@inproceedings{1b2744ed8d2c4311bc8a680f05d35f0f,
title = "Irradiation effects in a highly irradiated cold worked stainless steel removed from a commercial PWR",
abstract = "Mechanical and corrosion properties were measured on a cold worked, Type 316 stainless steel tube removed from the core of a Pressurized Water Reactor (PWR) after 23 years of service. Neutron exposure levels of the material ranged from near 0 to 65 dpa (∼4.5×1022 n/cm2, E>1 MeV) and irradiation temperatures from 290 to 320°C. As expected, the strength of the material increased and the ductility decreased with irradiation. Slow strain rate and stressed O-ring crack initiation tests in PWR water were used to determine the susceptibility of the material to irradiation assisted stress corrosion cracking (IASCC). The data indicate that IASCC susceptibility may accelerate above 20 dpa and saturate after 60 dpa. At the highest fluence, limited intergranular failure was observed on the fracture surface of a specimen slow strain rate tested in inert gas.",
keywords = "IASCC, PWR, Stainless Steel, Swelling",
author = "Joyce Conermann and Regis Shogan and Koji Fujimoto and Toshio Yonezawa and Yoichiro Yamaguchi",
year = "2005",
month = dec,
day = "1",
language = "English",
isbn = "9780873395953",
series = "Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors",
pages = "277--287",
booktitle = "Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors",
note = "12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors ; Conference date: 14-08-2005 Through 18-08-2005",
}