This study conducts failure tests using a simulated specimen to investigate the effect of thermal aging on the deformation and failure behaviors of system, structure, and components (SSCs) of nuclear power plants (NPPs) made of cast austenitic stainless steels (CASSs) under excessive seismic loads. Both unaged and thermally aged CF8A CASSs were used for the experiment, and the large cyclic loads in the form of displacement-control and load-control were applied at a quasi-static displacement rate. Displacement-controlled tests were performed at room temperature (RT) and 316oC and load-controlled tests were performed at RT. The results show that the deformation behaviors of aged CF8A CASS under both types of cyclic load are almost the same as those of unaged CF8A CASS. The thermal aging slightly promotes the failure of CF8A CASS under displacement-controlled cyclic loads, but the failure of specimen still occurs under the cyclic load levels several times higher than the load of the design basis earthquake. Under load-controlled cyclic loads, thermal aging retards the failure of CF8A CASS. Consequently, the thermal aging has no apparent negative effect on the deformation and failure behaviors of CASSs under large cyclic loads, even if it considerably changes the strength, ductility, and fracture toughness of CASSs.
|Title of host publication||Design and Analysis|
|Publisher||American Society of Mechanical Engineers (ASME)|
|Publication status||Published - 2019|
|Event||ASME 2019 Pressure Vessels and Piping Conference, PVP 2019 - San Antonio, United States|
Duration: 2019 Jul 14 → 2019 Jul 19
|Name||American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP|
|Conference||ASME 2019 Pressure Vessels and Piping Conference, PVP 2019|
|Period||19/7/14 → 19/7/19|
Bibliographical noteFunding Information:
This research was supported by Nuclear Power Core Technology Development Program of the Korean Institute of Energy Technology Evaluation and Planning (KETEP), granted financial resources from the Ministry of Trade, Industry and Energy, Republic of Korea (20141520100860) and by National Research Foundation (NRF) funded by Ministry of Science and ICT (2018M2A8A4084016).
© 2019 ASME
ASJC Scopus subject areas
- Mechanical Engineering