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.
Información Adicional
Campo | Valor |
---|---|
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 |