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7篇 您的检索式:作者名="Tongda Ma"
    题名 作者 年代 出处 被引量
1In-situ Observation of Point Defect and Precipitate Evolvement of CLAM Steel under Electron Irradiation显示文摘The point defect and precipitate evolution of China low activation martensitic steel(CLAM) under electron beam irradiation were characterized by high voltage electron microscopy.The process was recorded in-situ on electronsensitive films.The irradiation dose rate was 1.78×10^(-3) dpa/s and the highest dose was 2.12 dpa/s.Irradiation introduced dislocation loops into the sub-grain,which increased density when the irradiation dose was increased from 0.53 dpa to 1.59 dpa at 723 K.The precipitate,found to be an M_6C type,was irradiated at 773 K at the [011]plane direction.The precipitate morphology and structure were unchanged when the irradiation dose was increased to 2.12 dpa.Compared with the irradiation at 723 K in the sub-grain,no other defects were generated at the nearby grain boundary at 773 K.Yong Xin Tongda Ma Xin Ju Jie Qiu 2013Journal of Materials Science & Technology2013,29,5:2
2Characterization of Si/SiGe/Si Deposited on SIMOX SOI by Synchrotron Radiation X-Ray Double-crystal Topography显示文摘The synchrotron X-ray double-crystal topography was employed to investigate the structure of Si/SiGe/Si deposited on SIMOX SOI. Rocking curves with three diffraction peaks were acquired before and after 180° rotation of samples. Double-crystal topographs taken at the full width at half maximum (FWHM) of the three peaks differ from each other. Many defects appear in the Si layers that are likely related to the tilt between SOI and epitaxial layers.Ma Tongda Tu Hailing Hu Guangyong Wang Jing 2004Journal of Rare Earths2004,22,z2:0
3低温下高能重离子辐照低活化铁素体/马氏体钢CLF-1的微硬度变化行为研究显示文摘In the present work,irradiation hardening of a reduced activation ferritic/martensitic steel CLF-1 candidate to fusion reactor blankets was studied.Specimens were irradiated with high-energy N and Fe ions at about-50℃.Energy of the incident ions was dispersed to successively decreasing 10 grades by using an energy degrader,thereby generating an atomic displacement damage plateau in the specimens from the surface to a depth of 25m,which is sufficiently broad for the Vickers hardness test.Three damage levels of 0.05,0.1 and 0.2 dpa were approached.Depth distribution of atomic displacement damage(in dpa)was estimated by SRIM 2013 code(using Kinchin-Pease model,with a displacement threshold energy Ed=40 eV[1]).Ding Zhaonan Zhang Chonghong Yang Yito Chen Yuguang Zhang Xianlong Song Yin Ma Tongda Xu Yuping Luo Guangnan 2018IMP & HIRFL Annual Report2018,,1:0
4High auxin stimulates callus through SDG8-mediated histone H3K36 methylation in Arabidopsis显示文摘Callus induction,which results in fate transition in plant cells,is considered as the first and key step for plant regeneration.This process can be stimulated in different tissues by a callus-inducing medium(CIM),which contains a high concentration of phytohormone auxin.Although a few key regulators for callus induction have been identified,the multiple aspects of the regulatory mechanism driven by high levels of auxin still need further investigation.Here,we find that high auxin induces callus through a H3 K36 histone methylation-dependent mechanism,which requires the methyltransferase SET DOMAIN GROUP 8(SDG8).During callus induction,the increased auxin accumulates SDG8 expression through a TIR1/AFBs-based transcriptional regulation.SDG8 then deposits H3 K36 me3 modifications on the loci of callus-related genes,including a master regulator WOX5 and the cell proliferation-related genes,such as CYCB1.1.This epigenetic regulation in turn is required for the transcriptional activation of these genes during callus formation.These findings suggest that the massive transcriptional reprogramming for cell fate transition by auxin during callus formation requires epigenetic modifications including SDG8-mediated histone H3 K36 methylation.Our results provide insight into the coordination between auxin signaling and epigenetic regulation during fundamental processes in plant development.Jun Ma Qiang Li Lei Zhang Sen Cai Yuanyuan Liu Juncheng Lin Rongfeng Huang Yongqiang Yu Mingzhang Wen Tongda Xu 2022Journal of Integrative Plant Biology2022,64,12:0
53 - 44 Production and Annealing Behavior of Lattice Damage in Energetic Kr Implanted 6H-SiC显示文摘Meng Yancheng Zhang Chonghong Ma Tongda Fu Xin 2012IMP & HIRFL Annual Report2012,,1:0
64-30 Research Progress of Group of Energy Materials in 2016显示文摘The Group of Energy Materials(GEM)in IMP is engaged in the irradiation response of materials candidate to advanced nuclear energy systems(Gen IV,fusion reactors).The major progress of research in our group in 2016 is in the irradiation hardening/embrittlement of oxide-dispersion-strengthened(ODS)ferritic steels and Vanadium alloys,and in the mechanisms underlying damage production in silicon carbide(SiC)fibers.A brief description is given as follows.1.Effect of the oxide nano particles on the irradiation hardening of ODS ferritic steels The influence of oxide nano particles on the irradiation resistance of ODS ferritic steels is a crucial issue for the upgrade of ODS steels.Zhang Chonghong Ding Zhaonan Yang Yitao Song Yin Zhang Liqing Yan Tingxin Ma Tongda 2016IMP & HIRFL Annual Report2016,,1:0
74-33 Irradiation Hardening of V-4Cr-4Ti and V-5Cr-5Ti alloys Due to Helium Implantation and Displacement Damage显示文摘Vanadium alloys(V-Cr-Ti series)are important candidate materials for blanket components of fusion reactors due to their low activation and high strength at elevated temperatures.Low-temperature irradiation embrittlement determines the operation temperature limit of Vanadium alloys for the application to structural materials of fusion reactors irradiation response of vanadium alloys needs to be clarified for their application.In the present study,specimens of two alloys(V-4Cr-4Ti and V-5Cr-5Ti)were irradiated with energetic He ions and heavy ions to understand hardening of the alloys due to helium accumulation and cascade damage production.Yan Tingxing Zhang Chonghong Yang Yitao Zhang Liqing Ma Tongda 2016IMP & HIRFL Annual Report2016,,1:0
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