Microstructural and Mechanical Characterization of 316L Steel Irradiated with Energetic ions

• 作者: Chai Jianlong Cui Minghuan Guo Yawei Jin Peng Li Jinyu Shen Tielong Wang Zhiguang Wei Kongfang Zhang Tongmin Zhu Yabin
• 来源期刊: 中国科学院近代物理研究所和兰州重离子研究装置年报:英文版
• 学科: 工学
• 关键词: STEEL 316L AUSTENITIC
• 年，卷（期）: 2018,（1）
• 页码范围: 81-84
• 页数: 4页
• 分类号: TG1

摘要

The 316L type austenitic stainless steel as main structural materials,are widely used for the fission reactors for more than 30 years.Besides,316L steel has been chosen as primary structural material for future advanced nuclear facility,such as fusion reactor and Accelerator Driven Subcritical(ADS)system[1].In this work,one set of the 316L steel specimens were irradiated with H and Heions to the doses of 1.01017 and 1.01018ion
cm