| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
IASCC Initiation Testing of ex-PWR Baffle-former Bolts |
| Author(s) |
Mike Ickes, Lijin Dong, Gary Was |
| On-Site Speaker (Planned) |
Mike Ickes |
| Abstract Scope |
Irradiation-assisted stress corrosion cracking (IASCC) is an issue that has caused degradation of pressurized water reactors (PWRs), and is managed by costly inspection and replacement activities at nuclear power facilities. Type 347 stainless steel baffle-former bolts have been affected by IASCC at several US PWRS recently, however little IASCC initiation data exists on materials taken from such bolts. To address this gap in data, miniature 4-point bend specimens were extracted from the baffle-former bolts at the Westinghouse Churchill Site hot cell facility and tested in simulated PWR conditions at the University of Michigan. As the US nuclear industry is considering replacing lithium hydroxide additions with potassium hydroxide additions in the PWR coolant, equivalent specimens were tested in either potassium hydroxide or lithium hydroxide in an attempt to determine if there was any difference in IASCC initiation behavior between the two environments. |
| Proceedings Inclusion? |
Undecided |