Corrosion behaviour of 11Cr1Si ferritic/martensitic steel in static liquid lead–bismuth eutectic at 450–550 ℃

Qingsong Chen; Lihong Zhai; Yaxuan Chen; Hao Liu; Jijun Yang; Feifei Zhang

Nuclear Materials and Energy (Jun 2023)

Corrosion behaviour of 11Cr1Si ferritic/martensitic steel in static liquid lead–bismuth eutectic at 450–550 ℃

Qingsong Chen,
Lihong Zhai,
Yaxuan Chen,
Hao Liu,
Jijun Yang,
Feifei Zhang

Affiliations

Qingsong Chen: Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China
Lihong Zhai: China Nuclear Power Technology Research Institute, Shenzhen 518026, China
Yaxuan Chen: China Nuclear Power Technology Research Institute, Shenzhen 518026, China
Hao Liu: Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China
Jijun Yang: Key Laboratory of Radiation Physics and Technology of Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China; Corresponding authors.
Feifei Zhang: China Nuclear Power Technology Research Institute, Shenzhen 518026, China; Corresponding authors.

Journal volume & issue: Vol. 35
p. 101429

Abstract

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The corrosion behaviour of 11Cr1Si ferritic/martensitic (F/M) steel in static liquid lead–bismuth eutectic (LBE) at 450–550 °C was investigated. The results show that the oxide layer on 11Cr1Si F/M steel exposed in LBE at 450–550 °C appeared different structural characteristics. The oxide layer on 11Cr1Si F/M steel at 450 °C was composed of an outer Fe3O4 layer on the top of an inner Fe-Cr spinel layer, while the oxide layer at 500 °C and 550 °C consisted of an outer Fe3O4 layer, an inner Fe-Cr spinel layer and the irregular internal oxidation zone. Meanwhile, the thickness of the oxide layer obviously increased with increasing temperature and time. The corresponding corrosion appearances and mechanisms were also discussed.

Published in Nuclear Materials and Energy

ISSN: 2352-1791 (Online)
Publisher: Elsevier
Country of publisher: United Kingdom
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-materials-and-energy/

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