Corrosion Behavior of Candidate SCWR Fuel Cladding Materials

doi:10.11902/1005.4537.2013.123

Journal of Chinese Society for Corrosion and protection

2014, Vol. 34

Issue (4): 301-306 DOI: 10.11902/1005.4537.2013.123

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Corrosion Behavior of Candidate SCWR Fuel Cladding Materials

SHEN Zhao, ZHANG Lefu, ZHU Fawen, BAO Yichen

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

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Abstract Corrosion performance of candidate clad materials for fuel of supercritical water-cooled reactor (SCWR) is reviewed with emphasis on that of four typical candidate alloys. According to the results presented in this paper, it is noted that the austenitic stainless steels with high Cr content show excellent corrosion resistance. Therefore, this kind of steels should be good candidate clad material for the fuel of SCWR.

Key words: supercritical water-cooled reactor fuel cladding corrosion oxide film

Received: 21 June 2013

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Cite this article:

SHEN Zhao, ZHANG Lefu, ZHU Fawen, BAO Yichen. Corrosion Behavior of Candidate SCWR Fuel Cladding Materials. Journal of Chinese Society for Corrosion and protection, 2014, 34(4): 301-306.

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https://www.jcscp.org/EN/10.11902/1005.4537.2013.123 OR https://www.jcscp.org/EN/Y2014/V34/I4/301

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