Evaluation of weight loss of stainless steels in supercritical water

Yusaku Maruno, Junya Kaneda, Shigeki Kasahara, Norihisa Saito, Tatsuo Shikama, Hideki Matsui

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (Scopus)


The supercritical water-cooled reactor (SCWR) is one of the Generation IV nuclear systems. According to a planned design for the SCWR, the temperature of the main steam is supposed to be 560°C and the surface temperature of the fuel cladding, which has a thickness of only 0.45 mm, is supposed to reach 700°C. General corrosion is one of the most critical issues for designing the fuel cladding when taking these temperature conditions into account. Therefore, the general corrosive behavior of candidate cladding materials under the SCWR conditions needs to be evaluated. In particular, from the viewpoint of a safe-life design for the SCWR, it is necessary to evaluate the amount of weight loss, which reflects the corrosion resistance, under the SCWR conditions before selecting the most promising materials for the fuel claddings. This paper reports on the weight loss of Type304, Type316L, Type310S, 12Cr-1Mo-1WVNb, modified Type316L, and modified Type310S under 500, 550, and 600°C supercritical water conditions. After the corrosion tests were finished, the oxide film from the specimen was removed using molten lithium. The weight loss was measured as the difference in weight of the same specimen before and after the corrosion test without the oxide film. The results showed that the weight loss increased along with the test temperature. On the basis of the Arrhenius equation, a linear relationship was observed between the weight loss and the reciprocal of the temperature. Type310S and modified Type310S had a smaller weight loss than Type316L, Type304, and 12Cr-1Mo-1WVNb. In addition, the weight loss of these candidate materials at 700°C during 50000h was extrapolated by the Arrhenius equation. Meanwhile, the reduced thicknesses of Type310S and modified Type310S were estimated as 45 μm or less, which is 10% or less of the thickness of the fuel claddings. Based on the above results, Type310S and modified Type310S were the most promising alloys for the fuel cladding.

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
PublisherAtomic Energy Society of Japan
Number of pages10
ISBN (Electronic)9781617386084
Publication statusPublished - 2009
Externally publishedYes
EventInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 - Shinjuku, Tokyo, Japan
Duration: 2009 May 102009 May 14

Publication series

NameInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009


OtherInternational Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
CityShinjuku, Tokyo

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering


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