TY - GEN
T1 - The role of lattice curvature on the SCC susceptibility of alloy 600
AU - Léonard, Fabien
AU - Di Gioacchino, Fabio
AU - Cottis, Robert A.
AU - Vaillant, Francois
AU - Da Fonseca, Joao Quinta
AU - Carrette, Florence
AU - Ilevbare, Gabriel
PY - 2011
Y1 - 2011
N2 - This study investigates the link between microstructure and stress corrosion cracking susceptibility for three heats of alloy 600 representative of plant components (forged control rod drive mechanism nozzle, rolled divider plate, and rolled divider plate stub). The experimental approach was designed to determine the effect of the manufacturing process (forged versus rolled materials) and the pre-strain (as-received versus pre-strained materials) on stress corrosion cracking of alloy 600. Results showed the carbide distribution to be the main microstructural parameter influencing SCC but a lattice curvature parameter, in synergy with the carbide distribution, has proven to give a better representation of the materials SCC susceptibilities.
AB - This study investigates the link between microstructure and stress corrosion cracking susceptibility for three heats of alloy 600 representative of plant components (forged control rod drive mechanism nozzle, rolled divider plate, and rolled divider plate stub). The experimental approach was designed to determine the effect of the manufacturing process (forged versus rolled materials) and the pre-strain (as-received versus pre-strained materials) on stress corrosion cracking of alloy 600. Results showed the carbide distribution to be the main microstructural parameter influencing SCC but a lattice curvature parameter, in synergy with the carbide distribution, has proven to give a better representation of the materials SCC susceptibilities.
KW - Alloy 600
KW - Lattice curvature
KW - Orientation gradient
KW - PWSCC
UR - https://www.scopus.com/pages/publications/84867602531
M3 - Conference contribution
AN - SCOPUS:84867602531
SN - 9781622761944
T3 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
SP - 1640
EP - 1652
BT - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
T2 - 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Y2 - 7 August 2011 through 11 August 2011
ER -