Degradation modes of austenitic and ferritic-martensitic stainless steels in He-CO-CO2 and liquid sodium environments of equivalent oxygen and carbon chemical potentials

G. Gulsoy, G. S. Was, S. J. Pawel, J. T. Busby

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2 Scopus citations

Abstract

The objective of this work is to explore possible thermodynamic correlations between the degradation modes of austenitic and ferritic-martensitic alloys observed in high temperature He-CO-CO2 environments with oxygen and carbon chemical potentials equivalent to that in a liquid sodium environment containing 2-5 molppm oxygen and 0.02-0.2 molppm carbon at temperatures 500-700 °C. Two He-CO-CO2 environments (Pco/Pco2 = 1320, Pco = 1980 molppm, and Pco/Pco2 = 9, Pco = 13.5 molppm) were selected to test alloys NF616 and 316L at 700 and 850 °C. Upon exposure to He environments at 850 °C, 316L samples exhibited thick surface Cr2O3 scales and substantial internal oxidation; however at 700 °C no significant internal oxidation was observed. NF616 samples exhibited relatively thinner surface Cr2O3 scales compared to 316L samples at both temperatures. NF616 samples exposed to liquid sodium at 700 °C and He-Pco/Pco2 = 9 at 850 °C showed decarburization. No surface oxide formation was observed on the sample exposed to the Na environment. Results obtained from He exposure experiments provide insight into what may occur during long exposure times in a sodium environment.

Original languageEnglish
Pages (from-to)633-643
Number of pages11
JournalJournal of Nuclear Materials
Volume441
Issue number1-3
DOIs
StatePublished - 2013

Funding

Support for this research was provided by the Department of Energy, Office of Nuclear Energy , under Grant # DE-AC07-051D14517 . The authors would like to gratefully acknowledge the useful discussions with Dr. Anton Van der Ven of the University of Michigan Ann Arbor on the thermodynamic analysis presented in this paper and the assistance of Dr. Carl Henderson of the University of Michigan Ann Arbor with EPMA.

FundersFunder number
U.S. Department of Energy
Office of Nuclear EnergyDE-AC07-051D14517

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