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자료유형
학술저널
저자정보
Zunqi Xiao (Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academ) Jing Liu (Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academ) Zhizhong Jiang (Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academ) Lin Luo (Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academ) Qunying Huang (Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academ)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제6호
발행연도
2022.6
수록면
1,962 - 1,971 (10page)
DOI
https://doi.org/10.1016/j.net.2021.12.020

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The liquid lead-lithium (Pbe17Li) blanket has many applications in fusion reactors due to its good tritiumbreeding performance, high heat transfer efficiency and safety. The compatibility of liquid Pbe17Li alloywith the structural material of blanket under magnetic field is one of the concerns. In this study,corrosion experiments China low activation martensitic (CLAM) steel and 316L steel were carried out in aforced convection Pbe17Li loop under 1.0 T magnetic field at 480 C for 1000 h. The corrosion results on316L steel showed the characteristic with a superficial porous layer resulted from selective leaching ofhigh-soluble alloy elements and subsequent phase transformation from austenitic matrix to ferriticphase. Then the porous layers were eroded by high-velocity jet fluid. The main corrosion mechanism ofCLAM steel was selective dissolution-base corrosion attack on the microstructure boundary regions andexclusively on high residual stress areas. CLAM steel performed a better corrosion resistance than that of316L steel. The high Ni dissolution rate and the erosion of corroded layers are the main causes for thesevere corrosion of 316L steel.

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