Haiming Wen
- Name
- Professor Haiming Wen
- Institution
- Missouri University of Science and Technology
- Position
- Assistant Professor
- Affiliation
- Missouri University of Science and Technology
- h-Index
- 25
- ORCID
- 0000-0003-2918-3966
- Expertise
- Atom Probe Tomography, Irradiation, Mechanical Properties, Nanostructured Materials, Steels
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"A strong and ductile cobalt-free solid-solution Fe30Ni30Mn30Cr10 multi-principal element alloy from hot rolling"
Hans Pommerenke, Jiaqi Duan, Nathan Curtis, Victor DeLibera, Adam Bratten, Andrew Hoffman, Mario Buchely, Ron O'Malley, Haiming Wen,
J. of Alloys and Compounds
Vol. 948
2023
Link
Most of the face-centered cubic (FCC) multi-principal element alloys (MPEAs) developed thus far contain cobalt. For many applications, it is either required or beneficial to avoid cobalt, since cobalt has long-term activation issue (for nuclear applications), is expensive, and is considered a critical material. In addition, FCC structured solid-solution MPEAs tend to have relatively low strength. A FCC solid-solution Fe30Ni30Mn30Cr10 (at %) MPEA was fabricated via arc melting, followed by homogenization at 1100 °C for 12 h. The alloy was hot rolled at 1100 °C with a total reduction of up to 97 %. The microstructure was characterized and mechanical properties were investigated at various stages. Tensile testing showed that yield strength (YS) increased by 285–595 MPa and ultimate tensile strength (UTS) increased by 520–710 MPa. This increase in YS and UTS occurred with a total elongation (ductility) of 40 %. Meanwhile, hot rolling at high reductions led to evident decreases in size and area fraction of Mn-rich inclusions. Overall, after hot rolling, this FCC solid-solution MPEA is both strong and ductile. |
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| "Annealing behavior in a high-pressure torsion-processed Fe–9Cr steel" Jiaqi Duan, Haiming Wen, Caizhi Zhou, Xiaoqing He, Rinat Islamgaliev, Ruslan Valiev, Journal of Materials Science Vol. 55 2020 6678-6695 Link | ||
| "Discontinuous grain growth in an equal-channel angular pressing processed Fe-9Cr alloy with a heterogeneous microstructure" Jiaqi Duan, Haiming Wen, Caizhi Zhou, Xiaoqing He, Rinat Islamgaliev, Ruslan Valiev, Materials Characterization Vol. 159 2020 110004 Link | ||
| "Distribution of fission products palladium, silver, cerium and cesium in the un-corroded areas of the locally corroded SiC layer of a neutron irradiated TRISO fuel particle" Haiming Wen, Isabella van Rooyen, Journal of the European Ceramic Society Vol. 37 (2017) 2017 3271-3284 Link | ||
| "Effect of grain size on the irradiation response of Grade 91 steel subjected to Fe ion irradiation at 300 °C" Haiming Wen, Jiaqi Duan, Li He, Journal of Materials Science Vol. 57 2022 13767-13778 Link | ||
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"Effects of Al and Ti Additions on Irradiation Behavior of FeMnNiCr Multi-Principal-Element Alloy"
Andrew Hoffman, Haiming Wen, Li He, Kumar Sridharan, Matthew Luebbe, Jiaqi Duan,
JOM
Vol. 72
2020
150-159
Two Co-free multi-principal-element alloys (MPEAs), viz. single-phase face-centered cubic (FCC) Fe30Ni30Mn30Cr10 and (Fe30Ni30Mn30Cr10)94Ti2Al4 (all in atomic percent) with FCC matrix containing Ni-Ti-Al enriched L12 (ordered FCC) secondary phase (γ′), have been developed and investigated. The alloys were ion irradiated at 300°C and 500°C to peak damage of 120 displacements per atom (dpa). Compared with the (Fe30Ni30Mn30Cr10)94Ti2Al4 alloy, in the Fe30Ni30Mn30Cr10 alloy, the dislocation loops were smaller, with a higher number density. The difference in loop size between the two MPEAs was attributed to the addition of Ti to the matrix, which was anticipated to lower the stacking fault energy and stabilize the faulted Frank loops. The γ′ phase showed good stability under irradiation, with no new γ′ precipitation or growth in existing precipitates. Both alloys showed similar irradiation-induced hardening at 300°C, but the (Fe30Ni30Mn30Cr10)94Ti2Al4 alloy exhibited lower irradiation-induced hardening at 500°C compared with the Fe30Ni30Mn30Cr10 alloy. |
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| "Effects of the Tempering and High-Pressure Torsion Temperatures on Microstructure of Ferritic/Martensitic Steel Grade 91" Artur Ganeev, Marina Nikitina, Vil Sitdikov, Rinat Islamgaliev, Andrew Hoffman, Haiming Wen, Materials Vol. 11 2018 Link | ||
| "Electron Microscopy Study of Pd, Ag, and Cs in Carbon Areas in the Locally Corroded SiC Layer in a Neutron-Irradiated TRISO Fuel Particle" Haiming Wen, Isabella van Rooyen, John Hunn, Tyler Gerczak, Journal of the European Ceramic Society Vol. 38 (2018) 2016 4173-4188 Link | ||
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"Enhanced Resistance to Irradiation Induced Ferritic Transformation in Nanostructured Austenitic Steels"
Andrew Hoffman, Maalavan Arivu, Haiming Wen, Li He, Kumar Sridharan, Xin Wang, Xiang Liu, Lingfeng He, Yaqiao Wu,
Materialia
Vol. 13
2020
Link
Irradiation induced phase transformation of γ-austenite to α-ferrite has been observed in austenitic steels for the past several decades. This transformation can be detrimental to structural materials in a nuclear reactor environment as the increased fraction of the ferritic phase can increase corrosion and embrittlement and lead to stress corrosion cracking. This transformation is caused by both strain induced martensite transformation as well as radiation induced segregation and precipitation. In this study, two radiation tolerant nanostructured 304L austenitic steels (one ultrafine grained and one nanocrystalline) were manufactured using severe plastic deformation. These nanostructured 304L steels were compared to conventional coarse-grained 304L, after self-ion irradiation at 500°C up to a peak damage of 50 displacements per atom. Phase fraction after irradiation was analyzed using grazing incidence x-ray diffraction, precession electron diffraction, and electron backscatter diffraction. Nanostructured 304L steels showed significant resistance to irradiation induced austenite to ferrite transformation. This resistance was shown to be due to a decrease in defect formation, as well as a reduction in radiation induced segregation and precipitation. |
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| "Evolution of microstructure and texture during annealing in a high-pressure torsion processed Fe-9Cr alloy" Haiming Wen, Jiaqi Duan, Caizhi Zhou, Rinat Islamgaliev, Ruslan Valiev, Materialia Vol. 6 2019 100349 Link | ||
| "High-pressure Torsion Assisted Segregation and Precipitation in a Fe-18Cr-8Ni Austenitic Stainless Steel" Andrew Hoffman, Haiming Wen, Rinat Islamgaliev, Ruslan Valiev, Materials Letters Vol. 243 2019 116-119 Link | ||
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"Local chemical ordering of a neutron-irradiated CrFeMnNi compositionally complex alloy"
Nathan Curtis, Sohail Shah, Mukesh Bachhav, Kaustubh Bawane, Fei Teng, Calvin Parkin, Tiankai Yao, Haiming Wen, Adrien Couet,
Acta Materialia
Vol. 286
2025
Link
While ion-irradiation studies are a critical first step in studying compositionally complex alloys (CCAs) for nuclear applications, they do not capture all the microstructural changes occurring under the low irradiation dose rates and different particles’ scattering patterns experienced in a nuclear reactor setting. To explore these phenomena in reactor-relevant conditions for the first time in CCA, the single-phase solid-solution Cr10Fe30Mn30Ni30 was neutron irradiated up to 6.61 displacements per atom at 395 and 579 °C. Irradiation-enhanced local chemical ordering (LCO) well beyond the range of short range ordering was observed, and is predicted to be the precursor to the precipitation of a coherent Ni-Mn L10 phase and a Cr-rich α’ phase, though TEM analysis did not indicate the presence of either in any irradiation condition. The line density of faulted dislocation loops decreased from 6.47 to 1.69 ∙ 1015 m−2 from 3.43 to 6.61 dpa at 579 °C despite no appreciable faulted loop content in the unirradiated material. LCO is expected to increase the complexity of the energy landscape within this alloy, restricting interstitial point defect mobility and creating local regions of greater stacking fault energy. These contribute to the negative correlation between irradiation dose and faulted dislocation loop density in this study, as well as the lack of void swelling observed. |
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| "Microstructure, strength and irradiation response of an ultra-fine grained FeNiCoCr multi-principal element alloy" Haiming Wen, Journal of Alloys and Compounds Vol. 851 2021 156796 Link | ||
| "Novel effects of grain size and ion implantation on grain boundary segregation in ion irradiated austenitic steel" Haiming Wen, Acta Materialia Vol. 246 2023 Link | ||
| "Severe plastic deformation assisted carbide precipitation in Fe-21Cr-5Al alloy" Maalavan Arivu, Andrew Hoffman, Jiaqi Duan, Haiming Wen, Rinat Islamgaliev, Ruslan Valiev, Materials Letters Vol. 253 2019 78-81 Link |
| "Advanced Studies of Radiation Damage in Compositionally Complex Alloys" Haiming Wen, Dane Morgan, Adrien Couet, Nathan Curtis, Michael Moorehead, Mukesh Bachhav, Sohail Shah, Phalgun Nelaturu, Junliang Liu, Daniel Murray, Bao-Phong Nguyen, Dan Thoma, ” The Minerals, Metals, & Materials Society Conference March 3-7, (2024) | |
| "Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy" Nathan Curtis, Calvin Parkin, Tiankai Yao, Mukesh Bachhav, Haiming Wen, Adrien Couet, Nuclear Science User Facilities’ Science Review Board Meeting August 1-1, (2023) | |
| "Effects of severe plastic deformation and irradiation on precipitation in ultrafine-grained steels studied using atom-probe tomography" Andrew Hoffman, Haiming Wen, 2019 TMS Annual Meeting March 10-14, (2019) | |
| "Effects of Ti and Al Additions on Irradiation Behavior of FeMnNiCr Based High Entropy Alloys" Andrew Hoffman, Haiming Wen, Li He, Kumar Sridharan, 2019 TMS Annual Meeting March 10-14, (2019) | |
| "Effects of Ti and Al Additions on Irradiation Behavior of FeMnNiCr Based High-Entropy Alloys" Matthew Luebbe, Andrew Hoffman, Hans Pommeranke, Li He, Kumar Sridharan, Haiming Wen, Materials Science & Technology 2019 September 29-3, (2019) | |
| "Enhanced Austenite Stability in Nanostructured Steels During Ion Irradiation" Andrew Hoffman, Haiming Wen, Maalavan Arivu, 2020 TMS Annual Meeting February 23-27, (2020) | |
| "Micro/Nano Structural Examination and Fission Product Identification in Neutron Irradiated AGR-1 TRISO Fuel" Terry Holesinger, Haiming Wen, 2016 International Topical Meeting on High Temperature Reactor Technology (HTR 2016) November 6-10, (2016) Link | |
| "Microstructure evolution in irradiation-tolerant ultrafine-grained steels" Haiming Wen, Andrew Hoffman, Jiaqi Duan, 2019 TMS Annual Meeting March 10-14, (2019) | |
| "Neutron Irradiation Induced Local Chemical Ordering in CrFeMnNi and CrFeMnNiTiAl Compositionally Complex Alloys" Nathan Curtis, Sohail Shah, Kaustubh Bawane, Fei Teng, Tiankai Yao, Mukesh Bachhav, Haiming Wen, Adrien Couet, The Minerals, Metals, & Materials Society Conference March 23-27, (2025) | |
| "The role of electron and atom probe tomography in characterization of nuclear fuels" Assel Aitkaliyeva, Cynthia Papesch, Yaqiao Wu, Haiming Wen, Nuclear Fuels and Structural Materials (NFSM-2016) June 12-16, (2016) |
| U.S. DOE Nuclear Science User Facilities Awards 30 Rapid Turnaround Experiment Research Proposals - Awards total nearly $1.2 million The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 30 new Rapid Turnaround Experiment (RTE) projects, totaling up to approximately $1.2 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. Wednesday, April 26, 2017 - Calls and Awards |
| U.S. DOE Nuclear Science User Facilities Awards 35 Rapid Turnaround Experiment Research Proposals - Awards total approximately $1.3 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. Wednesday, September 20, 2017 - Calls and Awards |
| 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 |
| NSUF Researcher Feature: Haiming Wen - Monday, July 20, 2020 - Researcher Highlight |
| NSUF awards 30 Rapid Turnaround Experiment proposals - Approximately $1.53M has been awarded. Tuesday, June 14, 2022 - Calls and Awards |
| NSUF awards 22 Rapid Turnaround Experiment proposals - Thursday, September 14, 2023 - Calls and Awards |
NSUF Profile
This NSUF Profile is 75
Accomplished Author
Authored 10+ NSUF-supported publications
Top 5% Presenter
Top 5% of all NSUF-supported presenters
Top 5% Submitter
Top 5% of all RTE Proposal submissions
Top 5% Researcher
Top 5% of all RTE Proposals awarded
Accomplished Collaborator
Collaborated on 3+ RTE Proposals
Accomplished Reviewer
Reviewed 10+ RTE Proposals
Understanding the role of nanostructuring in enhancing phase stability of 304 austenitic steel during irradiation via in-situ ion irradiation in transmission electron microscope - FY 2023 RTE 3rd Call, #23-4756
Irradiation behavior of nanostructured ferritic/martensitic Grade 91 steel at high dose - FY 2022 RTE 1st Call, #22-4406
Enhancing irradiation tolerance of steels via nanostructuring by innovative manufacturing techniques - FY 2016 CINR, #16-10537
Nanostructuring to enhance irradiation tolerance of ferritic/martensitic Grade 91 steels - FY 2018 RTE 2nd Call, #18-1403
Enhanced irradiation tolerance of high-entropy alloys - FY 2017 RTE 3rd Call, #17-1122
Atom Probe Tomography Study of Neutron Irradiated U-Mo Fuel - FY 2017 RTE 2nd Call, #17-952
Ion irradiation of advanced materials – nanostructured steels and high entropy alloysNew Proposal - FY 2017 RTE 1st Call, #16-865
STEM/EELS Study of Fission Product Transport in Neutron Irradiated TRISO Fuel Particles - FY 2015 RTE 3rd Call, #15-581
Atom Probe Tomography and Transmission Electron Microscopy of Neutron-Irradiated Nanocrystalline Compositionally Complex Alloys - FY 2023 RTE 3rd Call, #23-4768
High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys - FY 2023 RTE 1st Call, #23-4521
Atom probe and transmission electron microscopy studies on neutron irradiated FeCrMnNi Compositionally Complex Alloy - FY 2022 RTE 1st Call, #22-4459
Correlative Transmission Electron Microscopy and Atom Probe Tomography Study of Radiation Induced Segregation and Precipitation in Nanostructured SS304 - FY 2019 RTE 3rd Call, #19-2880
Advanced microstructural characterization of irradiation-induced phase transformation in 304 steel - FY 2019 RTE 3rd Call, #19-2858
Alleviating irradiation-induced precipitation in a Fe-21Cr-5Al alloy via nanostructuring. - FY 2019 RTE 2nd Call, #19-1761
Advanced Characterizations of Low-dose Neutron Irradiated T91 and HT9 Alloys - FY 2015 CINR, #CFA-15-8312
APT Study of Fission Product Transport in Unirradiated/Neutron Irradiated TRISO Fuel Particles - FY 2015 RTE 1st Call, #15-541
About Us
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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