Corrosion of zirconium-based fuel cladding alloys in supercritical water

Y. H. Jeong, J. Y. Park, H. G. Kim, J. T. Busby, E. Gartner, M. Atzmon, G. S. Was, R. J. Comstock, Y. S. Chu, M. Gomes Da Silva, A. Yilmazbayhan, Arthur Thompson Motta

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

10 Scopus citations

Abstract

Corrosion tests in supercritical water and 500°C steam were performed on Zr-based model alloys up to 132 days to evaluate the potential use of Zr alloy cladding in the supercritical water reactor (SCWR). Corrosion tests performed in dynamic and static conditions showed similar results, and the 500°C steam test also showed promise as a screen test for supercritical water as the relative corrosion behavior of the alloys appeared to be similar. The corrosion test results showed a wide variety of corrosion resistance depending on the alloy composition. While Zr sponge, crystal bar Zr and Zircaloy-4 showed accelerated corrosion behavior, some of the experimental model alloys showed appreciable corrosion resistance. Among the alloys that exhibited reasonable corrosion resistance the best were Zr-FeCr or Zr-Cr-Fe alloys, and these compared favorably with other alloys under consideration for the SCWR, such as ferriticmartensitic alloys. The results suggest that at least as far as uniform corrosion goes, Zr alloys could be considered for utilization in the supercritical water cooled reactor.

Original languageEnglish (US)
Title of host publicationProceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Pages1369-1378
Number of pages10
StatePublished - Dec 1 2005
Event12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors - Salt Lake City, UT, United States
Duration: Aug 14 2005Aug 18 2005

Other

Other12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Country/TerritoryUnited States
CitySalt Lake City, UT
Period8/14/058/18/05

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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