Pourbaix diagrams (potential-pH diagrams) for the ternary system of Fe-Cr-Ni at 25°C to 300°C were calculated. Extrapolation of thermochemical data to elevated temperatures was performed with the revised model of Helgeson-Kirkham-Flowers, which also allows uncharged aqueous complexes to be handled. The large stability of the bimetallic spinel oxides (trevorite [NiFe2O4], chromite [FeCr2O4], and nichromite [NiCr2O4]) is shown by their predominance areas on top of those for the single metal Pourbaix diagrams. NiFe2O4 had the largest stability area of the spinels, and it covered the entire potential range for the stability of water at intermediate pH. FeCr2O4 had a stability area located around the hydrogen line. NiCr2O4 had the smallest stability area and was the least stable of the bimetallic spinels. Results were discussed in connection with the different chemistries used in nuclear power reactors of the boiling water type.
Skip Nav Destination
Article navigation
1 November 1999
Research Article|
November 01 1999
Pourbaix Diagrams for the Ternary System of Iron-Chromium-Nickel
B. Beverskog;
B. Beverskog
fn1-1_3283945
*Studsvik Material AB, S-611 82 Nyköping,
Sweden
.
Search for other works by this author on:
I. Puigdomenech
I. Puigdomenech
**Dept. of Inorg. Chem., Royal Institute of Technology, SE-100 44 Stockholm,
Sweden
.
Search for other works by this author on:
Present address: Institute for Energy Technology, OECD Halden Reactor Project, Box 173, N-1751 Halden, Norway.
Online ISSN: 1938-159X
Print ISSN: 0010-9312
NACE International
1999
CORROSION (1999) 55 (11): 1077–1087.
Citation
B. Beverskog, I. Puigdomenech; Pourbaix Diagrams for the Ternary System of Iron-Chromium-Nickel. CORROSION 1 November 1999; 55 (11): 1077–1087. https://doi.org/10.5006/1.3283945
Download citation file:
Citing articles via
Suggested Reading
Characterization of the Oxide Film Formed on Type 316 Stainless Steel in 288°C Water in Cyclic Normal and Hydrogen Water Chemistries
CORROSION (November,1995)
Fatigue Crack Growth Behavior of Sensitized Type 304 Stainless Steel Under Boiling Water Reactor Conditions
CORROSION (November,2007)