NSUF 17-961: Nano-precipitate Response to Neutron Irradiation in Model ODS FeCrAl Alloy 125YF

The primary objective of this project is to investigate the response of nano-precipitates within an oxide dispersion strengthened (ODS) FeCrAl alloy to neutron irradiation. Although there are some studies that have investigated neutron irradiation effects on ODS FeCr alloys, there exists a lack of neutron irradiation experiments investigating the irradiation resistance of ODS FeCrAl alloys (particularly microstructural characterization). From the neutron irradiation work that does exist for ODS FeCr alloys, fundamental questions still exist about the potential dissolution of nanoclusters due to collision cascades at LWR operating temperatures which could lead to degradation in their radiation resistance over their lifetime. Thus, this work aims to provide a more complete description of the post-irradiation microstructure of these Al-containing ODS ferritic alloys to supplement current mechanical property data. Specifically, ODS FeCrAl alloys will be examined following neutron irradiation to ~1.8 dpa at ~200, 330, and 550ºC. To perform the post irradiation examination (PIE), this project requires the use of focused ion beam (FIB) sample preparation, as well as atom probe tomography (APT). APT analysis provides a way not only to quantify the size and number density of nano-precipitates, but it also allows for the visualization of the precipitate morphologies. The precipitate size, number density, and composition results obtained from these techniques will indicate the irradiation stability of nano-precipitates in the Fe-12Cr-5Al+FeO+Y2O3 (125YF) alloy, and will help explain trends seen in recent tensile results for these irradiated specimens. Understanding the post-irradiation nano-precipitate and defect behavior directly relates to the tensile behavior at temperatures representative of LWR operating temperatures. The information then has wide reaching impacts on ferrous-based alloy development for the nuclear industry, specifically with regards to the applicability of ODS FeCrAl alloys as an ATF cladding concept. This project is predicted to take no more than 6 months to complete. Fabrication of APT samples using FIB techniques is estimated to take no more than 1 month. APT data collection is expected to take less than 1 month after sample preparation. Data analysis and reporting will take approximately 4 months from the date of initial data collection.

Additional Info

Field	Value
Abstract	The primary objective of this project is to investigate the response of nano-precipitates within an oxide dispersion strengthened (ODS) FeCrAl alloy to neutron irradiation. Although there are some studies that have investigated neutron irradiation effects on ODS FeCr alloys, there exists a lack of neutron irradiation experiments investigating the irradiation resistance of ODS FeCrAl alloys (particularly microstructural characterization). From the neutron irradiation work that does exist for ODS FeCr alloys, fundamental questions still exist about the potential dissolution of nanoclusters due to collision cascades at LWR operating temperatures which could lead to degradation in their radiation resistance over their lifetime. Thus, this work aims to provide a more complete description of the post-irradiation microstructure of these Al-containing ODS ferritic alloys to supplement current mechanical property data. Specifically, ODS FeCrAl alloys will be examined following neutron irradiation to ~1.8 dpa at ~200, 330, and 550ºC. To perform the post irradiation examination (PIE), this project requires the use of focused ion beam (FIB) sample preparation, as well as atom probe tomography (APT). APT analysis provides a way not only to quantify the size and number density of nano-precipitates, but it also allows for the visualization of the precipitate morphologies. The precipitate size, number density, and composition results obtained from these techniques will indicate the irradiation stability of nano-precipitates in the Fe-12Cr-5Al+FeO+Y2O3 (125YF) alloy, and will help explain trends seen in recent tensile results for these irradiated specimens. Understanding the post-irradiation nano-precipitate and defect behavior directly relates to the tensile behavior at temperatures representative of LWR operating temperatures. The information then has wide reaching impacts on ferrous-based alloy development for the nuclear industry, specifically with regards to the applicability of ODS FeCrAl alloys as an ATF cladding concept. This project is predicted to take no more than 6 months to complete. Fabrication of APT samples using FIB techniques is estimated to take no more than 1 month. APT data collection is expected to take less than 1 month after sample preparation. Data analysis and reporting will take approximately 4 months from the date of initial data collection.
Award Announced Date	2017-04-26T10:08:47.093
Awarded Institution	None
Facility	None
Facility Tech Lead	Yaqiao Wu
Irradiation Facility	None
PI	Caleb Massey
PI Email	[email protected]
Project Type	RTE
RTE Number	961