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| 1 | 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 | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 2 | 高能Sn离子引起碳化硅纤维损伤的X-射线衍射分析显示文摘Silicon carbide(SiC)fiber possesses low neutron capture cross-section,low induced radioactivity,high thermal stability,low density,high specific strength,good oxidation-ablation resistance,high specific modulus,especially improved flaw tolerance and non-catastrophic mode of failure.Therefore,silicon carbide fiber is considered as a candidate structural component in advanced nuclear industry fields.The irradiation damage which silicon carbide fiber will experience cannot be ignored.In fission reactors,SiC fibers are inevitably subjected to irradiation by various fission fragments(heavy ions with up to hundreds of MeV)irradiation,which are produced via chain fission of the uranium.While in fusion reactors,the average energy of recoils produced by neutron irradiation in materials can reach several hundred keV.Most of the energy of fission fragments/recoils is deposited in the materials mainly through electronic processes(excitation and ionization of atoms along the trajectory of ions).Therefore,it is indispensable to acquire a comprehensive knowledge of the microstructure of SiC fibers under energetic-heavy-ion irradiation. | Zhang Liqing Zhang Chonghong Huang Qing Zhang Xianlong Ding Zhaonan Chen Yuguang Li Jianyang Ma Baoshui | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 3 | 快重离子辐GaN的光谱特性研究显示文摘In the past decade,III-V semiconductor material such as gallium phosphide(GaP),gallium nitride(GaN)and related nitride compounds,have been developing very rapidly due to their wide range of applications.Ion beams were proven to be an efficient method to modify the structure and properties of the materials.In the present work,lattice defects produced in GaN crystal by 350 MeV 56Fe21+ions were characterized by using various methods including Raman scattering,XRD and photoluminescence(PL)spectrometry at room temperature. | Song Yin Chen Xiaoxu Zhang Xianlong Yang Yitao Ding Zhaonan Zhang Chonghong | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 4 | 利用小冲杆技术对于重离子辐照钢样品的本构关系的研究显示文摘In order to ensure the safety and evaluate lifetime extension of nuclear power plants,it is fundamentally significant to accurately surveillance the mechanical properties of the in-pile components.Irradiation hardening and embrittlement is a major concern[1].For the in-pile surveillance specimen test,it is convenient to use miniaturized specimens(with reduced radioactivity)to characterize the mechanical properties.For irradiation experiments using energetic ion beams as a surrogate method,the limited area of the ion beam and the limited depth of ion range make it compulsory to develop miniaturized specimen technique to evaluate the mechanical properties of materials.Among all the small specimen test technique,small punch test(SPT)is the most attractive and widely used,which employs disc specimens firmly gripped between two dies and deformed vertically into a circular hole by a spherical punch[2;3].The sample strength and ductility can not be obtained straightforward due to the complicated stress state and the load deflections curve(LDC).Data are generally interpreted by semi-empirical formulations[4].To characterize the constitutive relation and directly observe the deformation mechanism of the ion irradiated material is a challenging work. | Zhang Xianlong Zhang Chonghong Ding Zhaonan Chen Yuguang Ma Baoshui | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 5 | 核反应堆压力容器钢的辐照缺陷演化的OKMC模拟研究显示文摘Reactor Pressure Vessel(RPV)is a key structural component of nuclear reactor.It has to endure high-dose neutron irradiation during service.Neutron irradiation produces defect clusters and solute segregation,causing hardening and embrittlement of the RPV steel.A pretty number of testing and characterization techniques of microstructure and mechanical properties utilizing miniaturized specimens have been developed[1−4].Current experimental studies show that the increase of nano-hardness and micro-hardness of materials is positively correlated with that of macroscopic yield stress and ductile-brittle transition temperature[5;6].Meanwhile,some physical models related to defects,solute cluster characteristics and hardness change of materials have been established[7;8],supposing that the hardness increment in irradiation material mainly comes from the large heterogeneous clusters. | Li Jianyang Zhang Chonghong Ding Zhaonan | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 6 | Post-irradiation Annealing Behavior of Irradiation Hardening of China Low-CuRPV Steel显示文摘In the present work,irradiation hardening of a low-copper reactor pressure vessel steel(Chinese A508-3)was studied.Specimens of the RPV steel were irradiated with high-energy Fe ions at a terminal of a cyclotron at a low temperature around 173 K to two damage levels of 0.15 and 0.21 dpa. | Ding Zhaonan Zhang Chonghong Zhang Xianlong Chen Yuguang Yang Yitao Song Yin Liu Xiangbing Xue Fei | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 7 | An Investigation on Strains of Kr-ion-implanted and Subsequently Annealed SiC显示文摘Silicon carbide(SiC)has been considered as potential structural materials in advanced nuclear energy systems for many years due to its superior physical and chemical properties. | Zhang Liqing Zhang Chonghong Zhang Xianlong Ding Zhaonan Chen Yuguang Li Jianyang Xu Qiumei Han Xuxiao | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 8 | Study on Experiment and Finite Element Modelling of Small Punch Test显示文摘Due to the limitation of irradiation space in the test reactor and the dose restriction to testers for post-irradiation examination,small-scale specimen techniques are used in the nuclear industry as non-standard evaluation methods[1,2]. | Zhang Xianlong Ding Zhaonan Zhang Chonghong | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 9 | Effect of Fast Heavy Ion Irradiation on Luminescence Characteristics of SrLaAlO_(4)显示文摘SrLaAlO_(4) crystals have been widely used as high temperature superconductor films and substrate materials for white LED luminescent materials.Although SrLaAlO4 materials have been concerned and studied extensively. | Song Yin Zhang Xianlong Chen Yuguang Ding Zhaonan Yang Yitao Zhang Chonghong | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 10 | 高能离子辐照的ODS铁素体刚硬化效应研究显示文摘Influence of the nanoscale oxide particles on mechanical properties and irradiation resistance of oxide-dispersionstrengthened(ODS)ferritic steels is of critical importance for the use of the material in fuel cladding or blanket components in advanced nuclear reactors.In the present work,impact of structures of oxide dispersoids on the irradiation hardening of ODS ferritic steels was studied.Specimens of three kinds of high-Cr ODS ferritic steels containing oxide dispersoids with different number density and average size were irradiated with high-energy Niions at about−50℃.The energy of the incident Ni ions was varied from 12.73 to 357.86 MeV by using an energy degrader at the terminal so that a plateau of atomic displacement damage(∼0.8 dpa)was produced from the near surface to a depth of 24m in the specimens. | Ding Zhaonan Zhang Chonghong Yang Yitao Song Yin Zhang Xianlong Akihiko Kimura | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 11 | 高能氩离子引起碳化硅纤维损伤的透射电镜研究显示文摘Silicon carbide(SiC)fiber possesses low neutron capture cross-section,low induced radioactivity,high thermal stability,low density,high specific strength,good oxidation-ablation resistance,high specific modulus,especially improved flaw tolerance and non-catastrophic mode of failure.Therefore,silicon carbide fiber is considered as a candidate structural component in advanced nuclear industry fields.The irradiation damage which silicon carbide fiber will be subject to is inevitable.For structural components in fast breed reactors or in fusion reactors,the energy of PKAs(primary knocked-on atoms)produced by high-energy neutron irradiation can be several hundred keV,therefore effects of energy deposition via electronic processes(excitation and ionization)by PKAs in materials cannot be ignored.In situations of fuel cladding,materials may surfer from irradiation by fission fragments(which are heavy ions with up to hundreds of MeV).It is therefore necessary to know effects of energetic heavy-ion irradiation in silicon carbide for nuclear application. | Zhang Liqing Zhang Chonghong Huang Qing Ding Zhaonan Chen Yuguang Su Changhao Zhang Xianlong Ma Baoshui | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 12 | 350 MeV ^(56)Fe^(21)+离子辐照ZnO的微观结构和拉曼特性研究显示文摘ZnO is a typical II-VI semiconductor oxide material,which has attracted wide attention from the scientific community because of its excellent optical,photonic and electronic properties.ZnO single crystal was irradiated with 350 MeV ^(56)Fe^(21)+ ions from the HIRFL(Heavy Ion Research Facility in Lanzhou),and was subsequently investigated by Raman spectroscopy.Figure 1 shows Raman spectra of incident and scattered light along the z axis of ZnO single crystal with/without ion irradiation.With the increase of irradiation dose,Vo gradually increases and gets the saturation state at 1×10^(14) ions/cm^(2).Figure 2 shows the Raman spectra of Vertical z axis of incident and scattered light of ZnO single crystal irradiated to 1×10^(14) Fe-ions/cm^(2) at different depths from the surface.It can be seen that a maximum Vo defect peak appears near the end of the ion range.The active Raman mode is represented by the corresponding vibration of the ion,and the red arrow indicates the movement of the dominant ion. | Song Yin Zhang Chonghong Zhang Shengxia Yang Yitao Ding Zhaonan | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 13 | He离子注入ODS钢中硬化效应研究显示文摘In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,effects of helium bubbles formation in an oxide dispersion strengthened(ODS)steel is studied.Specimens of an ODS ferritic steel(15Cr-4Al-0.6Zr-0.1Ti)were implanted with mutiple-energy He ions at room temperature at the terminal of the 320 kV High-voltage Platform in IMP,to create a damage plateau of 0.4 dpa for average(corresponding to an He concentration of about 7000 appm)from the near surface to a depth about 1m.The specimen was subsequently thermally annealed at 800℃for 1 h in vacuum so that simple defects formed in the as-implanted state underwent significant recombination,meanwhile helium bubbles at nano-scale were formed. | Su Changhao Zhang Chonghong Yang Yitao Ding Zhaonan Chen Yuguang and Akihiko Kimura | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 14 | 4-30 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 | 2016 | IMP & HIRFL Annual Report2016，，1： | 0 |
| 15 | 3-26 Research Progress in Group of Energy Materials in 2015显示文摘The fracture behavior is a very important aspect of the mechanical properties of structure materials. For highenergy ions, their range in steels can be significantly larger than the average size of grains of steels, thus their irradiation can change the bulk properties of steels. It is therefore possible to study the fracture behavior of steel specimens irradiated with high-energy ions. | Zhang Chonghong Song Yin Yang Yitao Zhang Liqing Gou Jie Ding Zhaonan Chen Jiachao | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
| 16 | 3-28 Raman Spectra Study of Radiation Damage by Energetic Arq+ Ions on Silicon Carbide Fiber Surface显示文摘Silicon carbide (SiC) ber possesses high thermal stability, low density, high speci c strength, good oxidation-ablation resistance, high speci c modulus, especially improved aw tolerance and non-catastrophic mode of failure.Therefore, silicon carbide ber is widely used in aerospace, aviation, nuclear industry, and other elds. The radiation damage which silicon carbide ber will be subject to is inevitable though it is immune to various environments. | Zhang Liqing Zhang Chonghong Ding zhaonan Song Yin Yang Yitao Li Caisheng Fan Jiaqi Yuan Tingxing Huang Qing | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
| 17 | 3-29 Microstructure and Raman Spectra of Third Generation SiC Fibers by 410 MeV Sn Ion Beam Irradiation显示文摘Third generation SiC fibers have significantly improved the thermo-mechanical properties of SiC ceramic matrix composites which are considered as advanced materials for nuclear system application. In the present work, the Raman spectra presented in Fig. 1 give information related to the structural parameters of Sn-ion irradiated and unirradiated fibers. | Song Yin Zhang Chonghong Yang Yitao Ding Zhaonan Yan tingxin | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
| 18 | 3-30 Luminescence Effects of the Fe Ion Irradiated LED on the Terminal SFC-T1 at HIRFL显示文摘The lifetime of light-emitting diodes (LED) becomes a more important concern because of the increasing application of LED in the field of traffic light, solid-state light and color displays[1]. A life time test of a light source usually requires several thousand hours to ensure the successful application of LED in higher reliability and performance. | Gou Jie Zhang Chonghong Song Yin Yang Yitao Ding Zhaonan Yi Xiaoyan Xie Haizhong Yang Hua Wang Hongmei Wang Xiaozhi | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
| 19 | 3-31 Study on Hardening Caused by He Ion Implantation in Two Kinds of Reduced-activation Ferritic/Martensitic Steels Made in China显示文摘Reduced activation ferritic/martensitic steels (RAFM) are important candidate materials for future nuclear fusion reactors because of their high thermal conductivity, low thermal expansion rate and high resistance to void swelling. The influence of the accumulation of high concentration of helium via the(n, a)nuclear reaction on microstructures and macro-properties of the steels is an important issue limiting the service lifetime of the materials. | Fan Jiaqi Yang Yitao Ding Zhaonan Li Caisheng Zhang Chonghong Xu Yuping Luo Guangnan | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
| 20 | 3-32 Irradiation Hardening of A Domestic Reduced Activation Ferritic/martensitic Steel under High Energy Heavy-ion Bombardment显示文摘As a prime candidate for the structure components of fusion reactors, irradiation resistance of the reduced activation ferritic/martensitic steel (RAFM) has obtained intensive concern. In the present work, irradiation response of a domestic 8%-Cr RAFM was tested at the terminal SFC-T1 of HIRFL. | Ding Zhaonan Yang Yitao Song Yin Zhang Liqing Gou Jie Zhang Chonghong Xu Yuping Luo Guangnan | 2015 | IMP & HIRFL Annual Report2015，，1： | 0 |
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