NSUF 17-728: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel
Austenitic stainless steel NF709 has been down-selected for development as a candidate structural materials for sodium-cooled fast reactors. However, the understanding on its radiation resistance is limited to a few model or simplified alloys. Our recent firsthand microstructural characterization indicated significant evolution of precipitates in NF709 after irradiation to 3 displacements per atom (dpa) at 500°C. To better understand radiation resistance of NF709, this project is to study radiation-hardening and microstructural evolution of NF709 irradiated to 6 dpa at 400, 500, and 700°C. The outcome of this study will provide key insights to understand radiation resistance of Alloy 709 that is optimized from NF709 under the Advanced Reactor Technologies (ART) program.
ข้อมูลเพิ่มเติม
ฟิลด์ | ค่า |
---|---|
Awarded Institution | Oak Ridge National Laboratory |
Embargo End Date | 2026-02-27 |
Facility Tech Lead | Kory Linton |
NSUF Call | FY 2017 RTE 1st Call |
PI | Lizhen Tan |
Project Member | Dr. Lizhen Tan, Research Staff - Oak Ridge National Laboratory (https://orcid.org/0000-0002-3418-2450) |
Project Member | Dr. Tianyi Chen, Assistant Professor - Oregon State University (https://orcid.org/0000-0003-2880-824X) |
Project Notes | Awarded on 04/24/2017 |
Project Type | RTE |
Publication | Evolution dependence of vanadium nitride nanoprecipitates on directionality of ion irradiation Bong Goo Kim, Lizhen Tan, Gary Was Journal of Nuclear Materials 495 2017-11-01 http://www.sciencedirect.com/science/article/pii/S0022311517307237#ack0010 |
Publication | Phase Stability in the Fe-Rich Fe-Cr-Ni-Zr Alloys Tianyi Chen, Lizhen Tan, ying yang Metallurgical and Materials Transactions A 48 2017-07-31 https://link.springer.com/article/10.1007/s11661-017-4253-0#Sec9 |
Publication | Microstructural evolution of neutron-irradiated T91 and NF616 to ~4.3 dpa at 469 °C Kevin Field, Bong Goo Kim, Lizhen Tan, Yong Yang, Meimei Li Journal of Nuclear Materials 493 2017-09-01 http://www.sciencedirect.com/science/article/pii/S002231151730003X |
Publication | The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9 Tianyi Chen Acta Materialia 195 2020-05-16 https://doi.org/10.1016/j.actamat.2020.05.020 |
Publication | Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709 Haixuan Xu, Lizhen Tan, Li He None None 2019-05-07 https://www.osti.gov/servlets/purl/1528716 |
RTE Number | 728 |