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| 1 | Investigation of swelling induced by heavy ion and neutron irradiation in SiC显示文摘 | Hang Zang Daxi Guo Tielong Shen Chaohui He Zhiguang Wang Lilong Pang Cunfeng Yao Tao Yang | 2013 | Journal of Nuclear Materials . 2013 (1-3)2013，，1： | 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 | Structural and Magnetic Properties Studies on Swift Heavy Ion (SHI) Irradiated Fe-based Amorphous Alloys显示文摘 | Sun Jianrong Wang Zhiguang Jin Yunfang Zhu Yabin Shen Tielong Yao Cunfeng Pang Lilong Wei Kongfang Sheng Yanbin Chang Hailong Zhang Hongpeng Wang Ji Zhu Huiping | 2011 | IMP & HIRFL Annual Report2011，，1： | 0 |
| 5 | 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 |
| 6 | 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 |
| 7 | 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 |
| 8 | 3 - 3 Modifications of Iron-based Amorphous Alloys under Swift Heavy Ions (SHI) Irradiation Investigated by 57Fe Mossbauer Spectrometry显示文摘 | Sun Jianrong Wang Zhiguang Yao Cunfeng Shen Tielong Pang Lilong Zhu Yabin Sheng Yanbin Ma Yizhun Gou Jie Wei Kongfang Li Fashen | 2010 | IMP & HIRFL Annual Report2010，，1： | 0 |
| 9 | 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 |
| 10 | 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 |
| 11 | 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 |
| 12 | 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 |
| 13 | 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 |
| 14 | 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 |
| 15 | 3-17 Corrosion Studies of MAX Phase in Liquid Pb-Bi Alloy显示文摘As one of candidates for the fuel cladding or structure material used in fourth generation fission and fusiondemonstrate reactor, MAX phase has the properties of both ceramic and metal, such as high melting point, hightemperaturestability, good erosion resistance and radiation-damage tolerance[1;2]. Max phase is a series of ceramicsof nanolamellar and hexagonal structure. M represents transition element. A represents the third or fourth maingroup element. X represent N and C. In the design of lead-cooled fast reactor, it is required that the materialshould endure the corrosion of liquid Pb-Bi alloy. Therefore, understanding of the oxide layers and their growthmechanisms in LBE is fundamentally important for the development of candidate materials. | Deng Tianyu Sun Jianrong Wang Zhiguang Song Peng Shen Tielong Pang Lilong Zhu Yabin Cui Minghuan Wang Ji Zhu Huiping Wang Dong Du Yangyang He Wenhao | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 16 | 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 |
| 17 | Ti_(3)AlC_(2)材料辐照后空位型缺陷的演化显示文摘MAX phase material is a layered ternary compound with the chemical formula Mn+1AXn.M represents the transition metal the A represents A-group element and X is the nitrogen or carbon.We take Ti_(3)AlC_(2) as the sample.This material exhibits a combination of the attributes of both metals and ceramics[1].As a result,it has been considered as potential materials for use in current and future nuclear applications.Numerous researches have been focused on the phase transformation progress and anti-amorphization trait of this material[2,3].However,few researches have reported the behavior of vacancy defects after irradiation.We use the PAT and DBS technique to investigate this issue and try to find the relationship among the density of vacancy type defects,phase transformation,the irradiation fluence and temperature. | Deng Tianyu Sun Jianrong Wang Zhiguang Pang Lilong Shen Tielong Zhu Yabin Cui Minghuan Tai Pengfei | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 18 | Infuence of Plasma Nitrided on the Mechanical Properties on 316L Steel under Low Temperature Conditions显示文摘Surface modification of 316L austenitic stainless steel was performed by glow plasma nitriding at low temperature The surface morphology and microstructure of the nitrided samples were investigated by means of scanning electron microscopy(SEM)and X-ray difraction(XRD)method. | Lv Wenquan Pang Lilong Tai Pengfei Shen Tielong | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 19 | Study on Plating Magnetic Coating on the Surface of Tungsten Alloy Ball显示文摘At present,a novel design-particle flowing target,which is a fluidized solid target consisting of a large number of metal balls,has been proposed for the high power spallation target of CiADS.This sort of target has good neutron performance and good compatibility with structural materials,and can continuous flow with conducting of gravity. | Pang Lilong Tai Pengfei Wang Zhiguang Lv Wenquan | 2019 | IMP & HIRFL Annual Report2019，，1： | 0 |
| 20 | 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 |
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