Material Development for Nuclear Fusion and Energy Development Using Actinoids
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概要
- 論文の詳細を見る
In our Facilities. fundamental researches on nuclear fuels and reactor materials have been performed by making use of JMTR and JOYO. Authors outline original studies among them currently performed by having myself as the core. Research fields in progress are material developments for the nuclear fusion such as ferritic steel and V alloy and energy development using Actinoids. As the material development for practical nuclear fusion, we do those of low activation V alloys, ferritic steels and Quasi-amorphous actual fusion structural materials using the laser method. As the energy development with Actinoids, studies on nuclear fusion in solids and direct power generation are in progress.Low-activation V alloyferritic steelQuasi-amorphous fusion materialin-solid nuclear fission-fusion materialdirect power generation
- 東北大学の論文
- 1994-09-16
著者
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Kayano Hideo
The Oarai Branch Institute For Materials Reseach Tohoku University
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Kayano Hideo
The Oarai Branch Institute for Materials Research, Tohoku University
関連論文
- Development of Controlled Temperature-Cycle Irradiation Technique in JMTR
- In Reactor Measurement of Electrical Conductivity of Single Crystal α-Alumina
- Vickers Microhardness Testing with Miniaturized Disk Specimens
- Development of Molybdenum Alloy with High Toughness at Low Temperatures
- Effect of Specimen Geometry on Charpy Impact Test Results for Ferritic Steel Irradiated in JMTR
- Studies on hydrogen absorption-desorption proterties of U-Th-Zr alloys for developing new reactor fuel materials
- New Ternary Hydride Formation in U-Ti-H System
- Precipitation Behavior of Irradiated Reduced-Activation Ferritic Steels
- Development of rig for fundamental study of radiation effects on fusion materials in JMTR
- Study of Radiation Induced Electrical Degradation of Alumina in a Dynamic Pumping Condition in a Fission Reactor
- Irradiation Behavior of developed radiaiton resistance optical-fibers and observed optical radiation from their SiO_2 cores under reactor irradiation
- Development of Irradiation Techniques for Material Study in JMTR
- Low Activation V-Ti-Cr-Si Type Alloys for Fusion Applications
- Microstructure, Mechanical Properties and Fracture Behavior of α Particle Irradiated Type 316 Stainless Steel
- Analysis of the Neutron Spectrum by a Simple Method
- Effects of Neutron Irradiation on Mechanical Properties of Molybdenum
- Derivation of Energy Generated by Nuclear Fission-Fusion Reaction
- Embrittlement in Neutron Irradiated Niobium
- Microstructures of High-Purity Ferritic Steels after Helium Implantation
- Under Glorious Tradition of the Institute for Materials Research
- Material Development for Nuclear Fusion and Energy Development Using Actinoids
- Effects of temperature, strain rate, and specimen orientation on localized plastic deformation of irradiated zircaloy-2.
- Effect of neutron irradiation on fracture behavior of zirconium.
- Relation between microstructure and recovery behavior in fast-neutron irradiated titanium.
- Effect of neutron irradiation on mechanical properties of niobium and Nb-Y alloy.
- Mechanical properties of neutron-irradiated niobium.
- Effect of neutron irradiation on deformation behavior of zirconium.
- Neutron irradiation effects on thermally activated process of tensile properties of titanium.