Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure

• Published in: Journal of nuclear materials Vol. 427; no. 1-3; pp. 396 - 400
• Main Authors: Cheng, Ting, Keiser, James R., Brady, Michael P., Terrani, Kurt A., Pint, Bruce A.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.08.2012; Elsevier
• Subjects: ACCIDENTS; ALLOYS; Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; FUEL RODS; Fuels; Installations for energy generation and conversion: thermal and electrical energy; MATERIALS SCIENCE; Nuclear fuels; NUCLEAR POWER PLANTS; OXIDATION; REACTION KINETICS; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; STAINLESS STEELS; STEAM; Zirconium alloy; Aluminium; Iron; High temperature; Clad; Water vapor; Pressure; Nuclear reactor; Silicon carbide; Accident; Nuclear power plant; Stainless steel; Fuel rod; Oxidation; Alumina
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2012.05.007

Under certain severe accident conditions, the fuel rods of nuclear power plants are exposed to high temperature/pressure steam environments in which the Zr alloy cladding is rapidly oxidized. As alternative claddings, the oxidation resistances of SiC-based materials and stainless steels with high Cr and/or Al additions have been examined from 800-1200 °C in high-pressure steam environments. Very low reaction kinetics were observed with alumina-forming FeCrAl alloys at 1200 °C while Fe-Cr alloys with only 15-20% Cr were rapidly attacked.