Mechanical Properties of a High-Purity Fe-9Cr-2W-0.1C Model Alloy for Low-Activation Ferritic Steels for Fusion Reactors
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概要
- 論文の詳細を見る
- Japan Institute of Metalsの論文
- 2000-01-20
著者
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NAGASAKA Takuya
National Institute for Fusion Science
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Matsui Hideki
Institute For Materials Research Tohoku University
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Fukumoto Ken-ichi
Institute For Materials Research Tohoku University
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YAMAMOTO Takuya
Institute for Materials Research, Tohoku University
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YOSHIDA Hiroo
Graduate School of Engineering, Tohoku University
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Matsui Hideki
Institute For Material Research Tohoku University
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Yoshida Hiroo
Graduate School Of Engineering Tohoku University
関連論文
- Recovery of Hardness, Impact Properties and Microstructure of Neutron-Irradiated Weld Joint of a Fusion Candidate Vanadium Alloy
- Fracture Toughness of JLF-1 by Miniaturized 3-Point Bend Specimens with 3.3-7.0mm Thickness
- Void Formation in Magnesium Aluminate Spinel Heavily Irradiated with Fast Neutrons
- Hydrogen Absorption Properties of U-Th-Zr and U-Th-Ti-Zr Alloys
- Surface Segregation of Ti in a V-4Cr-4Ti Alloy and Its Influence on the Surface Reaction Rates of Hydrogen Isotopes
- Effect of Oxygen Impurities on Positronium Formation in Voids of Vanadium
- Effects of Impurities on Microstructural Evolution and Deformation Process of Ion-Irradiated V-Cr-Ti Alloys
- Mechanical Properties of a High-Purity Fe-9Cr-2W-0.1C Model Alloy for Low-Activation Ferritic Steels for Fusion Reactors
- Swelling of a V-5Fe Alloy After Irradiation in JOYO
- TENSILE PROPERTIES OF JPCA AND JFMS IRRADIATED IN JMTR BY MEANS OF MINIATURIZED SPECIMEN TESTING
- Factors Controlling Irradiation Hardening of Iron-Copper Model Alloy
- Effects of Downward Temperature Change on Microstructure in Vanadium Alloys during Irradiation
- Sintering Behavior of Metal Powders Involving Microwave-Enhanced Chemical Reaction
- Long-Term Thermal Stability of Reduced Activation Ferritic/Martensitic Steels as Structural Materials of Fusion Blanket
- Microstructure of Oxide Insulator Coating before and after Thermal Cycling Test
- Microstructure and Mechanical Properties of JLF-1 and CLAM Steels Exposed to Thermal Aging with Stress
- Corrosion Characteristics of Hydrogen Permeation Materials in Molten Salt Flinak
- Irradiation Creep Behavior of Vanadium Alloys during Neutron Irradiation in a Liquid Metal Environment
- Irradiation Effect on Tensile Property of F82H IEA and Its Joint in TITAN Project