Oxidation kinetics of austenitic stainless steels as SCWR fuel cladding candidate materials in supercritical water

Hiroshi Abe, Ryuichi Suzuki, Yutaka Watanabe

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

Abstract

The oxidation kinetics of supercritical-water-cooled reactor (SCWR) fuel cladding candidate materials, e.g. 15Cr-20Ni stainless steel (1520 SS) in supercritical water at 650 and 700, °C under 24, MPa has been investigated. Characteristics of oxide layers and its relation to oxidation behaviors are also studied. The applicability of the candidate materials for the fuel cladding of SCWR from oxidation kinetics, spalling susceptibility of oxide layer, and breakdown of Cr2O3 layer points of view has been discussed. The results indicate that the threshold condition for spalling of oxide layer is different at 650 and 700, °C. The decrease in oxidation kinetics of 1520 SS with time correspond to the change in rate-limiting process of oxidation from mass transfer through an Fe oxides to mass transfer through a Cr rich oxide layer with time. Based on the oxidation kinetics obtained in this study, 1520 SS is considered suitable for a fuel cladding of SCWR in combination with appropriate CW process. However, detailed evaluation and countermeasures for the degradation due to nodular oxidation are needed before application of tube-shaped 1520 SS in supercritical water at 700, °C. On the other hand, it is estimated that the use of that at 650, °C is acceptable because the weight gain after long-term exposure was considered to be much less than the threshold condition of the spalling.

Original languageEnglish
Title of host publicationProceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
EditorsDenise Paraventi, Michael Wright, John H. Jackson
PublisherSpringer International Publishing
Pages1181-1194
Number of pages14
ISBN (Print)9783319672434
DOIs
Publication statusPublished - 2018 Jan 1
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States
Duration: 2017 Aug 132017 Aug 17

Publication series

NameMinerals, Metals and Materials Series
VolumePart F9
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Other

Other18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
CountryUnited States
CityPortland
Period17/8/1317/8/17

Keywords

  • Austenitic stainless steel
  • Cold working
  • Fuel cladding material
  • Oxidation kinetics
  • Super critical water reactor

ASJC Scopus subject areas

  • Electronic, Optical and Magnetic Materials
  • Energy Engineering and Power Technology
  • Mechanics of Materials
  • Metals and Alloys
  • Materials Chemistry

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  • Cite this

    Abe, H., Suzuki, R., & Watanabe, Y. (2018). Oxidation kinetics of austenitic stainless steels as SCWR fuel cladding candidate materials in supercritical water. In D. Paraventi, M. Wright, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 1181-1194). (Minerals, Metals and Materials Series; Vol. Part F9). Springer International Publishing. https://doi.org/10.1007/978-3-319-67244-1_75