"Ion irradiation and examination of Additive friction stir deposited 316 stainless steel"
Priyanka Agrawal, Ching-Heng Shiau, Aishani Sharma, Zhihan Hu, Megha Dubey, Yu Lu, Lin Shao, Ramprashad Prabhakaran, Yaqiao Wu, Rajiv Mishra,
Materials & Design
Vol. 238
2024
112730
Link
This study explored solid-state additive friction stir deposition (AFSD) as a modular manufacturing technology, with the aim of enabling a more rapid and streamlined on-site fabrication process for large meter-scale nuclear structural components with fully dense parts. Austenitic 316 stainless steel (SS) is an excellent candidate to demonstrate AFSD, as it is a commonly-used structural material for nuclear applications. The microstructural evolution and concomitant changes in mechanical properties after 5 MeV Fe++ ion irradiation were studied comprehensively via transmission electron microscopy and nanoindentation. AFSD-processed 316 SS led to a fine-grained and ultrafine-grained microstructure that resulted in a simultaneous increase in strength, ductility, toughness, irradiation resistance, and corrosion resistance. The AFSD samples did not exhibit voids even at 100 dpa dose at 600 °C. The enhanced radiation tolerance as compared to conventional SS was reasoned to be due to the high density of grain boundaries that act as irradiation-induced defect sinks. |
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"Materials qualification through the Nuclear Science User Facilities (NSUF): A case study on irradiated PM-HIP structural alloys" Janelle Wharry, Donna Guillen, Caleb Clement, Saquib Bin Habib, Wen Jiang, Yu Lu, Yaqiao Wu, Ching-Heng Shiau, David Frazer, Brenden Heidrich, Collin Knight, David Gandy, Frontiers in Nuclear Engineering Vol. 2 2023 1306529 Link | ||
"Microstructural changes of proton irradiated Hastelloy-N and in situ micropillar compression testing of one single grain at different local damage levels" Miguel Pena, Andres Morell-Pacheco, Ching-Heng Shiau, Boopathy Kombaiah, Lingfeng He, Laura Hawkins, Adam Gabriel, Frank Garner, Lin Shao, JNM Vol. 2022 Link | ||
"Orientation-selected micro-pillar compression of additively manufactured 316L stainless steels: Comparison of as-manufactured, annealed, and proton-irradiated variants" Ching-Heng Shiau, Cheng Sun, Michael McMurtrey, Frank Garner, Lin Shao, JNM Vol. 566 2022 Link |
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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