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Fluoride volatility
Separation of Fluoride Residue Arising from Fluoride Volatility Recovery of Uranium from Spent Nuclear Fuel
Properties of Selected Radioisotopes
System Studies of Fission-Fusion Hybrid Molten Salt Reactors
RFI) DE-FOA-0002533 on Cleaning up Radioisotope Enventories (CURIE)
12.2% 130,000 155M Top 1% 154 5,300
Fuel Cycle Processes Directed Self-Study Course! This Is the Third of Nine Modules Available in This Directed Self-Study Course
Estimation of Alkali Metal Mole Percent and Weight of Calcined Solids for ICPP Calcine
Actinide Separation Chemistry in Nuclear Waste Streams and Materials, December 1997
The Study of Alternate, Solid-Phase Fluorinating Agents for Use in Reactive Gas Recycle of Used Nuclear Fuel
(Msrs): Coupling Spent Fuel Processing and Actinide Burning
Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors
Nuclear Fuel Cycle Technologies for Future Low-Carbon Society 70 Nuclear Fuel Cycle Technologies for Future Low-Carbon Society
Progress in Development of Fluoride Volatility Reprocessing Technology
Off-Gas Performance and the Fission Product Mechanistic Source Term
(12) United States Patent (10) Patent No.: US 7,323,153 B2 Amamoto Et Al
Resistance of Nickel-Containing Alloys in Hydrofluoric Acid, Hydrogen Fluoride and Fluorine (Ceb-5)
Application of Advanced Head End Reprocessing Concepts to a Fluoride Volatility Flowsheet
State-Of-The-Art Report on the Progress of Nuclear Fuel Cycle Chemistry
Top View
Laboratory and Pilot-Plant Studies on the Conversion of Uranyl Nitrate Hexahydrate to Ufsby Fluidized-Bed Processes
Spent Nuclear Fuel Reprocessing Flowsheet
Fast Spectrum Molten Salt Reactor Options
Improved Fluoride Volatility Reprocessing for MOX Fuel Cycle
Innovative Separations Technologies
Fluorination of Niobium Compounds with Fluorine for Fluoride Volatility T Method ⁎ Daisuke Watanabe , Daisuke Akiyama, Nobuaki Sato
Review of Hazards Associated with Molten Salt Reactor Fuel Processing Operations
Thorium Fuel Cycle — Potential Benefits and Challenges
ORNL-3497 Contract No. W-7405-Eng-26 CHEMICAL
Recovery of Enriched Uranium from Aluminum-Clad Fuel Elements
ADVANCED NUCLEAR FUEL PROCESSING OPTIONS FINAL REPORT October 6, 1997 Author(S): Kent D. Abney Larry R. Avens P. Garyeller Edwar
Molten Fluorides As Power Reactor Fuels1
IAEA Nuclear Energy Series Status of Developments in the Back End of the Fast Reactor Fuel Cycle
1 an Experience on Dry Nuclear Fuel Reprocessing
Removal of Technetium Impurities from Uranium Hexafluoride
Gas-Phase Molybdenum-99 Separation from Uranium Dioxide by Fluoride Volatility Using Nitrogen Trifluoride