Corrosion resistance of candidate cladding materials for supercritical water reactor. (May 2019)

• Record Type: Journal Article
• Authors: Guo, Xianglong; Fan, Yi; Gao, Wenhua; Tang, Rui; Chen, Kai; Shen, Zhao; Zhang, Lefu
• Is Part Of: Annals of nuclear energy. Volume 127(2019)
• Page Start: 351
• Page End: 363
• Publication Date: 2019-05
• Subjects: Supercritical water -- Corrosion -- Candidate cladding materials; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2018.12.007
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Weight gain data of candidate cladding materials for SCWR is summarized. ODS steels and AFA steels may be promising cladding material for SCWR. Corrosion mitigation techniques are also reviewed. Abstract: Due to increasing attentions to supercritical water reactor (SCWR), the corrosion response of materials in supercritical water (SCW) has attracted lots of research interests. This paper summarizes the current corrosion test results conducted in Shanghai Jiao Tong University (SJTU) and compares the data with literature data. The corrosion resistances of candidate materials (including ferritic/martensitic (F/M) steel, austenitic stainless steel, alumina-forming austenitic (AFA) stainless steel and oxide dispersion strengthened (ODS) steel) in supercritical water are discussed and analyzed. High Cr content austenitic stainless steel, proper Cr content AFA stainless steel and ODS steel are promising cladding materials for SCWR since they generally have satisfactory corrosion resistance even in 650 °C SCW.