils
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