Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

• Published in: Journal of nuclear materials Vol. 411; no. 1; pp. 83 - 89
• Main Authors: Chiang, M.F., Young, M.C., Huang, J.Y.
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01-04-2011; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Water chemistry; Coolant; Hydrogen; Oxides; Fracture; Crack propagation; Nuclear reactor; Corrosion resistance; Boiling water reactor; Corrosion; Fatigue strength; Stainless steel; Concentration effect; Crack
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2011.01.035

Corrosion fatigue behavior of stainless steel 304L (SS304L) in a simulated BWR coolant with hydrogen injection was investigated. Hydrogen water chemistry slightly mitigated the corrosion fatigue degradation of the as-received SS304L specimens, but, on the contrary, it slightly increased the corrosion fatigue crack growth rates (CFCGRs) of the cold-worked specimens. All the CFCGR-tested specimens showed similar fracture features, except for the amounts of deposited corrosion debris. The results indicated that decreasing the oxygen concentration of water environment is not an effective measure to suppress the fatigue crack growth rate of cold-worked SS304L. The CFCGRs of the SS304L were determined by an interaction between corrosion, oxide-induced crack closure and cold work in corrosive environments. At a specific level of reduction, cold work could enhance the corrosion fatigue resistance of SS304 both in the air-saturated and HWC coolant environments.