Numerical Modeling for Coextraction of Tc(VII)with U(VI)by n-Octyl(phenyl)-N, N-diisobutylcarbamonylmethylphosphine Oxide from Nitric Acid Solution
スポンサーリンク
概要
- 論文の詳細を見る
- 1995-05-25
著者
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TACHIMORI Shoichi
Department of Materials Science,Japan Atomic Energy Research Institute
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Takagi Shunji
Mitsubishi Research Institute Inc.
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Sanami T
Department Of Quantum Science And Energy Engineering Tohoku University
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Tanaka S
Takasaki Research Establishment Japan Atomic Energy Research Institute
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Takeuchi Masayuki
Tokai Works Japan Nuclear Cycle Development Institute
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Tachimori Shoichi
Department Of Fuel Cycle Safety Research Japan Atomic Energy Research Institute
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Tanaka S
The University Of Tokyo Graduate School Of Engineering Department Of Quantum Engineering And Systems
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Yamawaki Michio
Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo
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Takeuchi M
Tokai Works Japan Nuclear Cycle Development Institute
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TAKEUCHI Mitsuo
Nuclear Engineering Research Laboratory, The University of Tokyo
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TANAKA Satoru
Nuclear Engineering Research Laboratory, The University of Tokyo
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Yamawaki Michio
Nuclear Engineering Research Laboratory Faculty Of Engineering University Of Tokyo
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Yamawaki Michio
Nuclear Engineering Research Laboratory The University Of Tokyo
関連論文
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- Measurements of(n, xp), (n, xd)Double Differential Cross Sections of Carbon and Aluminum for 65 and 75 MeV Neutrons
- Calculations of Effective Dose and Ambient Dose Equivalent Conversion Coefficients for High Energy Photons
- External Radiation Conversion Coefficients using Radiation Weighting Factor and Quality Factor for Neutron and Proton from 20 MeV to 10 GeV
- Measurements of Activation Cross Sections on Spallation Reactions for ^Co and ^Cu at Incident Neutron Energies of 40 to 120 MeV
- Measurements and Calculations of Neutron Energy Spectra Behind Polyethylene Shields Bombarded by 40- and 65-MeV Quasi-Monoenergetic Neutron Sources
- Separation of Americium(III) from Lanthanide by Encapsulating Hexadentate-ligand
- Measurement of Prompt Fission Neutron Spectrum of Neptunium-237 for 0. 62 MeV Incident Neutrons
- Measurements of Double-Differential Neutron Emission Cross Sections of ^6Li, ^7Li and ^9Be for 11. 5 MeV and 18. 0 MeV Neutrons
- Studies on hydrogen absorption-desorption proterties of U-Th-Zr alloys for developing new reactor fuel materials
- Development of New Reactor Fuel Materials Hydrogen Absorption Properties of U-Th, U-Th-Zr and U-Th-Ti-Zr Alloys
- New Ternary Hydride Formation in U-Ti-H System
- Silicate Anion Structural Change in Calcium Silicate Hydrate Gel on Dissolution of Hydrated Cement
- SORPTION OF ALKALINE METAL IONS ONTO C-S-H : CALCIUM SILICATE HYDRATED PHASES
- Dissolution Phenomena of CaO-SiO_2-H_2O Gel at Ca/Si>1 Coexisting with Ettringite System
- Measurement of Fast Neutron-Induced Fission Cross Section Ratio of Neptunium-237 relative to Uranium-235 between 6 and 120 keV
- Measurement and Analysis of Fission Rate Distributions of ^Np and ^U in a Polyethylene System with a 65 MeV Neutron Source
- Adhesive Property of Radionuclides on Material Surface in High Level Radioactive Liquid Waste
- Corrosion Behavior of Stainless Steel in Nitric Acid Solution under Gamma-ray Irradiation
- Gamma-ray Irradiation Effects on Corrosion Rates of Stainless Steel in Boiling Nitric Acid Containing Ionic Additives
- Numerical Modeling for Coextraction of Tc(VII)with U(VI)by n-Octyl(phenyl)-N, N-diisobutylcarbamonylmethylphosphine Oxide from Nitric Acid Solution
- Effect of the Hydrophobic Anion of Picrate on the Extraction of Europium(III) with Diamide
- High Resolution Measurements of Double Differential (n, α)Cross Sections of ^Ni and ^Ni between 4. 2 and 6. 5 MeV Neutrons
- Experimental Verification and Analysis of Neutron Streaming Effect through Void Holes for Control Rod Insertion in HTTR
- Density Equation of Aqueous Solution Containing Plutonium (IV), Uranium (VI) and Nitric Acid
- Hydration of N,N-Bis(2-ethylhexyl)hexanamide in Dodecane
- Distribution Study of the Hydration of Nitric Acid in Dodecane
- Thermodynamic Study of a U-Fe Alloy by Means of Knudsen Effusion Mass Spectrometry (高温マススペクトロメトリ-)
- Physical and Chemical Aspects of Hydrogen Transport in Fusion Reactor Materials
- Outgassing of Hydrogen from Metal Wall
- Complex Formation between Tributyl Phosphate and Nitric Acid and the Hydration of the Complexes in Dodecane
- Effect of Endgrain Attack on Corrosion of 18Cr-10Ni Austenitic Stainless Steel in Simulated Dissolver Liquor
- Calculation of HNO_2 Concentration from Redox Potential in HNO_3-H_2O System as an Aid to Understanding the Cathodic Reaction of Nitric Acid Corrosion
- Density equations of UO2(NO3)2-HNO3 and UO2(NO3)2-Gd(NO3)3-HNO3 solutions.
- Fast Transport of Colloidal Particles through Quartz-Packed Columns.