Void swelling in electron irradiated high purity Fe-Cr-Ni austenitic alloys.
スポンサーリンク
概要
- 論文の詳細を見る
High-purity Fe-Cr-Ni austenitic alloys corresponding to commercial Type-316 stainless steel and Hastelloy-X were used to investigate the void swelling mechanism of the austenitic steels. The alloys were irradiated with 1 MeV electrons in a high voltage electron microscope in the temperature range of 300600°C to a total dose of about 30 dpa. Low void swelling in Ni-base alloy is attributed to both low void number density and small void size. Void embryos in Fe-base alloy are stabilized by strain field arised from Ni solute segregation around the void surface. The stabilization does not occur in Ni-base alloy, which results in extremely low void number density at high temperatures ( ?? 500°C). Higher void growth rates in Fe-base alloy than in Ni-base alloy are attributable to large climbing rate of dislocations produced during the irradiation.
- 一般社団法人 日本原子力学会の論文
著者
-
Katano Yoshio
Japan Atomic Energy Research Institute
-
SHIRAISHI Kensuke
Japan Atomic Energy Research Institute
-
Hishinuma Akimichi
Japan Atomic Energy Research Institute
関連論文
- Neutron Irradiation Effects in Al-Li and Al-Mg-Li Alloys
- Positron Lifetime Study of Neutron-Irradiated Molybdenum
- Observations of Dislocation Network in Neutron-Irradiated LiF Crystal
- Damage Structures and Mechanical Properties of High-Purity Fe-9Cr Alloys Irradiated by Neutrons
- 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.
- Effect of solute titanium on void swelling in 316 stainless steel.
- 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