Fundamental Processes of Damage Formation in Neutron-Irradiated Metals
スポンサーリンク
概要
- 論文の詳細を見る
In order to study the elementary damaging processes of neutron-irradiated metals, damage parameters such as the PKA energy spectrum, the integrated damage energy due to PKAs below an energy E_<PKA> and the gas atom production were calculated for various neutron energy spectra. The present status of computer simulations of the formation of displacement damage cascades is summarized. We carried out the cryotransfer electron microscope observation of neutron-irradiated specimens to examine the structure of displacement damage cascades after the cooling phase of their formation. It is clarified that damage formation processes in neutron-irradiated metals are dynamical and indispensable to understand fully the damage structure evolution on high temperature irradiation.
- 東北大学の論文
- 1991-03-05
著者
-
SHIMOMURA Yoshiharu
Applied Physics and Chemistry,Faculty of Engineering,Hiroshima University
-
Shimomura Yoshiharu
Applied Physics And Chemistry Faculty Of Engineering Hiroshima University
-
Fukushima H
Applied Physics And Chemistry Faculty Of Engineering Hiroshima University
-
Fukushima Hiroshi
Applied Physics and Chemistry, Faculty of Engineering, Hiroshima University
-
Nishiguchi Rieko
Applied Physics and Chemistry, Faculty of Engineering, Hiroshima University
-
Nishiguchi R
Hiroshima Jogakuin Univ. Hiroshima Jpn
-
Fukushima Hiroshi
Applied Material Physics Mechnical System Engineering Hiroshima University
関連論文
- Characterization of Graphites by Positron Lifetimes
- Computer Simulation of Displacement Damage Cascade Formation near Sigma 5 Twist Boundary in Silver
- Fundamental Processes of Damage Formation in Neutron-Irradiated Metals
- The Effects of Gas Atoms on the Formation of Voids in Neutron-irradiated Metals
- Full-Potential KKR Calculations for Point Defect Energies in Metals, based on the Generalized-Gradient Approximation: I. Vacancy Formation Energies in fcc and bcc Metals
- Effects of Low-Temperature Neutron Irradiation on T_c of LnBa_2Cu_3O_ (Ln=Y, La) and La_2CuO_4
- Types of Damages in Fission-Neutron Irradiated Cu and Cu Dilute Alloys at 200℃
- The Effects of Repeated Electron Irradiation for the Formation of Interstitial Loops in Pure Aluminum
- Molecular Dynamics Simulations of the Behavior of Small Interstitial Clusters in Copper
- Formation of Voids in Pure Aluminum Quenched in Hydrogen Gas
- Dependence of the Growth Rate of Interstitial Loops on Irradiated Crystallographic Directions in Electron Irradiated Pure Aluminum
- Point Defect Clusters at a Twin Boundary in Pure Aluminum
- On the Important Effect of Water Vapor in the Atmosphere on Void Formation in Quenched Pure Aluminum