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| 1 | Suppressing trap states and energy loss by optimizing vertical phase distribution through ternary strategy in organic solar cells显示文摘Suppressing the trap-state density and the energy loss via ternary strategy was demonstrated.Favorable vertical phase distribution with donors(acceptors)accumulated(depleted)at the interface of active layer and charge extraction layer can be obtained by introducing appropriate amount of polymer acceptor N2200 into the systems of PBDB-T:IT-M and PBDB-TF:Y6.In addition,N2200 is gradiently distributed in the vertical direction in the ternary blend film.Various measurements were carried out to study the effects of N2200 on the binary systems.It was found that the optimized morphology especially in vertical direction can significantly decrease the trap state density of the binary blend films,which is beneficial for the charge transport and collection.All these features enable an obvious decrease in charge recombination in both PBDB-T:IT-M and PBDB-TF:Y6 based organic solar cells(OSCs),and power conversion efficiencies(PCEs)of 12.5%and 16.42%were obtained for the ternary OSCs,respectively.This work indicates that it is an effective method to suppress the trap state density and thus improve the device performance through ternary strategy. | Pengqing Bi Shaoqing Zhang Tong Xiao Minghuan Cui Zhihao Chen Junzhen Ren Chaochao Qin Guanghao Lu Xiaotao Hao Jianhui Hou | 2021 | Science China Chemistry2021，64，4： | 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 | 3-8 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 |
| 11 | 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 |
| 12 | 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 |
| 13 | 3-14 Magnetic Properties of SiC-Fe Composite显示文摘SiC ceramics are promising candidate materials for future advanced nuclear energy system, due to the uniqueproperties such as superior high temperature mechanical properties, high temperature chemical inertness and lowneutron capture cross section[1;2]. Furthermore, some transition metals such as Fe, Co and Ni could be introducedinto SiC so that the material obtained magnetic properties[3] and could be conveniently driven by the electromagneticforce. Compared with Co and Ni, Fe owns the lowest neutron capture cross section. In view of this consideration,the metal matrix composite SiC-Fe was designed. | Liu Chao Cui Minghuan Sun Jianrong Wang Zhiguang | 2014 | IMP & HIRFL Annual Report2014，，1： | 0 |
| 14 | 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 |
| 15 | 载能离子辐照316L不锈钢的力学性能及微观结构表征显示文摘The 316L type austenitic stainless steel as main structural materials,are widely used for the fission reactors for more than 30 years.Besides,316L steel has been chosen as primary structural material for future advanced nuclear facility,such as fusion reactor and Accelerator Driven Subcritical(ADS)system[1].In this work,one set of the 316L steel specimens were irradiated with H and Heions to the doses of 1.01017 and 1.01018ioncm��2,at room temperature(RT)and 500℃,respectively.Another set of specimens with and without 100 ppm He pre-implantation were irradiated with Feions to the doses of 10,20 and 50 dpa at 450℃and 600℃,respectively. | Shen Tielong Jin Peng Zhu Yabin Cui Minghuan Wei Kongfang Chai Jianlong Guo Yawei Zhang Tongmin Li Jinyu Wang Zhiguang | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 16 | 500 keV氦离子注入钨引起的损伤研究显示文摘Tungsten(W)is a promising candidate as the plasma-facing materials in fusion reactors,which suffers from helium(He)from the nuclear reaction,etc.The optimized dispersion-strengthened tungsten possesses better mechanical strength and toughness and is more resistant to irradiation than pure tungsten.However,there are few researches on the defects and properties in irradiated dispersion-strengthened tungsten,and the effects of dispersoids on the irradiation-induced defects are still unclear. | Cui Minghuan Shen Tielong Wang Zhiguang | 2018 | IMP & HIRFL Annual Report2018，，1： | 0 |
| 17 | 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 |
| 18 | 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 |
| 19 | 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 |
| 20 | 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 |
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