First Results of Characterization of 9Cr-3WVTiTaN Low Activation Ferritic/Martensitic Steel

钢铁研究学报(英文版), 2010, 17(5): 57-62.

^1, , ^2, , ^3, , ^4, , ^5,

1.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

2.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

3.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

4.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

5.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

基金项目: National Basic Research Program (973 Program) of China(2007CB209800)

First Results of Characterization of 9Cr-3WVTiTaN Low Activation Ferritic/Martensitic Steel

LI Xing-gang ^1, , YAN Qing-zhi ^2, , MA Rong ^3, , WANG Hao-qiang ^4, , GE Chang-chun ^5,

1.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

2.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

3.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

4.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

5.Institute of Nuclear Materials,School of Material Science and Engineering,University of Science and Technology Beijing,Beijing 100083,China

Keywords： supercritical water-cooled reactor

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.

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First Results of Characterization of 9Cr-3WVTiTaN Low Activation Ferritic/Martensitic Steel

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