Ce Zheng

Publications:
"Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion-irradiated advanced ferritic/martensitic steels" Ce Zheng, Stuart Maloy, Djamel Kaoumi, Scripta Materialia Vol. 162 2019 460-464 Link
"Effect of dose on irradiation-induced loop density and Burgers vector in ion-irradiated ferritic/ martensitic steel HT9" Ce Zheng, Stuart Maloy, Djamel Kaoumi, Philosophical Magazine Vol. 98 2018 2440-2456 Link
TEM samples of F/M steel HT9 were irradiated to 20 dpa at 420°C, 440°C and 470°C in a TEM with 1 MeV Kr ions so that the microstructure evolution could be followed in situ and characterized as a function of dose. Dynamic observations of irradiation-induced defect formation and evolution were done at different temperatures. The irradiation-induced loops were characterized in terms of their Burgers vector, size and density as a function of dose and similar observations and trends were found at the three temperatures: (i) both a/2 <111> and a <100> loops are observed; (ii) in the early stage of irradiation, the density of irradiation-induced loops increases with dose (0-4 dpa) and then decreases at higher doses (above 4 dpa), (iii) the dislocation line density shows an inverse trend to the loop density with increasing dose: in the early stages of irradiation the pre-existing dislocation lines are lost by climb to the surfaces while at higher doses (above 4 dpa), the build-up of new dislocation networks is observed along with the loss of the radiation-induced dislocation loops to dislocation networks; (iv) at higher doses, the decrease of number of loops affects more the a/2 <111> loop population; the possible loss mechanisms of the a/2 <111> loops are discussed. Also, the ratio of a <100> to a/2 <111> loops is found to be similar to cases of bulk irradiation of the same alloy using 5 MeV Fe2+ions to similar doses of 20 dpa at similar temperatures.
"Ion irradiation effects on commercial PH 13-8 Mo maraging steel Corrax" Ce Zheng, Ryan Schoell, Peter Hosemann, Djamel Kaoumi, Journal of Nuclear Materials Vol. 514 2019 255-265 Link
"Microstructural and nanomechanical characterization of in-situ He implanted and irradiated fcc materials" David Frazer, Peter Hosemann, Djamel Kaoumi, Ce Zheng, Microscopy & Microanalysis Vol. 23 (Suppl 1) 2017 756-757 Link
"Microstructure characterization of ion-irradiated Ferritic/Martensitic HT9 steel" Djamel Kaoumi, Ce Zheng, Microscopy & Microanalysis Vol. 23 2017 Link
"Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel" Maria A Auger, Djamel Kaoumi, Ce Zheng, Michael Moody, Journal of Nuclear Materials Vol. 491 2017 162-176 Link
In this study, Ferritic/Martensitic (F/M) HT9 steel was irradiated to 20 displacements per atom (dpa) at 600 nm depth at 420 and 440 °C, and to 1, 10 and 20 dpa at 600 nm depth at 470 °C using 5 MeV Fe++ ions. The characterization was conducted using ChemiSTEM and Atom Probe Tomography (APT), with a focus on radiation induced segregation and precipitation. Ni and/or Si segregation at defect sinks (grain boundaries, dislocation lines, carbide/matrix interfaces) together with Ni, Si, Mn rich G-phase precipitation were observed in self-ion irradiated HT9 except in very low dose case (1 dpa at 470 °C). Some G-phase precipitates were found to nucleate heterogeneously at defect sinks where Ni and/or Si segregated. In contrast to what was previously reported in the literature for neutron irradiated HT9, no Cr-rich α′ phase, χ-phases, η phase and voids were found in self-ion irradiated HT9. The difference of observed microstructures is probably due to the difference of irradiation dose rate between ion irradiation and neutron irradiation. In addition, the average size and number density of G-phase precipitates were found to be sensitive to both irradiation temperature and dose. With the same irradiation dose, the average size of G-phase increased whereas the number density decreased with increasing irradiation temperature. Within the same irradiation temperature, the average size increased with increasing irradiation dose.
Presentations:
"Combined use of in-situ and ex-situ TEM to characterize ion irradiation induced dislocation loops in F/M steels" Djamel Kaoumi, Ce Zheng, E-MRS 2018 June 18-22, (2018)
"Dose effect on the irradiation induced loop density & Burgers vector in ion-irradiated alloy T91 irradiated in-situ in a TEM" Djamel Kaoumi, Ce Zheng, TMS 2018 March 11-15, (2018)
"Dose effect on the irradiation induced loop density and Burgers vector in ion-irradiated ferritic/martensitic steel HT9 through in-situ TEM," Djamel Kaoumi, Ce Zheng, MMM 2018 October 28-2, (2018)
"In-situ ion irradiation induced microstructure evolution in ferritic/martensitic steel HT9" Djamel Kaoumi, Ce Zheng, Microscopy and Microanalysis meeting 2017 August 1-4, (2017)
"In-situ ion irradiation induced microstructure evolution in Ferritic/Martensitic steel T91, poster presentation" Djamel Kaoumi, Ce Zheng, TMS-2017 conference February 26-2, (2017)
"Use of In-Situ TEM to study the Dose Effect on the Irradiation Induced Loop Density and Burgers Vector in an Ion-Irradiated F/M Steel for Nuclear Applications" Djamel Kaoumi, Ce Zheng, WOTWISI-5 April 11-13, (2018)
Additional Publications:
"Effect of low activation rare-earth oxides on sintering of β-SiC" Ce Zheng, Chong Wei, Shanshan Xu, Yichun Bi, Xiaoqiang Li, Dengzhou Xu, [2022] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2022.08.008 · ISSN: 0955-2219
"The corrosion behavior of CVD SiC coatings on SiCf/SiC composites in a simulated molten salt reactors environment" Chuanxin Liu, Ce Zheng, Bo Chen, Jing Zhang, Shanglei Feng, Hefei Huang, Xiaoqiang Li, Yiming Qin, [2022] Corrosion Science · DOI: 10.1016/j.corsci.2022.110411 · ISSN: 0010-938X
"Microstructure response of Amosic-3 SiC/SiC composites under self-ion irradiation" Ce Zheng, Yichun Bi, Qingping Mao, Hailong Qin, Yiming Qin, Xiaoqiang Li, Shanshan Xu, [2022] Journal of the European Ceramic Society · DOI: 10.1016/j.jeurceramsoc.2021.11.032 · ISSN: 0955-2219
"Creep properties of advanced austenitic steel 709 determined through short experiments under in-situ neutron diffraction followed by TEM characterization" Ryan Schoell, Ce Zheng, Mahmut N. Cinbiz, Matthew Frost, Ke An, Djamel Kaoumi, Yuchen Zhao, [2021] Materials Characterization · DOI: 10.1016/j.matchar.2021.111519 · ISSN: 1044-5803
"Effect of deposition temperature on the corrosion behavior of CVD SiC coatings on SiCf/SiC composites under simulated PWR conditions" Xiaoqiang Li, Chuanxin Liu, Ce Zheng, Qingping Mao, Bo Chen, Ke Jing, Yaru Tan, Laifei Cheng, Litong Zhang, Yiming Qin, [2021] Corrosion Science · DOI: 10.1016/j.corsci.2020.109233 · ISSN: 0010-938X
"Helium bubble nucleation and growth in alloy HT9 through the use of in situ TEM: Sequential he-implantation and heavy-ion irradiation versus dual-beam irradiation" Ce Zheng, Cedric Baumier, Aurelie Gentils, Djamel Kaoumi, Kai Duemmler, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152641 · EID: 2-s2.0-85095569165 · ISSN: 0022-3115
"Contrasting roles of Laves_Cr2Nb precipitates on the creep properties of novel CuCrNbZr alloys" Ce Zheng, Boopathy Kombaiah, Lizhen Tan, David J. Sprouster, Lance L. Snead, Steven J. Zinkle, Ying Yang, Ling Wang, [2020] Materials Science and Engineering A · DOI: 10.1016/j.msea.2020.139110 · EID: 2-s2.0-85080908509 · ISSN: 0921-5093
"Dislocation loop evolution in F/M steel T91 under in-situ ion irradiation: Influence of the presence of initial dislocations" Djamel Kaoumi, Ce Zheng, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152363 · EID: 2-s2.0-85087763078 · ISSN: 0022-3115
"Effect of heterostructure and hetero-deformation induced hardening on the strength and ductility of brass" G.Z. He, C. Zheng, X.L. Ma, D. Kaoumi, Y.S. Li, Y.T. Zhu, X.T. Fang, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.01.037 · EID: 2-s2.0-85078444623 · ISSN: 1359-6454
"In Situ Micropillar Compression Tests of 304 Stainless Steels After Ion Irradiation and Helium Implantation" David Frazer, Ce Zheng, Peter Hosemann, Djamel Kaoumi, Ryan Schoell, [2020] JOM · DOI: 10.1007/s11837-020-04127-2 · EID: 2-s2.0-85082954591 · ISSN: 1543-1851
"Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature" Elaina R. Reese, Kevin G. Field, Tian Liu, Emmanuelle A. Marquis, Stuart A. Maloy, Djamel Kaoumi, Ce Zheng, [2020] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.151845 · EID: 2-s2.0-85073823752 · ISSN: 0022-3115
"Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels" Jia-Hong Ke, Stuart A. Maloy, Djamel Kaoumi, Ce Zheng, [2019] Scripta Materialia · DOI: 10.1016/j.scriptamat.2018.12.018 · EID: 2-s2.0-85058704067 · ISSN: 1359-6462
"Influence of annealing parameters on the mechanical properties of heterogeneous lamella structured 5083 aluminum alloy" Guozhen He, Michael Ruiz, Ce Zheng, Yanfei Wang, Zhongkai Li, Yuntian Zhu, Xiaotian Fang, [2019] Letters on Materials · DOI: 10.22226/2410-3535-2019-4-556-560 · EID: 2-s2.0-85078409497 · ISSN: 2410-3535
"Ion irradiation effects on commercial PH 13-8 Mo maraging steel Corrax" Ryan Schoell, Peter Hosemann, Djamel Kaoumi, Ce Zheng, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.11.041 · EID: 2-s2.0-85058006280 · ISSN: 0022-3115
"Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose" Elaina R. Reese, Kevin G. Field, Emmanuelle Marquis, Stuart A. Maloy, Djamel Kaoumi, Ce Zheng, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.06.019 · EID: 2-s2.0-85067602813 · ISSN: 0022-3115
"Effect of dose on irradiation-induced loop density and Burgers vector in ion-irradiated ferritic/martensitic steel HT9" Stuart Maloy, Djamel Kaoumi, Ce Zheng, [2018] Philosophical Magazine · DOI: 10.1080/14786435.2018.1490825 · EID: 2-s2.0-85049588670
"Nano-size metallic oxide particle synthesis in Fe-Cr alloys by ion implantation" A. Gentils, J. Ribis, V.A. Borodin, L. Delauche, B. Arnal, C. Zheng, [2017] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2017.03.067 · EID: 2-s2.0-85015421720
"Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel" D. Kaoumi, C. Zheng, [2017] Materials Characterization · DOI: 10.1016/j.matchar.2017.10.019 · EID: 2-s2.0-85032004953
"Thermal annealing behavior of nano-size metal-oxide particles synthesized by ion implantation in Fe-Cr alloy" A. Gentils, J. Ribis, V. A. Borodin, M. Descoins, D. Mangelinck, F. Dalle, B. Arnal, L. Delauche, C. Zheng, [2017] Journal of Applied Physics · DOI: 10.1063/1.4982756 · EID: 2-s2.0-85018759287

Oxide dispersion strengthened (ODS) steels are promising structural materials for the next generation nuclear reactors, as well as fusion facilities. The detailed understanding of the mechanisms involved in the precipitation of nano-oxides during ODS steel production would strongly contribute to the improvement of the mechanical properties and the optimization of manufacturing of ODS steels, with a potentially strong economic impact for their industrialization. A useful tool for the experimental study of nano-oxide precipitation is ion implantation, a technique that is widely used to synthesize precipitate nanostructures in well-controlled conditions. Earlier, we have demonstrated the feasibility of synthesizing aluminum-oxide particles in the high purity Fe-10Cr alloy by consecutive implantation with Al and O ions at room temperature. This paper describes the effects of high-temperature annealing after the ion implantation stage on the development of the aluminum based oxide nanoparticle system. Using transmission electron microscopy and atom probe tomography experiments, we demonstrate that post-implantation heat treatment induces the growth of the nano-sized oxides in the implanted region and nucleation of new oxide precipitates behind the implantation zone as a result of the diffusion driven broadening of implant profiles. A tentative scenario for the development of metal-oxide nano-particles at both ion implantation and heat treatment stages is suggested based on the experimental observations.

"Metal-oxide nanoclusters in Fe-10%Cr alloy by ion implantation" Aurélie Gentils, Joël Ribis, Vladimir A. Borodin, Odile Kaïtasov, Frédérico Garrido, Ce Zheng, [2015] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2015.08.020 · EID: 2-s2.0-84948566002
"Nano-size metallic oxide particle nucleation in high purity Fe-10%Cr alloy by ion implantation" [2015] PTM 2015 - Proceedings of the International Conference on Solid-Solid Phase Transformations in Inorganic Materials 2015 · EID: 2-s2.0-84962633668
"The feasibility of Al-based oxide precipitation in Fe-10%Cr alloy by ion implantation" Aurélie Gentils, Joël Ribis, Odile Kaïtasov, Vladimir A. Borodin, Marion Descoins, Dominique Mangelinck, Ce Zheng, [2014] Philosophical Magazine · DOI: 10.1080/14786435.2014.941028 · EID: 2-s2.0-84906780240
Source: ORCID/CrossRef using DOI