Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I) Determination of Neptunium-237
スポンサーリンク
概要
- 論文の詳細を見る
- Atomic Energy Society of Japanの論文
- 1998-06-25
著者
-
Koyama Shin-ichi
Japan Atomic Energy Agency
-
Osaka Masahiko
Japan Atomic Energy Agency
-
Mitsugashira Toshiaki
Tohoku University
-
Mitsugashira Toshiaki
The Oarai-branch Institute For Materials Research Tohoku University
-
Mitsugashira Toshiaki
Oarai Lab. Institute For Materials Research Tohoku University
-
Mitsugashira Toshiaki
Institute For Materials Research (imr) Tohoku University
-
Mitsugashira Toshiaki
The Oarai-branch Institute For Material Research Tohoku University
-
Osaka Masahiko
Japan Nuclear Cycle Development Institute
-
Otsuka Yuko
Alpha Gamma Section O-arai Engineering Center Power Reactor And Nuclear Fuel Development Corporation
-
Koyama S
Japan Atomic Energy Agency
-
MOROZUMI Katsufumi
Japan Nuclear Cycle Development Institute
-
OSAKA Masahiko
Alpha Gamma Section, O-arai Engineering Center, Japan Nuclear Cycle Development Institute
-
KOYAMA Shin-ichi
Alpha Gamma Section, O-arai Engineering Center, Japan Nuclear Cycle Development Institute
-
MOROZUMI Katsufumi
Alpha Gamma Section, O-arai Engineering Center, Japan Nuclear Cycle Development Institute
-
KONNO Koichi
Alpha Gamma Section, O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporati
-
KAJITANI Mikio
Nuclear Fuel Cycle Development Section, Head Office, Power Reactor and Nuclear Fuel Development Corp
-
Kajitani Mikio
Nuclear Fuel Cycle Development Section Head Office Power Reactor And Nuclear Fuel Development Corpor
-
Konno K
Japan Nuclear Cycle Dev. Inst.
-
Koyama Shinichi
Japan Atomic Energy Agency
-
Koyama Shinichi
Alpha Gamma Section, O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
関連論文
- Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity — Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL —
- Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity : Irradiation Tests of Np and Np-U Samples in the Experimental Fast Reactor JOYO (JAEA) and the Advanced Test Reactor at INL
- Molecular Dynamics Study on Defect Structure of Gadolinia-Doped Thoria
- Successive Magnetic Transitions and Large Reduction of Resistivity with Ferromagnetic Ordering in UPdGe
- Fabrication Technology for MOX Fuel Containing AmO_2 by an In-cell Remote Process
- Determination of Radionuclides Induced by Fast Neutrons from the JCO Criticality Accident in Tokai-mura, Japan for Estimating Neutron Doses
- Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0. 1eV to 10keV with Lead Slowing-down Spectrometer and at 0. 0253eV with Thermal Neutron Facility
- Molecular Dynamics Studies of Americium-Containing Mixed Oxide Fuels
- Development of a Multi-functional Reprocessing Process based on Ion-exchange Method by using Tertiary Pyridine-type Resin
- Separation and Utilization of Tc and Other Rare Metal Fission Products by an Extended Aqueous Reprocessing
- Chromatographic Separation of Trivalent Actinides by Using Tertiary Pyridine Resin with Methanolic Nitric Acid Solutions
- Production of Pure ^Pu Tracer for the Assessment of Plutonium in the Environment
- Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior
- Measurement of Burnup in FBR MOX Fuel Irradiated to High Burnup
- Analysis of Irradiated ^Np in the Experimental Fast Reactor JOYO for the Evaluation of its Transmutation Behavior in a Fast Reactor
- Analysis of Curium Isotopes in Mixed Oxide Fuel Irradiated in Fast Reactor
- Analysis of Minor Actinides in Mixed Oxide Fuel Irradiated in Fast Reactor, (I) Determination of Neptunium-237
- Activation of Gold by the JCO Criticality Accident
- A Novel Concept for Americium-containing Target for Use in Fast Reactors
- Densification of Molybdenum-Cermet Fuel by Sintering with Metal Additives
- Reductive Extraction of Actinides and Lanthanides from Molten Chloride Salt into Liquid Zinc
- Activation Analysis of Uranium and Thorium Contained in High Purity Niobium Oxides
- Neutron Activation Analysis of Thorium by the Use of the Japan Materials Testing Reactor
- Estimation of Total Fission Events in the JCO Criticality Accident by Passive γ-Ray Measurement of ^La in Radioequilibrium with Precursor ^Ba
- Equilibrium Distributions of Actinides and Lanthanides in Molten Salt and Liquid Metal Binary Phase Systems
- Fundamental Study of the Sulfide Reprocessing Process for Oxide Fuel (I) Study on the Pu, MA and FP Tracer-Doped U_3O_8
- Extraction of Trivalent f-elements from Water Deficient Nitrate Melt
- A Novel Concept for Americium-containing Target for Use in Fast Reactors