Grain Growth and Neutron Irradiation Effect in Al-Li Alloys
スポンサーリンク
概要
著者
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SHIRAISHI Kensuke
Japan Atomic Energy Research Institute
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FUKAYA Kiyoshi
Japan Atomic Energy Research Institute
関連論文
- Positron Lifetime Study of Neutron-Irradiated Molybdenum
- Electron Irradiation Damage in Aluminum in a High Voltage Electron Microscope
- Dislocation Loops Formed in Aluminum in a High Voltage Electron Microscope
- Void swelling in electron irradiated Hastelloy-X.
- Dose and temperature dependence of void swelling in electron irradiated stainless steel.
- Surface effect on void swelling behavior of stainless steel.
- Radiation damage in stainless steel electron irradiated in a high voltage electron microscope.
- Growth Mechanism of Voids in Fast Reactor Irradiated Austenitic Stainless Steel
- Grain Boundary Migration and Growth of Gas Bubbles in Neutron Irradiated Al-Li Alloys
- Grain Growth and Neutron Irradiation Effect in Al-Li Alloys
- Void swelling in electron irradiated high purity Fe-Cr-Ni austenitic alloys.
- Fatigue Behavior of Magnox AL80 and Irradiation Effect on Fatigue Properties
- Behavior of Tritium in Aluminum-Lithium Alloys
- The Effect of Grain Size on the Tensile Properties of Magnox AL80
- Metallographic Observations on Creep Deformation of Magnox AL 80