NSUF 22-4459: Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy

Designing fuel claddings and ducts in advanced fission reactors such as the sodium fast reactor (SFR) is a challenge that may be overcome by shifting away from conventional alloy design. Alloys with one to two primary metallic constituent elements, typically show severe deterioration in material properties, such as excessive void swelling, at hundreds of displacements per atoms (dpas) of irradiation dose. Compositionally complex alloys (CCA) feature multiple primary alloying elements in solid solution and are of particular interest for understanding how matrix composition determines radiation damage behavior. Indeed, recent studies have shown that in addition to promising material properties, these alloys may resist extended defect formation under irradiation. The project focuses on the characterization of neutron irradiated CCAs in the FeCrMnNi system. Cr10Fe30Mn30Ni30 has been irradiated to 2 and 6 dpas at 300 and 500 ˚C at the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). These irradiation conditions (dpa and temperature) are directly comparable to the in-study in the IVEM-Tandem facility. The 2 dpa irradiation capsule has been disassembled; the samples are available for nanoscale characterizations. TEM lamellae and atom probe tomography (APT) needles will be extracted by focused-ion beam. Potential void swelling and dislocation loop densities measurements will be performed using S/TEM micrographs, and Super-X energy dispersive X-ray spectroscopy (EDS) chemical maps and line-scans will be used along with APT to assess chemical segregation and short-range ordering induced by irradiation. This will represent the first characterization of neutron irradiation response of CCAs at reactor relevant temperatures.

Informație Adițională

Cîmp Valoare
Awarded Institution University of Wisconsin
Embargo End Date 2026-02-27
Facility Tech Lead Alina Montrose
NSUF Call FY 2022 RTE 1st Call
PI Adrien Couet
PIE Facilities Irradiated Materials Characterization Laboratory
Project Member Dr. Lingfeng He, Associate Professor - North Carolina State University (https://orcid.org/0000-0003-2763-1462)
Project Member Professor Haiming Wen, Associate Professor - Missouri University of Science and Technology (https://orcid.org/0000-0003-2918-3966)
Project Member Professor Adrien Couet, Assistant Professor - University of Wisconsin (https://orcid.org/0000-0002-7330-5150)
Project Member Dr. Mukesh Bachhav, Staff Scientist - Idaho National Laboratory (https://orcid.org/0000-0001-8104-6032)
Project Member Dr. Calvin Parkin, Postdoctoral Appointee - Sandia National Laboratories (https://orcid.org/0000-0002-4300-3952)
Project Notes Awarded on 06/14/2022
Project Type RTE
Publication Local chemical ordering of a neutron-irradiated CrFeMnNi compositionally complex alloy Nathan Curtis, Sohail Shah, Mukesh Bachhav, Kaustubh Bawane, Fei Teng, Calvin Parkin, Tiankai Yao, Haiming Wen, Adrien Couet Acta Materialia 286 2025-03-01 https://doi.org/10.1016/j.actamat.2025.120752
Publication Advanced Studies of Radiation Damage in Compositionally Complex Alloys Haiming Wen, Dane Morgan, Adrien Couet, Nathan Curtis, Michael Moorehead, Mukesh Bachhav, Sohail Shah, Junliang Liu, Daniel Murray, Bao-Phong Nguyen, Dan Thoma ” The Minerals, Metals, & Materials Society Conference 2024-03-03 - 2024-03-07
Publication Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy Nathan Curtis, Calvin Parkin, Tiankai Yao, Mukesh Bachhav, Haiming Wen, Adrien Couet Nuclear Science User Facilities’ Science Review Board Meeting 2023-08-01 - 2023-08-01
Publication Neutron Irradiation Induced Local Chemical Ordering in CrFeMnNi and CrFeMnNiTiAl Compositionally Complex Alloys Nathan Curtis, Sohail Shah, Kaustubh Bawane, Fei Teng, Tiankai Yao, Mukesh Bachhav, Haiming Wen, Adrien Couet The Minerals, Metals, & Materials Society Conference 2025-03-23 - 2025-03-27
RTE Number 4459