| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Environmentally Assisted Cracking: Theory and Practice
|
| Presentation Title |
Cracking of Reactor Core Internal Materials in LWR Environments |
| Author(s) |
Yiren Chen |
| On-Site Speaker (Planned) |
Yiren Chen |
| Abstract Scope |
The service performance of reactor core internal components is critical for the long-term availability and stability of light water reactors (LWRs). Subject to intensive neutron irradiation and corrosive high-temperature coolant, core internal materials are vulnerable to irradiation- and environment-induced degradations during power operation. To evaluate the long-term effects of neutron irradiation on the cracking behavior of reactor core materials, crack growth rate and fracture toughness J-resistance curve tests are performed on a Type 304 stainless steel harvested from a decommissioned pressurized water reactor. These decommissioned materials provide an excellent opportunity to assess the extent of material degradation under prototypical LWR irradiation and service conditions, eliminating any uncertainties associated with laboratory irradiation experiments. The tests are performed at ~315°C in low-corrosion-potential environments. The results are compared with the current crack growth models for irradiated stainless steels and are discussed in the context of cracking mechanisms under LWR relevant conditions. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |