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First Results of Characterization of 9Cr-3WVTiTaN Low Activation Ferritic/Martensitic Steel 被引量:6
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作者 LI Xing-gang YAN Qing-zhi MA Rong WANG Hao-qiang GE Chang-chun 《Journal of Iron and Steel Research International》 SCIE EI CAS CSCD 2010年第5期57-62,共6页
Ferritic/martensitic steels with Cr of 9%-12% (in mass percent) are favourable candidates for fuel cladding tube and in-core components of supercritical water-cooled reactor. 9Cr-3WVTiTaN low activation ferritic/mar... Ferritic/martensitic steels with Cr of 9%-12% (in mass percent) are favourable candidates for fuel cladding tube and in-core components of supercritical water-cooled reactor. 9Cr-3WVTiTaN low activation ferritic/martensitic steel, designated as China Nuclear Steel- I (CNS- I ), was patterned after T91 steel (modified 9Cr-lMo) for the reactor. The idea of low activation material and microalloy technology was introduced into the design of the steel. The hardening, tempering and transformation behaviour of CNS- I steel was investigated. The steel has advantages in tensile properties at elevated temperature relative to zircaloy that has been widely used as cladding material for conventional light water reactors. CNS- I steel exhibits tensile properties and impact toughness comparable to T91 steel which exhibits availability in the present fission reactors and fast breeder reactor but includes undesired radioactive elements such as molybdenum and niobium. 展开更多
关键词 supercritical water-cooled reactor low activation ferritic/martensitic steel tension Charpy impact
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