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

Gary Was

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gsw@umich.edu

1921 Cooley

T: (734) 763-4675

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G. Gulsoy, G. S Was, S. J Pawel, and J. T Busby (2013)

JOURNAL OF NUCLEAR MATERIALS, 441(1-3):633-643.

3rd Symposium on Nuclear Fuels and Structural Materials for Next Generation Nuclear Reactors (NFSM) held as an Embedded Topical within the American-Nuclear-Society Annual Meeting, San Diego, CA, JUN 13-17, 2010

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