Yu Lu

Profile Information
Name
Dr Yu Lu
Institution
Boise State University
Position
Senior Research Associate
Affiliation
Center for Advanced Energy Studies
h-Index
ORCID
0000-0001-8273-2616
Expertise
APT, Microstructure Characterization, Nanoindentation, Nuclear Materials, SEM
Publications:
"Comparing structure-property evolution for PM-HIP and forged alloy 625 irradiated with neutrons to 1 dpa" Caleb Clement, Caleb Clement, Yangyang Zhao, Yu Lu, David Frazer, Donna Guillen, David Gandy, Janelle Wharry, Materials Science and Engineering: A Vol. 857 [unknown] Link
The nuclear power industry has growing interest in qualifying powder metallurgy with hot isostatic pressing (PM-HIP) to replace traditional alloy fabrication methods for reactor structural components. But there is little known about the response of PM-HIP alloys to reactor conditions. This study directly compares the response of PM-HIP to forged Ni-base Alloy 625 under neutron irradiation doses ∼0.5–1 displacements per atom (dpa) at temperatures ranging ∼321–385 °C. Post-irradiation examination involves microstructure characterization, ASTM E8 uniaxial tensile testing, and fractography. Up through 1 dpa, PM-HIP Alloy 625 appears more resistant to irradiation-induced cavity nucleation than its forged counterpart, and consequently experiences significantly less hardening. This observed difference in performance can be explained by the higher initial dislocation density of the forged material, which represents an interstitial-biased sink that leaves a vacancy supersaturation to nucleate cavities. These findings show promise for qualification of PM-HIP Alloy 625 for nuclear applications, although higher dose studies are needed to assess the steady-state irradiated microstructure.
"Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation" Janelle Wharry, Wen Jiang, Yangyang Zhao, Yu Lu, David Frazer, Donna Guillen, David Gandy, Journal of Nuclear Materials Vol. 594 2024 155018 Link
"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.
"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
Additional Publications:
"Irradiation-assisted pseudoelasticity in 316L stainless steel through dislocation loop-controlled martensitic phase transformations" Yu Lu, Soumita Mondal, Yaqiao Wu, Janelle P. Wharry, Arya Chatterjee, [2025] Materials Research Letters · DOI: 10.1080/21663831.2025.2509783
"Decoupling irradiation effects on deformation-induced martensitic transformations in commercial Ni-Cr-Fe alloys" Yu Lu, Janelle P. Wharry, Caleb Clement, [2025] Materials Science and Engineering: A · DOI: 10.1016/j.msea.2024.147563
"Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel" Laura Hawkins, Zhongxia Shang, Evan A. McDermott, Benson Kunhung Tsai, Lingfeng He, Yu Lu, Miao Song, Haiyan Wang, Xiaoyuan Lou, Jingfan Yang, [2024] Acta Materialia · DOI: 10.1016/j.actamat.2024.119650 · ISSN: 1359-6454
"Dislocation channel broadening–A new mechanism to improve irradiation-assisted stress corrosion cracking resistance of additively manufactured 316 L stainless steel" Laura Hawkins, Zhongxia Shang, Evan A. McDermott, Benson Kunhung Tsai, Lingfeng He, Yu Lu, Miao Song, Haiyan Wang, Xiaoyuan Lou, Jingfan Yang, [2024] Acta Materialia · DOI: 10.1016/j.actamat.2024.119650 · EID: 2-s2.0-85182705925 · ISSN: 1359-6454
"Comparison of PM-HIP to forged SA508 pressure vessel steel under high-dose neutron irradiation" Yangyang Zhao, Yu Lu, Yaqiao Wu, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, Wen Jiang, [2024] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2024.155018 · EID: 2-s2.0-85188086214 · ISSN: 0022-3115
"Corrigendum to “Comparing structure-property evolution for PM-HIP and forged alloy 625 irradiated with neutrons to 1dpa” [Mater. Sci. Eng. A (2022) 144058](S092150932201437X)(10.1016/j.msea.2022.144058)" Sowmya Panuganti, Patrick H. Warren, Yangyang Zhao, Yu Lu, Katelyn Wheeler, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, Caleb Clement, [2024] Materials Science and Engineering: A · DOI: 10.1016/j.msea.2024.146202 · EID: 2-s2.0-85187249144 · ISSN: 0921-5093
"Effect of laser power and deposition sequence on microstructure of GRCop42 - Inconel 625 joints fabricated using laser directed energy deposition" Zexiao Wang, Jana Howard, Yu Lu, Nick Wannenmacher, Sheng Shen, Brian K. Paul, Somayeh Pasebani, Jakub Preis, [2024] Materials and Design · DOI: 10.1016/j.matdes.2024.112944 · EID: 2-s2.0-85191329463 · ISSN: 1873-4197
"Ion irradiation and examination of Additive friction stir deposited 316 stainless steel" Ching-Heng Shiau, Aishani Sharma, Zhihan Hu, Megha Dubey, Yu Lu, Lin Shao, Ramprashad Prabhakaran, Yaqiao Wu, Rajiv S. Mishra, Priyanka Agrawal, [2024] Materials and Design · DOI: 10.1016/j.matdes.2024.112730 · EID: 2-s2.0-85184747598 · ISSN: 1873-4197
"Atomic Layer Processing of MoS2" John D. Hues, Jake Soares, Steven Letourneau, Matthew Lawson, Devika Choudhury, Anil U. Mane, Yu Lu, Yaqiao Wu, Steven M. Hues, Lan Li, Jeffrey W. Elam, Elton Graugnard, Wesley Jen, [2023] IEEE Workshop on Microelectronics and Electron Devices, WMED · DOI: 10.1109/wmed58543.2023.10097444 · EID: 2-s2.0-85156218698 · ISSN: 1947-3842
"Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys" Caleb D. Clement, Yangyang Zhao, Katelyn Baird, David Frazer, Jatuporn Burns, Yu Lu, Yaqiao Wu, Collin Knight, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, [2023] Data in Brief · DOI: 10.1016/j.dib.2023.109092 · EID: 2-s2.0-85151304212 · ISSN: 2352-3409
"Mechanism for the superior IASCC resistance in HIP AM 316L" [2023] Transactions of the American Nuclear Society · DOI: 10.13182/t128-42094 · EID: 2-s2.0-85180635519 · ISSN: 0003-018X
"Microstructural Characterization of Ion Irradiated ODS MA956 Alloy" Yaqiao Wu, Ramprashad Prabhakaran, Megha Dubey, Lin Shao, Yu Lu, [2023] Microscopy and microanalysis : the official journal of Microscopy Society of America, Microbeam Analysis Society, Microscopical Society of Canada · DOI: 10.1093/micmic/ozad067.804 · EID: 2-s2.0-85168607359 · ISSN: 1435-8115
"Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials" Mychailo B. Toloczko, Ramprashad Prabhakaran, Yuanyuan Zhu, Yu Lu, Yaqiao Wu, Donna Post Guillen, [2023] Materials · DOI: 10.3390/ma16165518 · EID: 2-s2.0-85168779246 · ISSN: 1996-1944

A thermal neutron absorber material composed of Al3Hf particles in an aluminum matrix is under development for the Advanced Test Reactor. This metal matrix composite was fabricated via hot pressing of high-purity aluminum and micrometer-size Al3Hf powders at volume fractions of 20.0, 28.4, and 36.5%. Room temperature tensile and hardness testing of unirradiated specimens revealed a linear relationship between volume fraction and strength, while the tensile data showed a strong decrease in elongation between the 20 and 36.5% volume fraction materials. Tensile tests conducted at 200 °C on unirradiated material revealed similar trends. Evaluations were then conducted on specimens irradiated at 66 to 75 °C to four dose levels ranging from approximately 1 to 4 dpa. Tensile properties exhibited the typical increase in strength and decrease in ductility with dose that are common for metallic materials irradiated at ≤0.4Tm. Hardness also increased with neutron dose. The difference in strength between the three different volume fraction materials was roughly constant as the dose increased. Nanoindentation measurements of Al3Hf particles in the 28.4 vol% material showed the expected trend of increased hardness with irradiation dose. Transmission electron microscopy revealed oxygen at the interface between the Al3Hf particles and aluminum matrix in the irradiated material. Scanning electron microscopy of the exterior surface of tensile tested specimens revealed that deformation of the material occurs via plastic deformation of the Al matrix, cracking of the Al3Hf particles, and to a lesser extent, tearing of the matrix away from the particles. The fracture surface of an irradiated 28.4 vol% specimen showed failure by brittle fracture in the particles and ductile tearing of the aluminum matrix with no loss of cohesion between the particles and matrix. The coefficient of thermal expansion decreased upon irradiation, with a maximum change of −6.3% for the annealed irradiated 36.5 vol% specimen.

"Understanding the roles of dislocation networks in additively manufactured stainless steels on void swelling" [2023] Transactions of the American Nuclear Society · DOI: 10.13182/t128-41991 · EID: 2-s2.0-85180625724 · ISSN: 0003-018X
"Comparing Structure-Property Evolution for Pm-Hip and Forged Alloy 625 Irradiated with Neutrons to 1dpa" Sowmya Panuganti, Patrick H. Warren, Yangyang Zhao, Yu Lu, Katelyn Wheeler, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, Caleb D. Clement, [2022] SSRN · DOI: 10.2139/ssrn.4184542 · EID: 2-s2.0-85179579324 · ISSN: 1556-5068
"Comparing structure-property evolution for PM-HIP and forged alloy 625 irradiated with neutrons to 1 dpa" Sowmya Panuganti, Patrick H. Warren, Yangyang Zhao, Yu Lu, Katelyn Wheeler, David Frazer, Donna P. Guillen, David W. Gandy, Janelle P. Wharry, Caleb Clement, [2022] Materials Science and Engineering: A · DOI: 10.1016/j.msea.2022.144058 · EID: 2-s2.0-85139004530 · ISSN: 0921-5093
"Nucleation and growth of molybdenum disulfide grown by thermal atomic layer deposition on metal oxides" Steven Letourneau, Matthew Lawson, Anil U. Mane, Yu Lu, Yaqiao Wu, Steven M. Hues, Lan Li, Jeffrey W. Elam, Elton Graugnard, Jake Soares, [2022] Journal of Vacuum Science and Technology A: Vacuum, Surfaces and Films · DOI: 10.1116/6.0002024 · EID: 2-s2.0-85143987049 · ISSN: 1520-8559

To enable greater control over thermal atomic layer deposition (ALD) of molybdenum disulfide (MoS2), here we report studies of the reactions of molybdenum hexafluoride (MoF6) and hydrogen sulfide (H2S) with metal oxide substrates from nucleation to few-layer films. In situ quartz crystal microbalance experiments performed at 150, 200, and 250 °C revealed temperature-dependent nucleation behavior of the MoF6 precursor, which is attributed to variations in surface hydroxyl concentration with temperature. In situ Fourier transform infrared spectroscopy coupled with ex situ x-ray photoelectron spectroscopy (XPS) indicated the presence of molybdenum oxide and molybdenum oxyfluoride species during nucleation. Density functional theory calculations additionally support the formation of these species as well as predicted metal oxide to fluoride conversion. Residual gas analysis revealed reaction by-products, and the combined experimental and computational results provided insights into proposed nucleation surface reactions. With additional ALD cycles, Fourier transform infrared spectroscopy indicated steady film growth after ∼13 cycles at 200 °C. XPS revealed that higher deposition temperatures resulted in a higher fraction of MoS2 within the films. Deposition temperature was found to play an important role in film morphology with amorphous films obtained at 200 °C and below, while layered films with vertical platelets were observed at 250 °C. These results provide an improved understanding of MoS2 nucleation, which can guide surface preparation for the deposition of few-layer films and advance MoS2 toward integration into device manufacturing.

"Evolution of δ ferrite in a CF3 cast stainless steel upon neutron irradiation to 3, 5, 10, 20, and 40 dpa" Appajosula Rao, Yiren Chen, Yong Yang, Yu Lu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152865 · EID: 2-s2.0-85101074374 · ISSN: 0022-3115
"TEM Characterization of High Dose Ion Irradiated MA956 ODS Alloy" [2021] Transactions of the American Nuclear Society · DOI: 10.13182/t125-36986 · EID: 2-s2.0-85179558401 · ISSN: 0003-018X
"In-situ TEM characterization of the tensile deformation of ion-irradiated HT-UPS steel at RT and 400 °C" Yu Lu, Zhenyu Fu, Yong Yang, Chi Xu, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151911 · EID: 2-s2.0-85075877343 · ISSN: 0022-3115
Source: ORCID/CrossRef using DOI