超临界水冷堆燃料包壳候选材料的耐腐蚀性能

doi:10.11902/1005.4537.2013.123

中国腐蚀与防护学报

2014, Vol. 34

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

论文

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超临界水冷堆燃料包壳候选材料的耐腐蚀性能

沈朝, 张乐福, 朱发文, 鲍一晨

上海交通大学核科学与工程学院上海 200240

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

全文: PDF(1400 KB) HTML

摘要: 介绍了超临界水冷堆候选材料的相关腐蚀实验结果,并且讨论了每种候选材料在超临界水环境中的耐腐蚀性能。根据当前研究结果可知,高Cr含量的奥氏体不锈钢在超临界水中具有良好的抗腐蚀性能,因此其最有可能成为超临界水冷堆燃料包壳材料。

关键词 ：超临界水冷堆, 燃料包壳, 腐蚀, 氧化膜

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

收稿日期: 2013-06-21

ZTFLH:

TG172

基金资助:国家重点基础研究发展计划项目 (2007CB209802) 资助

通讯作者: 通讯作者：张乐福,E-mail：lfzhang@sjtu.edu.cn E-mail: lfzhang@sjtu.edu.cn

作者简介: 沈朝，男，1990年生，硕士生，研究方向为核材料腐蚀及其水化学

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引用本文:

沈朝, 张乐福, 朱发文, 鲍一晨. 超临界水冷堆燃料包壳候选材料的耐腐蚀性能[J]. 中国腐蚀与防护学报, 2014, 34(4): 301-306.
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.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2013.123 或 https://www.jcscp.org/CN/Y2014/V34/I4/301

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