Computational Thermodynamics for Interpreting Oxidation of Structural Materials in Supercritical Water

Conference · Sat Jan 01 04:00:00 EST 2011

OSTI ID:1023319

Tan, Lizhen ^[1]; Yang, Ying ^[1]; Allen, Todd R. ^[2]; Busby, Jeremy T ^[1]

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1. ORNL
2. University of Wisconsin, Madison

Supercritical water-cooled reactor (SCWR) is one of the advanced nuclear reactors being developed to meet the soaring energy demand. The corrosion resistance of structural materials used in SCWR becomes one of the major concerns as the operation conditions being raised up to {approx}600 C and {approx}25 MPa. Oxidation has been observed as the major corrosion behavior. To mitigate the oxidation corrosion, stabilities of metals and oxides need to be understood with respect to environmental temperature and oxygen partial pressure. Computational thermodynamics provides a practical approach to assess phase stabilities of such multi-component multi-variable systems. In this study, calculated phase stability diagrams of alloys and corresponding oxides were used to guide the interpretation of oxidation behaviors of SCW-exposed structural materials. Examples include ferritic-martensitic steel, austenitic steels and Ni-base alloy, e.g., HCM12A (Fe-12Cr), D9 (Fe-15Cr-15Ni), 800H (Fe-21Cr-32Ni), and 690 (Ni-30Cr-10Fe). Calculated results are in good overall consistence with the experimental data.

• Research Organization: Oak Ridge National Laboratory (ORNL)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1023319
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ALLOYS
AMBIENT TEMPERATURE
AUSTENITIC STEELS
BUILDING MATERIALS
CORROSION
CORROSION RESISTANCE
ENERGY DEMAND
NUCLEAR POWER
OXIDATION
OXIDES
OXYGEN
PARTIAL PRESSURE
PHASE STABILITY
REACTORS
THERMODYNAMICS
WATER COOLED REACTORS