Mr. Pengyuan Xiu is a 5th year Ph.D student in Department of Nuclear Engineering and Radiological Sciences (NERS) at University of Michigan (UM) working on ion radiation effects on Additive Manufactured HT9 alloy using combined techniques of scanning / transmission electron microscopy (S/TEM) and atom probe tomography (APT). He was previously working on radiation effects on FeCrAl and nickel-based concentrated solid solution alloys using scanning / transmission electron microscopy (S/TEM). His Ph.D advisers at UM-NERS are Prof. Kevin Field and Prof. Lumin Wang. Mr. Xiu will seek positions in academia / research after his Ph.D graduation.
"Dislocation loop evolution and radiation hardening in nickel-based concentrated solid solution alloys"
Pengyuan Xiu,
Journal of Nuclear Materials
Vol. 538
2020
Link
Effects of chemical composition, ion irradiation dose and temperature on unfaulting of irradiation induced Frank dislocation loops to perfect loops in two nickel based single-phase solid solution alloys, Ni–20Fe and NiFe–20Cr, have been studied. The fraction of Frank loops decreases with irradiation dose from 7.2 to 38.4 dpa at 500, but with more Frank loops remaining in the ternary alloy. However, perfect loops and dislocation networks become the dominant features of defects at 580 in both alloys. The results indicate a thermally assisted loop unfaulting process that may be hindered by more sluggish defect motion in the alloy with more chemical components. Nano-indentation with both continuous stiffness method and single indentation method are used to measure radiation hardening. Loop unfaulting in both alloys irradiated at 580 reduced radiation hardening while significant hardening is observed after irradiation at 500. The quasi-static single indentation method exhibits lower hardness results compared to continuous stiffness method, because dislocations induced from the cyclic loading in the latter method get relaxed and stabilized, resulting in higher resistance to the indenter. |
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"Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium" Adam Gabriel, Laura Hawkins, Aaron French, Yongchang Li, Zhihan Hu, Lingfeng He, Pengyuan Xiu, Michael Nastasi, Frank Garner, Lin Shao, JNM Vol. 561 2022 Link | ||
"Microchemical evolution of irradiated additive-manufactured HT9" Pengyuan Xiu, Caleb Massey, T.M. Kelsey Green, Stephen Taller, dieter Isheim, Niyanth Sridharan, JNM Vol. 559 2022 Link | ||
"STEM Characterization of Dislocation Loops in Irradiated FCC Alloys"
Pengyuan Xiu,
Journal of Nuclear Materials
Vol. 544
2020
Link
In this study, we demonstrate the methodology systematically developed for dislocation loop (perfect and faulted loops) imaging and analysis in irradiated face-centered-cubic (FCC) alloys using scanning transmission electron microscopy (STEM). On-zone [001] STEM imaging was identified as the preferred choice for its accuracy and effectiveness based on the comparison with other dislocation loop imaging techniques including: (i) on-zone STEM imaging using other major low-index zone axes, (ii) kinematic two-beam conditions bright field imaging near the [001] zone axis in conventional TEM (CTEM) mode, and (iii) Rel-Rod CTEM dark-field (DF) imaging near the [011] zone axis. The effect of STEM collection angle on the contrast formation of dislocation loops was also investigated. The developed method was confirmed by imaging all populations of perfect and faulted loops of types a/2〈110〉{110} and a/3〈111〉{111} found in an ion irradiated Ni40Fe40Cr20 alloy. The proposed STEM-based technique can easily identify said loops with a size greater than 10 nm without any assumptions such as those commonly made using the conventional Rel-Rod CTEM-DF technique. The recommended methodology in this study is developed as a quick and convenient tool that can be generally applied to irradiated FCC-based materials due to their common crystallography. |
"Role of chemical disorder on radiation-induced defect production and damage evolution in NiFeCoCr" Gihan Velişa, Saro San, Miguel L. Crespillo, Zhe Fan, Hongbin Bei, William J. Weber, Pengyuan Xiu, Lumin Wang, Filip Tuomisto, Wai-Yim Ching, Yanwen Zhang, Yufan Zhou, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153689 | |
"Towards Optimized Characterization of Dislocation Loops in Irradiated FCC Alloys Using On-Zone STEM Techniques" Hongbin Bei, Yanwen Zhang, Lumin Wang, Kevin G Field, Pengyuan Xiu, [2022] Microscopy and Microanalysis · DOI: 10.1017/s1431927622008017 · ISSN: 1431-9276 | |
"Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures" Michael Moorehead, Mohamed Elbakhshwan, Xuan Zhang, Pengyuan Xiu, Lingfeng He, Mukesh Bachhav, Kumar Sridharan, Adrien Couet, Calvin Parkin, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153733 · ISSN: 0022-3115 | |
"Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium" Laura Hawkins, Aaron French, Yongchang Li, Zhihan Hu, Lingfeng He, Pengyuan Xiu, Michael Nastasi, Frank.A. Garner, Lin Shao, Adam Gabriel, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153519 · ISSN: 0022-3115 | |
"Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System" Miaomiao Jin, Kaustubh Bawane, Beata Tyburska-Püschel, Brian J. Jaques, Kevin G. Field, Jeffrey J. Giglio, Lingfeng He, Pengyuan Xiu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153244 · ISSN: 0022-3115 | |
"High radiation tolerance of an ultrastrong nanostructured NiCoCr alloy with stable dispersed nanooxides and fine grain structure" Mingyang Li, Pengyuan Xiu, Xing Wang, Gihan Velişa, Li Jiang, Karren L. More, Jonathan D. Poplawsky, Yongqin Chang, Yanwen Zhang, Lumin Wang, Chenyang Lu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153316 · ISSN: 0022-3115 | |
"Microchemical Evolution of Irradiated Additive-Manufactured HT9" Caleb P. Massey, T.M. Kelsy Green, Stephen Taller, Dieter Isheim, Niyanth Sridharan, Kevin G. Field, Pengyuan Xiu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153410 · ISSN: 0022-3115 | |
"Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation" Marat Khafizov, Chao Jiang, Beata Tyburska-Püschel, Brian J. Jaques, Pengyuan Xiu, Peng Xu, Mitchell K. Meyer, Kumar Sridharan, Darryl P. Butt, Jian Gan, Lingfeng He, [2021] Acta Materialia · DOI: 10.1016/j.actamat.2021.116778 | |
"STEM Characterization of Dislocation Loops in Irradiated FCC Alloys" Hongbin Bei, Yanwen Zhang, Lumin Wang, Kevin G. Field, Pengyuan Xiu, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152658 | |
"Elucidating He-H assisted cavity evolution in alpha Cr under multiple ion beam irradiation" Qing Peng, Pengyuan Xiu, Yan Yan, Zhijie Jiao, Chenyang Lu, Tong Liu, Chao Ye, Rui Shu, Yehong Liao, Qisen Ren, Fei Gao, Lumin Wang, Li Jiang, [2020] Scripta Materialia · DOI: 10.1016/j.scriptamat.2020.06.031 | |
"Irradiation‐Induced Extremes Create Hierarchical Face‐/Body‐Centered‐Cubic Phases in Nanostructured High Entropy Alloys"
Yong‐Jie Hu, Kai Sun, Pengyuan Xiu, Miao Song, Yanwen Zhang, Walker L. Boldman, Miguel L. Crespillo, Philip D. Rack, Liang Qi, William J. Weber, Lumin Wang, Li Jiang,
[2020]
Advanced Materials
· DOI: 10.1002/adma.202002652
· ISSN: 0935-9648
A nanoscale hierarchical dual‐phase structure is reported to form in a nanocrystalline NiFeCoCrCu high‐entropy‐alloy (HEA) film via ion irradiation. Under the extreme energy deposition and consequent thermal energy dissipation induced by energetic particles, a fundamentally new phenomenon is revealed, in which the original single‐phase face‐centered‐cubic (FCC) structure partially transforms into alternating nanometer layers of a body‐centered‐cubic (BCC) structure. The orientation relationship follows the Nishiyama–Wasser‐man relationship, that is, (011)BCC || ( 1¯1¯1)FCC and [100]BCC || [ 11¯0]FCC. Simulation results indicate that Cr, as a BCC stabilizing element, exhibits a tendency to segregate to the stacking faults (SFs). Furthermore, the high densities of SFs and twin boundaries in each nanocrystalline grain serve to accelerate the nucleation and growth of the BCC phase during irradiation. By adjusting the irradiation parameters, desired thicknesses of the FCC and BCC phases in the laminates can be achieved. This work demonstrates the controlled formation of an attractive dual‐phase nanolaminate structure under ion irradiation and provides a strategy for designing new derivate structures of HEAs. |
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"Irradiation-Induced Extremes Create Hierarchical Face-/Body-Centered-Cubic Phases in Nanostructured High Entropy Alloys"
Yong‐Jie Hu, Kai Sun, Pengyuan Xiu, Miao Song, Yanwen Zhang, Walker L. Boldman, Miguel L. Crespillo, Philip D. Rack, Liang Qi, William J. Weber, Lumin Wang, Li Jiang,
[2020]
Advanced Materials
· DOI: 10.1002/adma.202002652
· EID: 2-s2.0-85089577100
· ISSN: 1521-4095
A nanoscale hierarchical dual‐phase structure is reported to form in a nanocrystalline NiFeCoCrCu high‐entropy‐alloy (HEA) film via ion irradiation. Under the extreme energy deposition and consequent thermal energy dissipation induced by energetic particles, a fundamentally new phenomenon is revealed, in which the original single‐phase face‐centered‐cubic (FCC) structure partially transforms into alternating nanometer layers of a body‐centered‐cubic (BCC) structure. The orientation relationship follows the Nishiyama–Wasser‐man relationship, that is, (011)BCC || ( 1¯1¯1)FCC and [100]BCC || [ 11¯0]FCC. Simulation results indicate that Cr, as a BCC stabilizing element, exhibits a tendency to segregate to the stacking faults (SFs). Furthermore, the high densities of SFs and twin boundaries in each nanocrystalline grain serve to accelerate the nucleation and growth of the BCC phase during irradiation. By adjusting the irradiation parameters, desired thicknesses of the FCC and BCC phases in the laminates can be achieved. This work demonstrates the controlled formation of an attractive dual‐phase nanolaminate structure under ion irradiation and provides a strategy for designing new derivate structures of HEAs. |
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"Dislocation loop evolution and radiation hardening in nickel-based concentrated solid solution alloys" Yuri N. Osetsky, Li Jiang, Gihan Velisa, Yang Tong, Hongbin Bei, William J. Weber, Yanwen Zhang, Lumin Wang, Pengyuan Xiu, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152247 · ISSN: 0022-3115 | |
"The microstructure evolution in a SiCf/SiC composite under triple ion beam irradiation" Jiaxiang Xue, Tong Liu, Rui Shu, Yan Yan, Yehong Liao, Qisen Ren, Guang Ran, Kai Sun, Li Jiang, Pengyuan Xiu, Lumin Wang, Chao Ye, [2020] Ceramics International · DOI: 10.1016/j.ceramint.2019.12.266 · ISSN: 0272-8842 | |
"The microstructure evolution in a SiC |
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"Evolution of microstructure and nanohardness of SiC fiber-reinforced SiC matrix composites under Au ion irradiation" Jiaxiang Xue, Tong Liu, Rui Shu, Yan Yan, Yehong Liao, Qisen Ren, Guang Ran, Kai Sun, Li Jiang, Pengyuan Xiu, Lumin Wang, Chao Ye, [2020] Ceramics International · DOI: 10.1016/j.ceramint.2019.12.044 · ISSN: 0272-8842 | |
"Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys" Xing Wang, Yuri N. Osetsky, Yang Tong, Robert Harrison, Stephen E. Donnelly, Di Chen, Yongqiang Wang, Hongbin Bei, Brian C. Sales, Karren L. More, Pengyuan Xiu, Lumin Wang, William J. Weber, Yanwen Zhang, [2019] Acta Materialia · DOI: 10.1016/j.actamat.2019.10.013 · ISSN: 1359-6454 | |
"Effects of ion irradiation on chromium coatings of various thicknesses on a zirconium alloy" Pengyuan Xiu, Yan Yan, Chenyang Lu, Minjiang Huang, Tong Liu, Chao Ye, Haiping Sun, Rui Shu, Lumin Wang, Li Jiang, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151740 · ISSN: 0022-3115 | |
"Irradiation effects of medium-entropy alloy NiCoCr with and without pre-indentation" Tai-Ni Yang, Ke Jin, Gihan Velisa, Pengyuan Xiu, Qing Peng, Fei Gao, Yanwen Zhang, Hongbin Bei, William J. Weber, Lumin Wang, Chenyang Lu, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.06.020 · ISSN: 0022-3115 | |
"Influence of irradiation temperature on void swelling in NiCoFeCrMn and NiCoFeCrPd" Chenyang Lu, Gihan Velisa, Ke Jin, Pengyuan Xiu, Yanwen Zhang, Hongbin Bei, Lumin Wang, Tai-ni Yang, [2019] Scripta Materialia · DOI: 10.1016/j.scriptamat.2018.08.021 · ISSN: 1359-6462 | |
"Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations" Taini Yang, Ke Jin, Gihan Velisa, Pengyuan Xiu, Miao Song, Qing Peng, Fei Gao, Yanwen Zhang, Hongbin Bei, William J. Weber, Lumin Wang, Chenyang Lu, [2018] Materials Research Letters · DOI: 10.1080/21663831.2018.1504136 · ISSN: 2166-3831 | |
"Interstitial migration behavior and defect evolution in ion irradiated pure nickel and Ni-xFe binary alloys" Taini Yang, Liangliang Niu, Qing Peng, Ke Jin, Miguel L. Crespillo, Gihan Velisa, Haizhou Xue, Feifei Zhang, Pengyuan Xiu, Yanwen Zhang, Fei Gao, Hongbin Bei, William J. Weber, Lumin Wang, Chenyang Lu, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.07.006 · ISSN: 0022-3115 | |
"Effect of alloying elements on defect evolution in Ni-20X binary alloys" Chenyang Lu, Gihan Velisa, Ke Jin, Pengyuan Xiu, Miguel L. Crespillo, Yanwen Zhang, Hongbin Bei, Lumin Wang, Tai-ni Yang, [2018] Acta Materialia · DOI: 10.1016/j.actamat.2018.03.054 · ISSN: 1359-6454 | |
"Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys" Taini Yang, Ke Jin, Ning Gao, Pengyuan Xiu, Yanwen Zhang, Fei Gao, Hongbin Bei, William J. Weber, Kai Sun, Yan Dong, Lumin Wang, Chenyang Lu, [2017] Acta Materialia · DOI: 10.1016/j.actamat.2017.01.019 · ISSN: 1359-6454 | |
"Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys"
Liangliang Niu, Nanjun Chen, Ke Jin, Taini Yang, Pengyuan Xiu, Yanwen Zhang, Fei Gao, Hongbin Bei, Shi Shi, Mo-Rigen He, Ian M. Robertson, William J. Weber, Lumin Wang, Chenyang Lu,
[2016]
Nature Communications
· DOI: 10.1038/ncomms13564
· ISSN: 2041-1723
A grand challenge in material science is to understand the correlation between intrinsic properties and defect dynamics. Radiation tolerant materials are in great demand for safe operation and advancement of nuclear and aerospace systems. Unlike traditional approaches that rely on microstructural and nanoscale features to mitigate radiation damage, this study demonstrates enhancement of radiation tolerance with the suppression of void formation by two orders magnitude at elevated temperatures in equiatomic single-phase concentrated solid solution alloys, and more importantly, reveals its controlling mechanism through a detailed analysis of the depth distribution of defect clusters and an atomistic computer simulation. The enhanced swelling resistance is attributed to the tailored interstitial defect cluster motion in the alloys from a long-range one-dimensional mode to a short-range three-dimensional mode, which leads to enhanced point defect recombination. The results suggest design criteria for next generation radiation tolerant structural alloys. |
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"Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone" Zhi-Ming Zhang, Peng-Yuan Xiu, Jian-Qiu Wang, En-Hou Han, Wei Ke, Ming-Xing Su, Hong-Liang Ming, [2016] Acta Metallurgica Sinica (English Letters) · DOI: 10.1007/s40195-016-0461-7 · ISSN: 1006-7191 | |
"Microstructure, Residual Strain and Stress Behavior in 316L Heat-Affected Zone" Zhi-Ming Zhang, Peng-Yuan Xiu, Jian-Qiu Wang, En-Hou Han, Wei Ke, Ming-Xing Su, Hong-Liang Ming, [2016] Acta Metallurgica Sinica (English Letters) · DOI: 10.1007/s40195-016-0461-7 | |
"Observation of magnetic-field-induced transformation in MnCo0.78Fe0.22Ge alloys with colossal strain output and large magnetocaloric effect" Pengyuan Xiu, Lian Huang, Zhihua Nie, Junxi Zeng, Dennis E. Brown, Yang Ren, Yandong Wang, Zilong Wang, [2016] Journal of Magnetism and Magnetic Materials · DOI: 10.1016/j.jmmm.2015.12.083 · ISSN: 0304-8853 | |
"Observation of magnetic-field-induced transformation in MnCo |
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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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