TY - GEN
T1 - Investigation of pitting corrosion in sensitized modified high-nitrogen 316LN steel after neutron irradiation
AU - Merezhko, D. A.
AU - Merezhko, M. S.
AU - Gussev, M. N.
AU - Busby, J. T.
AU - Maksimkin, O. P.
AU - Short, M. P.
AU - Garner, F. A.
N1 - Publisher Copyright:
© The Minerals, Metals & Materials Society 2018.
PY - 2018
Y1 - 2018
N2 - The influence has been studied of thermo-mechanical treatment, sensitization conditions, and neutron irradiation on the pitting corrosion resistance of austenitic 316LN stainless steel variants in 10% FeCl3·6H2O at 22, °C. Variants of this steel were modified with additions of nitrogen, manganese, copper, and tungsten, as well as testing cast, cold-rolled, grain boundary engineered (GBE), and as-received variants. It was found that the 316LN steel variant with additions of 0.2% N and 2% Mn had the best pitting corrosion resistance of all studied conditions. When irradiated in a light water reactor (LWR) to a maximum fluence of 3, ×, 1017, n/cm2 (E, >, 1.1, meV, Tirr, <, 50, °C), neutron irradiation surprisingly increased the resistance of GBE steels to pitting corrosion. An anisotropy of corrosion resistance of GBE and cold rolled steels was observed.
AB - The influence has been studied of thermo-mechanical treatment, sensitization conditions, and neutron irradiation on the pitting corrosion resistance of austenitic 316LN stainless steel variants in 10% FeCl3·6H2O at 22, °C. Variants of this steel were modified with additions of nitrogen, manganese, copper, and tungsten, as well as testing cast, cold-rolled, grain boundary engineered (GBE), and as-received variants. It was found that the 316LN steel variant with additions of 0.2% N and 2% Mn had the best pitting corrosion resistance of all studied conditions. When irradiated in a light water reactor (LWR) to a maximum fluence of 3, ×, 1017, n/cm2 (E, >, 1.1, meV, Tirr, <, 50, °C), neutron irradiation surprisingly increased the resistance of GBE steels to pitting corrosion. An anisotropy of corrosion resistance of GBE and cold rolled steels was observed.
KW - Alloying
KW - Austenitic stainless steel
KW - Copper
KW - Grain boundary engineering
KW - Nitrogen
KW - Pitting corrosion
KW - Sensitization
KW - Tungsten
UR - http://www.scopus.com/inward/record.url?scp=85042467919&partnerID=8YFLogxK
U2 - 10.1007/978-3-319-67244-1_71
DO - 10.1007/978-3-319-67244-1_71
M3 - Conference contribution
AN - SCOPUS:85042467919
SN - 9783319672434
T3 - Minerals, Metals and Materials Series
SP - 1125
EP - 1140
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Paraventi, Denise
A2 - Wright, Michael
A2 - Jackson, John H.
PB - Springer International Publishing
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Y2 - 13 August 2017 through 17 August 2017
ER -