NSUF 26-5699: In situ dual beam irradiation on additively manufactured T91 ODS steel
This project aims to elucidate irradiation-induced microstructural evolution in additively manufactured (AM) T91 oxide-dispersion-strengthened (ODS) steel using in situ dual-beam (He + Kr) ion irradiation. The primary objective is to determine how nanoscale oxide precipitates and AM induced microstructural features influence helium (He) bubble nucleation, growth, and stability, with the ultimate goal of demonstrating enhanced resistance to He-induced swelling across a range of irradiation temperatures. In situ dual-beam irradiation experiments will be conducted at the IVEM facility using simultaneous 1 MeV Kr and 12 keV He ions at temperatures between 200 °C and 600 °C and He-to-dpa ratios spanning 100–1000 ppm/dpa. Real-time transmission electron microscopy will be employed to directly observe defect evolution, bubble–interface interactions, and oxide nanoparticle stability, followed by detailed post-irradiation TEM analysis. Comparative studies between AM ODS T91 steel and non-ODS AM T91 control samples will isolate the role of oxide nanoparticles and cellular dislocation substructures in mediating radiation damage.
If successful, this work will advance the state of knowledge by providing direct experimental evidence for how tailored defect-sink architectures in AM ODS steels delay the bubble-to-void transition under fusion-relevant irradiation conditions. The project will clarify the coupled effects of temperature, He concentration, and microstructural heterogeneity on He bubble size distributions, swelling behavior, grain boundary stability, and radiation-induced segregation-areas that remain poorly understood, particularly under simultaneous dual-beam irradiation. The anticipated scientific outcome is a mechanistic framework linking oxide nanoparticle characteristics to He management efficiency, enabling informed design of radiation-tolerant ferritic-martensitic steels for advanced nuclear energy systems. These insights are expected to guide microstructural engineering strategies that mitigate swelling and embrittlement in next-generation reactor environments
Additional Info
| Field | Value |
|---|---|
| Awarded Institution | Purdue University |
| DOI | 10.46936/NSUF/60017649 |
| Embargo End Date | 2028-04-22 |
| Facility Tech Lead | Wei-Ying Chen |
| Irradiation Facilities | Intermediate Voltage Electron Microscopy (IVEM)-Tandem Facility |
| NSUF Call | FY 2026 RTE 1st Call |
| PI | Xinghang Zhang |
| PIE Facilities | Intermediate Voltage Electron Microscopy (IVEM)-Tandem Facility |
| Project Member | Professor Xinghang Zhang, Professor - Purdue University (https://orcid.org/0000-0002-8380-8667) |
| Project Member | Mr. Adil Wazeer - Purdue University (https://orcid.org/0000-0003-2120-9957) |
| Project Member | Mr. Vaibhav Singh, Graduate Student - Purdue University (https://orcid.org/0000-0002-2392-6223) |
| Project Member | Mr Yinghang Liu, Research assistant - Purdue University (https://orcid.org/0009-0008-6882-7094) |
| Project Type | RTE |