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| 1 | The System Performance for TD-LTE with Precoded MIMO显示文摘This paper introduces the rank adaptive precoded MIMO in TD-LTE downlink system. | Zhang Yong Jiang Dajie Shen Xiaodong Han Lu Liu Guangyi Cui Cunfeng Huang Yuhong | 2008 | China Communications2008，5，3： | 1 |
| 2 | Nuclear Physics and Interdiscipline——Modification of Structure and Optical Band-gap of nc-Si : H Films with Ion Irradiation显示文摘 | Zhu Yabin Wang Zhiguang Sun Jianrong Yao Cunfeng Shen Tielong Chang Hailong Li Bingsheng Wei Kongfang Pang Lilong Sheng Yanbin Cui Minghuan Zhang Hongpeng Li Yuanfei Wang Ji Zhu Huiping | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 3 | Micro-raman Study on a-Si, nc-Si and c-Si irradiated by 6 MeV Bi-ions显示文摘 | Zhu Yabin Wang Zhiguang Sun Jianrong Yao Cunfeng Shen Tielong Chang Hailong Li Bingsheng Wei Kongfang Pang Lilong Sheng Yanbin Cui Minghuan Zhang Hongpeng Li Yuanfei Wang Ji Zhu Huiping | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 4 | Modification of LiTaO3 Crystal by Low-energy He-ion Implantation显示文摘 | Pang Lilong Wang Zhiguang Jin Yunfan Sun Jianrong Yao Cunfeng Cui Minghuan Wei Kongfang Shen Tielong Sheng Yanbin Zhu Yabin Li Yuanfei Wang Ji Zhu Huiping | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 5 | Investigation of Structural Modification of Lithium Tantalate Crystal Implanted by Low Energy H-ion显示文摘 | Pang Lilong Wang Zhiguang Yao Cunfeng Li Yuanfei Sun Jianrong Li Bingsheng Shen Tielong Cui Minghuan Wei Kongfang Sheng Yanbin Zhu Yabin Wang Ji Zhu Huiping | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 6 | Hardening of Tungsten Induced by 200 keV Helium Ions显示文摘 | Cui Minghuan Wang Zhiguang Yao Cunfeng Shen Tielong Li Bingsheng Sun Jianrong Pang Lilong Sheng Yanbin Zhu Yabin Li Yuanfei | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 7 | Development of a Static LBE Corrosion Equipment显示文摘 | Wang Ji Wang Zhigang Yao Cunfeng Sun JianRong Sheng Yanbin Cui Minghuan Li yuanfei Zhu Huiping Zhang Hongpeng Li Bingsheng Chang Hailong | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 8 | 3 - 19 Preparation and Ultra-long PVP Assembly of Aligned Nanofibers显示文摘 | Zhou Ming Sun Jianrong Yao Cunfeng Gou Jie Sheng Yanbin Shen Tielong Zhu Yabin Pang Lilong Cui Minghuan Wang Zhiguang Xie Erqing | 2010 | IMP & HIRFL Annual Report2010，，1： | 0 |
| 9 | 3-4 Compatibility Tests of SIMP and T91 Steels in Static LBE显示文摘Because of their good mechanical properties under irradiation up to 500 ?C, ferritic/martensitic steels are consideredto be the promising structural materials for advanced nuclear reactors. However, severe corrosion of structuralmaterials occurs in the presence of LBE in advanced nuclear reactors, especially at high temperature[1]. Therefore,the selection of the structural material exposed to LBE is an extremely complex problem and compatibility testsare required. | Zhang Hongpeng Yao Cunfeng Wang Zhiguang Wang Ji Zhu Huiping Sheng Yanbin Sun Jianrong Chang Hailong Wang Dong Li Bingsheng Shen Tielong Zhu Yabin Pang Lilong Cui Minghuan Wei Kongfang | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 10 | 3-5 An Experiment Setup for Synergetic Effect of Irradiation and LBE in IMP显示文摘Due to its unique properties, such as favorable neutronic characteristic, low melting point(~125 ?C) and highboiling point (> 1 600 ?C), good natural circulation and chemical inertness with water and air (unlike sodium), etc,lead bismuth eutectic (LBE) has been considered as perspective coolant and spallation target for accelerator drivensystems (ADS)[1;2]. The spallation structural materials of ADS will be long-term irradiated with fast neutrons whilesimultaneous being contact with LBE coolant. In the past few decades, irradiation or LBE corrosion behaviors invarious of materials have been massively investigated for the purpose of developing ADS. However, there are onlya few experiment data on the combined effect of irradiation and LBE corrosion on structural materials due to lackof related experimental setups[3;4]. Such tests are not only essential for ensuring the safety and reliability of ADS,but also necessary for building a database for licensing any materials for use in LBE cooled nuclear systems. | Yao Cunfeng Wang Zhiguang Zhang Hongpeng Sheng Yanbin Chang Hailong Sun Jianrong Wei Kongfang Li Bingsheng Shen Tielong Pang Lilong Zhu Yabin Wang Dong Du Yangyang Wang Ji Cui Minhuan Zhu Huiping Liu Chao Yang Yongwei Fan Deliang | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 11 | 3-8 Thermal Desorption and Surface Modification Induced by Helium Implantation in Tungsten显示文摘Plasma-facing materials (PFMs) for a fusion reactor suffer hydrogen/helium plasma bombardment, neutronirradiation and high temperature, etc. Tungsten is a promising candidate PFM due to its low sputtering yield forthe light elements, high thermal conductivity, high mechanical strength, and high melting point. Helium couldbe introduced by helium bombardment and neutron irradiation and trapped in tungsten at different sinks. It ispossible that the trapped helium atoms re-emit to the core plasma due to thermal desorption which affects thesafety. In this work, the thermal desorption behavior of helium implanted into tungsten at different temperatureswas investigated. | Cui Minghuan Wang Zhiguang Yao Cunfeng Pang Lilong Shen Tielong Sun Jianrong Zhu Yabin Sheng Yanbin Zhu Huiping Wang Ji Zhang Hongpeng | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 12 | 3-9 Mechanical Properties Studies on High-energy Kr-ion Irradiated Corrosion Layer Fe3O4显示文摘The RAFM (Reduced Activation Ferritic/Martensitic) steel is considered as one of the promising candidatestructural materials for LFRs (Lead alloy-cooled Fast Reactors) and ADS (Accelerator Driven Sub-critical system),and its compatibility with liquid metal and radiation-resistant properties have been extensively studied because ofthe requirements of reliability and safety of the blanket[1]. A number of corrosion experiments of RAFMs (Eurofer97, T91 and 316L, etc.) in liquid LiPb alloy have been investigated, and the corrosion results show that these Febasedsteels suffered more serious corrosion attack from 480 to 550 ?C, and the corrosion layer is made of the oxidelayer (Fe3O4 and CrxFe3?xO4) at steels' surface. Generally speaking, during the stage degeneration of material, theformation of corrosion layer is one of the important features of the process[2]. Cracking, blistering, embrittlementand other changes in materials may be induced by corrosion layers, and the corrosion layers have independentcompositions, structures and radiation-resistant properties with distinguished from the alloy matrix. In a word, inorder to further clarify the applicability of Fe-based structural materials in nuclear facilities, we should study notonly the RAFM steel itself but also its corrosion layer (Fe3O4, mainly). So we report on modifications of mechanicalproperties of Fe3O4 corrosion layer irradiated with high-energy ion. | Sun Jianrong Song Peng Zhang Hongpeng Chang Hailong Yao Cunfeng Pang Lilong Zhu Yabin Cui Minghuan Wang Ji Zhu Huiping Wang Zhiguang | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 13 | 3-10 Swift Heavy Ion Induced Modification of Fe/Cu Multilayers显示文摘When swift heavy ion (SHI) passes through metallic multilayers, the kinetic energy of the ion is mainly depositedto target electron subsystem (electronic energy loss, Se) by the inelastic collisions involving excitation and ionizationof the target atoms, which could induce atomic displacements and modify the interfacial structure [1?6]. Therefore,through the study of the process of the interfacial atoms diffusion induced by SHI irradiation, we could explore thepossible mechanism of atomic displacement induced by swift heavy ion irradiation. | Wei Kongfang Li Bingsheng Zhu Yabin Zhu Huiping Gao Ning Shen Tielong Yao Cunfeng Sun Jianrong Pang Lilong Cui Minghuan Chang Hailong Wang Ji Wang Dong Sheng Yanbin Zhang Hongpeng Wang Zhiguang Gao Xing | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 14 | 马氏体钢中的离子辐照和LBE腐蚀协同效应显示文摘Lead bismuth eutectic(LBE)has been proposed as a core coolant for Lead-cooled Fast Reactor(LFR)due to its several advantages,low melting point,chemically inert and good natural circulation[1].However,the LFR presents a harsh environment where the core components and mainly steels will suffer not only from the irradiation damage produced by neutrons,but also from the corrosion induced by the liquid LBE.Over the past decades,the irradiation effect and corrosion mechanism of LBE in both ferritic/martensitic alloys and austenitic steels have been investigated separately by both experimental and theoretical approach.However,the synergistic effects of irradiation and LBE corrosion on structural materials have rarely been studied[2,3]. | Yao Cunfeng Wang Zhiguang Zhang Hongpeng Chang Hailong Shen Tielong Zhu Yabin Pang Lilong Cui Minghuan Wei Kongfang Sun Jianrong Sheng yanbin Ma Zhiwei Liu Chao | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 15 | MgAl_(2)O_(4)掺杂对ZTA-MgAl_(2)O_(4)复相陶瓷力学及热学性能影响显示文摘MgAl_(2)O_(4) is a very suitable reinforcing phase owing to the advantageous performance such as high melting point,high strength,high hardness,corrosion resistance and good thermal shock stability.In this paper,the effects of MgAl_(2)O_(4) addition on microstructure and mechanical properties of ZTA-MgAl_(2)O_(4) composite ceramics prepared by Spark Plasma Sintering(SPS)were investigated. | Guo Yawei Chai Jianlong Zhu Yabin Wei Kongfang Li Shufeng Shen Tielong Yao Cunfeng Cui Minghuan Wang Zhiguang | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 16 | SiC含量对ZTA和ATZ复相陶瓷力学及热学性能的影响显示文摘Oxide/carbide composite ceramics were prepared by spark plasma sintering(SPS)usingα-Al2O3,ZrO2andβ-SiC powders as raw materials.The effects of SiC doping on the microstructure,mechanical and thermal properties of zirconia toughened alumina(ZTA)and alumina toughened zirconia(ATZ)based composites were investigated.Fig.1 shows the effect of SiC content on the mechanical properties of the complex phase ceramics.With the increase of SiC content,the bending strength of SiC-ATZ80mol%composite phase ceramics decreased from 992 to 761 MPa.The reason is that the thermal expansion mismatch between the SiC and the substrate induces thermal stress,resulting in the different shrinkage between the substrate and the SiC affecting its strength. | Chai Jianlong Guo Yawei Zhu Yabin Li Shufeng Shen Tielong Yao Cunfeng Cui Minghuan Wang Zhiguang | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 17 | 颗粒流散裂靶样机粉尘测试显示文摘The gravity-driven dense granular flow target(DGT)is a new type of concept of high power spallation target proposed to satisfy ultra-high beam power in ADS system[1].Using gravity-driven dense solid particle flow as target material and heat carrier,the essential idea of the granular flow target is to treat the power deposit offline easily,while avoiding many fatal defects,such as unstable flow of liquid lead and bismuth(LBE),material corrosion and abrasion,chemical toxicity leakage.A potential solution is provided,in order to meet the ultimate challenge posed by the ADS system with tens of MW beam power. | Sheng Yanbin Wang Zhiguang Sun Jianrong Tai Penfei Pang Lilong Gao Xing Cui Minghuan Zhang Hongpeng Chang Hailong Li Bingsheng Wei Kongfang Shen Tielong Zhu Yabin Yao Cunfeng Luo Peng | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 18 | 透射电子显微镜研究低能高剂量氦离子辐照引起非晶6H-SiC微观结构演化过程显示文摘Silicon carbide(SiC)is regarded as an important material in nuclear energy system and semiconductor industry,because of its excellent physical,electronic and optical properties.It is inevitable that dense atomic He atoms produced by(n,)nuclear transmutation reaction.Due to the low solubility of He atoms in SiC,He atoms are easy to be trapped by vacancies to form helium-vacancy clusters.After thermal annealing,helium atoms will escape from vacancies,to form cavities.In semiconductor technology,He implantation-induced cavities have lots of important applications.Therefore,the study of He-implanted SiC is critical.He-implantation-induced cavities have been extensively investigated.He-implantation-induced dislocation loops also have been investigated.Chen et al.observed interstitial-type dislocation loops associated with He bubbles due to the release of bubble interior pressure via emitting interstitials[1].These interstitials agglomerate into dislocation loops.It is consistent with previous results observed in the case of He-implanted 6H-SiC[2].What’s more,Barbot et al.regarded that the growth of the Frank loops lead to the formation of stacking faults,which do not result from the agglomeration of interstitials[3]. | Li Bingsheng Han Yi Wang Zhiguang Wei Kongfang Shen Tielong Sun Jianrong Yao Cunfeng Gao Ning Gao Xing Pang Lilong Zhu Yabin Chang Hailong Cui Minghuan Luo Peng Sheng Yanbin Zhang Hongpeng Fang Xuesong Zhao Sixiang Jin Jin Huang Yuxuan Liu Chao Tai Pengfei Wang Dong He Wenhao Qi Ming | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 19 | Fe和He离子注入如TiALC_(2)研究显示文摘In this work,we have used the Fe-ion irradiation and He-ion implantation successively(Fe+He)to produce an environment with lower appm He/dpa than the single He-ion implantation.Samples of Ti_(3)AlC_(2) were irradiated by 3.5 MeV Fe-ions to the fluences of 1.0×10^(16) ions/cm^(2),to produce amount of defects in advance.Then,irradiated samples were implanted with 500 keV He-ion to the fluence of 1.0×10^(17) ions/cm^(2).We have used the SRIM 2008 code[1]with the“Kinchin-Pease quick calculation”mode to simulate damage caused by Fe-ion irradiation and He-ion depositional concentration,as shown in Fig.1.The damage near the peak is about 10 dpa. | Pang Lilong Li Bingsheng Shen Tielong Gao Xing Fang Xuesong Gao Ning Yao Cunfeng Wei Kongfang Cui Minghuan Sun Jianrong Chang Hailong He Wenhao Wang Zhiguang | 2017 | IMP & HIRFL Annual Report2017，，1： | 0 |
| 20 | 3 Nuclear Physics and Interdiscipline——3 - 1 Modification of Structure and Optical Band-gap of nc-Si : H Films with High-energy Kr-ions显示文摘 | Zhu Yabin Wang Zhiguang Yao Cunfeng Sun Jianrong Shen Tielong Wei Kongfang Wang Ji Pang Lilong Cui Minghuan Li Yuanfei Zhu Huiping Song Peng Wang Dong | 2012 | IMP & HIRFL Annual Report2012，，1： | 0 |
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