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Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated Crevice Environments. Technical Progress Report Fourth Quarter. Nuclear Energy Research Initiative (NERI) Program.

DE2002765749

Publication Date	2000
Personal Author	Lumsden, J.
Page Count	14
Abstract	This program focuses on understanding mechanisms causing corrosion damage to steam generator tubes in a pressurized water reactor (PWR). The crevice formed by the tube/tube support plate (T/TSP) intersection in a PWR steam generator is a concentration site for nonvolatile impurities (referred to as hideout) from the steam generator water. The restricted mass transport in the small crevice volume prevents the species, which concentrate during the generation of steam, from quickly dispersing into the bulk water. The concentrated solutions in crevices have been a contributing cause of several forms of corrosion of steam generator tubes including intergranular attack/stress corrosion cracking (IGA/SCC), pitting, and wastage (general corrosion of the tube). The rate and type of corrosion are dependent on pH, specific anions, and the electrochemical potential (ECP). A key variable is the ECP since the type and kinetics of corrosion processes are determined by the potential.
Keywords	Stress corrosion PWR type reactors Inconel 600 Steam generators Crack propagation Intergranular corrosion Tubes Water chemistry
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Rockwell International, Thousand Oaks, CA. Science Center.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200220
Contract Number	DE-FG03-99SF1921

Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated Crevice Environments. Technical Progress Report Fourth Quarter. Nuclear Energy Research Initiative (NERI) Program.

Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated Crevice Environments. Technical Progress Report Fourth Quarter. Nuclear Energy Research Initiative (NERI) Program.
DE2002765749

Publication Date	2000
Personal Author	Lumsden, J.
Page Count	14
Abstract	This program focuses on understanding mechanisms causing corrosion damage to steam generator tubes in a pressurized water reactor (PWR). The crevice formed by the tube/tube support plate (T/TSP) intersection in a PWR steam generator is a concentration site for nonvolatile impurities (referred to as hideout) from the steam generator water. The restricted mass transport in the small crevice volume prevents the species, which concentrate during the generation of steam, from quickly dispersing into the bulk water. The concentrated solutions in crevices have been a contributing cause of several forms of corrosion of steam generator tubes including intergranular attack/stress corrosion cracking (IGA/SCC), pitting, and wastage (general corrosion of the tube). The rate and type of corrosion are dependent on pH, specific anions, and the electrochemical potential (ECP). A key variable is the ECP since the type and kinetics of corrosion processes are determined by the potential.
Keywords	Stress corrosion PWR type reactors Inconel 600 Steam generators Crack propagation Intergranular corrosion Tubes Water chemistry
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Rockwell International, Thousand Oaks, CA. Science Center.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200220
Contract Number	DE-FG03-99SF1921