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Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency | 論文
- REIDAC : A Software Package for Retrospective Dose Assessment in Internal Contamination with Radionuclides
- Redox Equilibrium of U^/U^ in Molten NaCl-2CsCl by UV-Vis Spectrophotometry and Cyclic Voltammetry
- Influence of Nitric Acid and Nitrous Acid on Oxidation and Extraction of Neptunium with Double Scrub Flow Sheet in Simplified Solvent Extraction Process
- Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels
- Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle
- ICONE11-36431 Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle
- Experimental Study on U-Pu Cocrystallization Reprocessing Process
- Batch Crystallization of Uranyl Nitrate
- Flowsheet Study of U-Pu Co-Crystallization Reprocessing System
- Dose Evaluation Based on ^Na Activity in the Human Body at the JCO Criticality Accident in Tokai-mura
- Separation of Actinide Elements by Solvent Extraction Using Centrifugal Contactors in the NEXT Process
- Uranium Crystallization Test with Dissolver Solution of Irradiated Fuel
- Removal of Liquid and Solid Impurities from Uranyl Nitrate Hexahydrate Crystalline Particles in Crystal Purification Process
- ICRPのヒト呼吸気道モデル66における生体パラメータがエアロゾル沈着に及ぼす影響--日本人とコーカシアン人
- Utilisation of OSL from Table Salt in Retrospective Dosimetry
- Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels
- Nitric Acid Concentration Dependence of Dicesium Plutonium(IV) Nitrate Formation during Solution Growth of Uranyl Nitrate Hexahydrate