Ferritic Steels for Sodium-cooled Fast Reactors: Design Principles and Challenges

被引:6
作者
Raj, Baldev [1 ]
Vijayalakshmi, M. [1 ]
机构
[1] Indira Gandhi Ctr Atom Res, Kalpakkam 603102, Tamil Nadu, India
关键词
MODIFIED 9CR-1MO STEEL; HARD ZONE; ALLOYS;
D O I
10.1007/s11837-010-0143-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
An overview of the current status of development of ferritic steels for emerging last reactor technologies is presented in this paper The creep-resistant 9-12Cr ferritic/martensitic steels are classically known for steam generator applications. The excellent void swelling resistance of ferritic steels enabled the identification of their potential for core component applications of fast reactors. Since then, an extensive knowledge base has been generated by identifying the empirical correlations between chemistry of the steels, heat treatment, structure, and properties, in addition to their in behavior A few concerns have also been identified which pertain to high-temperature irradiation creep, embrittlement, Type IV cracking in creep-loaded weldments and hard zone formation in dissimilar joints. The origin of these problems and the methodologies to overcome the limitations are highlighted. Finally, the suitability of the terrific steels is re-evaluated in the emerging scenario of the fist reactor technology, with a target of achieving better breeding ratio and improved thermal efficiency.
引用
收藏
页码:75 / 83
页数:9
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