ODS steels R&D for application to advanced nuclear systems

来源 :第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13) | 被引量 : 0次 | 上传用户：zzg770707

【摘要】

：

【作者】

：

Akihiko Kimura Wentuo Han Hwanil Je Yoosung Ha Ryuta Kasada Kiyohiro Yabuuchi Takuya Takayama Dongsheng Chen Takanari Okuda Shigeharu Ukai Satoshi Ohtsuka Peng Dou Sanghoon Noh

【机构】

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Institute of Advanced Energy,Kyoto University,Kyoto,Japan

【出处】

：

第13届中日双边先进能源系统和聚变裂变工程材料会议(CIS-13)

【发表日期】

：

2016年3期

【关键词】

：

high performance mechanism nano-particles HR-TEM radiation tolerance

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　　Materials development is essential for realization of advanced nuclear systems.Among the several candidate structural materials of the nuclear systems,oxide dispersion strengthened(ODS)steels,which have been produced by means of mechanical alloying,are considered to be promising for advanced nuclear systems with high thermal efficiency,because the ODS steels have high-strength at elevated temperatures and good resistance to corrosion and irradiation degradation.

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ODS steels R&D for application to advanced nuclear systems

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