Additional electron irradiation on neutron irradiated model alloys

2016 Fiscal Year Final Research Report

• Project/Area Number: 26630487
• Research Category: Grant-in-Aid for Challenging Exploratory Research
• Allocation Type: Multi-year Fund
• Research Field: Nuclear engineering
• Research Institution: Kyushu University
• Principal Investigator: Watanabe Hideo 九州大学, 応用力学研究所, 准教授 (90212323)
• Project Period (FY): 2014-04-01 – 2017-03-31
• Keywords: 原子炉圧力容器 / 照射脆化 / 銅クラスター

Outline of Final Research Achievements

The neutron irradiation of Fe based fission reactor materials lead to an increase in the ductile-to-brittle transition temperature (DBTT) with a decrease in the upper shelf energy. It is well known that the Cu content has a strong influence on the embrittlement phenomena; especially, the Cu-rich precipitates have been thought to be directly responsible for the embrittlement. To study the effect of dislocations loop and Cu-rich precipitates at high fluencies on radiation hardening in those steels, neutron irradiation has been conducted for Fe-0.6wt%Cu alloy. The neutron irradiation was performed in BR2 at 563K up to the dose of 5.7 x 1024 (n/m2).To know the nature of dislocation loops, additional electron irradiation was performed at room temperature. By this procedure, dislocation loops formed at 563K was identified to be interstitial type.

Free Research Field

原子力材料