Xiaoyuan Lou
- Name
- Dr. Xiaoyuan Lou
- Institution
- Purdue University
- Position
- Associate Professor
- h-Index
- ORCID
- 0000-0003-2211-0959
- Expertise
- Additive Manufacturing, Corrosion, High Temperature Material, Metallurgy, Oxidation, Sensors, Stress Corrosion Cracking (SCC)
| "A comparison study of void swelling in additively manufactured and cold-worked 316L stainless steels under ion irradiation" Xiaoyuan Lou, Journal of Nuclear Materials Vol. 551 2021 152946 Link | ||
| "Compositionally graded specimen made by laser additive manufacturing as a high-throughput method to study radiation damages and irradiation-assisted stress corrosion cracking" Xiaoyuan Lou, Journal of Nuclear Materials Vol. 560 2022 153493 Link | ||
| "Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel" Xiaoyuan Lou, Acta Materialia Vol. 266 2024 119650 Link | ||
| "Intragranular irradiation-assisted stress corrosion cracking (IASCC) of 316L stainless steel made by laser direct energy deposition additive manufacturing: Delta ferrite-dislocation channel interaction" Xiaoyuan Lou, Journal of Nuclear Materials Vol. 577 2023 154305 Link | ||
| "Void swelling in additively manufactured 316L stainless steel with Hafnium composition gradient under self-ion irradiation" Xiaoyuan Lou, Journal of Nuclear Materials Vol. 578 2023 154351 Link |
| "A nanomechanical approach to reveal the origins of superior intergranular cracking resistance in irradiated additively-manufactured stainless steel" Xiaoyuan Lou, TMS 2022 Annual Meeting [unknown] | |
| "Advanced Characterization of Additively Manufactured 316L Stainless Steel for Nuclear Applications" Xiaoyuan Lou, M&M 2021 [unknown] | |
| "Compositionally graded specimen as a high-throughput alloy screening method for evaluating irradiation-assisted stress corrosion cracking" Xiaoyuan Lou, 2021 Annual Meeting of International Cooperative Group on Environmentally-Assisted Cracking [unknown] | |
| "Compositionally graded specimen: a high-throughput approach for nuclear material development" Xiaoyuan Lou, TMS 2022 Annual Meeting [unknown] | |
| "Mitigating irradiated assisted stress corrosion cracking with minor refractory element modification – a high-throughput approach using compositionally-graded specimen" Xiaoyuan Lou, Materials in Nuclear Energy Systems (MiNES) 2021 [unknown] |
| DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.5 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, May 14, 2018 - Calls and Awards |
| DOE-NE Awards 19 RTE Projects - New projects total approximately $690K Thursday, February 6, 2020 - Announcement, Calls and Awards, Newsletter, News Release |
Understanding neutron irradiation-assisted stress corrosion cracking mechanisms of 316L stainless steel made by laser additive manufacturing - FY 2025 CINR, #25-34188
Investigating the out-of-plane IASCC propagation in neutron-irradiated 316L stainless steel made by laser powder bed fusion - FY 2025 RTE 2nd Call, #25-5381
The origin of exceptional IASCC resistance of the additively-manufactured stainless steel after hot isostatic pressing - FY 2020 RTE 1st Call, #20-2990
Heavy ion irradiation on SCC resistant austenitic stainless steel made by laser additive manufacturing - FY 2018 RTE 2nd Call, #18-1382
The effects of high-temperature creep on irradiation damages of 316H stainless steel made by laser additive manufacturing - FY 2023 RTE 2nd Call, #23-4685
Visualizing the root cause of dislocation channel broadening through in-situ TEM experiments - FY 2023 RTE 2nd Call, #23-4724
In-situ observation of microstructural stability under dual-beam irradiation in interface/microstructure-manipulated nickel alloys - FY 2019 RTE 3rd Call, #19-2855