NSUF 17-1014: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel
Austenitic stainless steel NF709 has been down-selected for development as a candidate structural material for sodium-cooled fast reactors. However, the understanding on its radiation resistance is limited to a few model or simplified alloys. To better understand radiation resistance of NF709, this project is to study radiation-hardening and microstructural evolution of NF709 irradiated up to 8 dpa in the temperature range of 430-470 °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.
Viðbótarupplýsingar
Svæði | Gildi |
---|---|
Awarded Institution | Oak Ridge National Laboratory |
Embargo End Date | 2019-06-20 |
Facility Tech Lead | Mukesh Bachhav |
NSUF Call | FY 2017 RTE 3rd Call |
PI | Tianyi Chen |
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 09/20/2017 |
Project Type | RTE |
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 | 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 | 1014 |