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

DE2002762168

Publication Date	2002
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) in 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. Damage to Alloy 600 steam generator tubes by IGA/SCC continues despite rigorous water chemistry controls during power operation. The continued degradation has resulted in operational leakage, extensive tube inspections and repair. Eventually, replacement of steam generators or plant decommissioning must be considered. Many remedial actions against IGA/SCC have been taken, which include: increases in secondary water purity, reductions in oxygen ingress, use of buffers such as boric acid, injecting of hydrazine to maintain reducing conditions, and control of molar ratios of cations and anions.
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
Title Note	Technical progress rept.
NTIS Issue Number	200220
Contract Number	DE-FG03-99SF21921

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

Investigation of the Mechanism of IGA/SCC of Alloy 600 in Corrosion Accelerating Heated Crevice Environments. Nuclear Energy Research Initiative (NERI) Program.
DE2002762168

Publication Date	2002
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) in 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. Damage to Alloy 600 steam generator tubes by IGA/SCC continues despite rigorous water chemistry controls during power operation. The continued degradation has resulted in operational leakage, extensive tube inspections and repair. Eventually, replacement of steam generators or plant decommissioning must be considered. Many remedial actions against IGA/SCC have been taken, which include: increases in secondary water purity, reductions in oxygen ingress, use of buffers such as boric acid, injecting of hydrazine to maintain reducing conditions, and control of molar ratios of cations and anions.
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
Title Note	Technical progress rept.
NTIS Issue Number	200220
Contract Number	DE-FG03-99SF21921