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The oxidation of alloy 690 in simulated pressurized water reactor primary water.
- Source :
-
Corrosion Science . Sep2017, Vol. 126, p227-237. 11p. - Publication Year :
- 2017
-
Abstract
- The oxide film formed on alloy 690 in simulated pressurized water reactor primary water is decorated with NiFe 2 O 4 particles which remain epitaxial with matrix. The penetrative inner oxides on both surface and crack wall are composed of Cr-rich (Fe,Cr,Ni) 3 O 4 and Cr 2 O 3 which were formed by solid state reactions of substrate with inwards diffusing oxygen and have orientation relationships with the substrate. Cr 2 O 3 forms first along the widely spaced planes of substrate. Compact Cr 2 O 3 layer cannot develop as there is no long-range outward diffusion of Cr in substrate with low defect density at low temperature. [ABSTRACT FROM AUTHOR]
- Subjects :
- *OXIDATION
*ALLOYS
*SOLID state physics
*SUBSTRATES (Materials science)
*DENSITY
Subjects
Details
- Language :
- English
- ISSN :
- 0010938X
- Volume :
- 126
- Database :
- Academic Search Index
- Journal :
- Corrosion Science
- Publication Type :
- Academic Journal
- Accession number :
- 124938563
- Full Text :
- https://doi.org/10.1016/j.corsci.2017.07.004