Dr. Tian Liu is currently a postdoctoral research fellow working with Professor Marquis in the Department of Materials Science and Engineering at the University of Michigan. Tian’s work focuses on microstructure analysis of nuclear materials, including steels, Ni-based alloys, Zr alloys, and Zr oxides following neutron, ion, and proton irradiations. Her recent work on atom probe tomography characterization of ion and neutron irradiated Alloy 800H funded through the ATR NSUF has been published in the Journal of Nuclear Materials. Tian obtained her PhD degree from the University of Alabama in 2018. Her dissertation work on processing-microstructure relationships in cold sprayed Al-Cu alloys required extensive expertise in various electron microscopy techniques, including transmission electron microscopy, precession electron diffraction, electron backscatter diffraction, and focused ion beam sample preparation. Her work during PhD study was published in Acta Materialia, Metallurgical and Materials Transcation A, Surface and Coatings Technology, and Journal of Thermal Spray Technology.
"Atom probe tomography characterization of ion and neutron irradiated Alloy 800H"
Tian Liu, Elaina Reese, Iman Ghamarian, Emmanuelle Marquis,
Journal of Nuclear Materials
Vol. 543
2020
Link
Alloy 800H is a high temperature and creep resistant alloy, and is considered as a candidate alloy for use in Generation IV nuclear reactor systems. To clarify the alloy's behavior under irradiation, samples were subjected to single ion irradiations up to 20 dpa at 440°C, a dual ion/He irradiation to 17 dpa at 460°C, and a neutron irradiation to 17 dpa at 385°C. The irradiated microstructures were characterized using atom probe tomography to complement previously published transmission electron microscopy studies. After single ion irradiation, sparse fine Al and Ti clusters were observed after 1dpa, while high number densities of nanoscale Ni-Al-Ti clusters, Cr-Ti rich carbides, and Si-decorated dislocation loops developed after 10 and 20 dpa. The microstructure formed during single ion irradiation exhibited a strong depth dependence. No significant differences were observed between the single and dual ion irradiations. While Ni-Al-Ti clusters, Cr-Ti rich carbides, and Si-decorated dislocation loops were also observed after neutron irradiation, the neutron-irradiated microstructure differed from those found in the ion-irradiated samples. |
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"Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature"
Ce Zheng, Elaina Reese, Kevin Field, Tian Liu, Emmanuelle Marquis, Stuart Maloy, Djamel Kaoumi,
Journal of Nuclear Materials
Vol. 528
2019
Link
The ferritic/martensitic steel HT9 was irradiated in the BOR-60 reactor at 650, 690 and 730 K (377, 417 and 457 °C) to doses between ∼14.6–18.6 displacements per atom (dpa). Irradiated samples were comprehensively characterized using analytical scanning/transmission electron microscopy and atom probe tomography, with emphasis on the influence of irradiation temperature on microstructure evolution. Mn/Ni/Si-rich (G-phase) and Cr-rich (αʹ) precipitates were observed within martensitic laths and at various defect sinks at 650 and 690 K (377 and 417 °C). For both G-phase and αʹ precipitates, the number density decreased while the size increased with increasing temperature. At 730 K (457 °C), within martensitic laths, a very low density of large G-phase precipitates nucleating presumably on dislocation lines was observed. No αʹ precipitates were observed at this temperature. Both a <100> and a/2 <111> type dislocation loops were observed, with the a <100> type being the predominant type at 650 and 690 K (377 and 417 °C). On the contrary, very few dislocation loops were observed at 730 K (457 °C), and the microstructure was dominated by a/2 <111> type dislocation lines (i.e., dislocation network) at this temperature. Small cavities (diameter < 2 nm) were observed at all three temperatures, whereas large cavities (diameter > 2 nm) were observed only at 690 K (417 °C), resulting in a bimodal cavity size distribution at 690 K (417 °C) and a unimodal size distribution at 650 and 730 K (377 and 457 °C). The highest swelling (%) was observed at 690 K (417 °C), indicating that the peak of swelling happens between 650 and 730 K (377 and 457 °C). |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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