研究动态

核科学与工程系主要针对国际热核聚变实验堆计划（ITER）、中国聚变工程实验堆（CFETR）、第四代（GenIV）先进核能系统、核燃料循环等国家重大需求，紧密围绕等离子体物理与聚变工程、铅基反应堆堆物理与设计、反应堆热工水力与核安全、先进核燃料/核材料制备和评价、乏燃料后处理与放射性废物处理、以及辐射防护与核医学物理等方向开展研究。

 

主要科研平台：

（一）磁约束聚变数值模拟平台

图片1

平台用于支持磁约束聚变物理研究的数值模拟。平台共70个计算节点，1680CPU核，理论峰值计算能力70万亿次/秒。平台集成了主流的磁约束聚变物理数值模拟软件，主要包括：EFIT（平衡）；GATO、ELITE、CLT（稳定性）；TGLF、BOUT++（湍流）；TGYRO、ONETWO、SOLPS（输运）。

目前平台用户来自国内外主要聚变研究单位，包括中国科学技术大学、中科院等离子体物理研究所，核工业西南物理研究院、华中科技大学、北京大学、大连理工大学、深圳大学、合肥工业大学、美国通用原子能公司、利弗莫尔国家实验室、圣彼得堡彼得大帝理工大学等。

（二）磁约束聚变工程设计平台

    平台基于GPU虚拟化技术以及ICA协议实现云端的工程设计分析，以及虚拟现实系统提供设计讨论及评审功能。平台安装了ENOVIA、CATIA、DELMIA、ANSYS、Abaqus、Maple、EnSight等主流的工程管理、设计、分析软件，以及多款自主研发的中子学分析相关软件，能够有效支持聚变装置设计与分析。

（三）直线等离子体实验装置

    紧凑型直线等离子体实验装置，主要用于材料的等离子体辐照实验研究。采用直热式六硼化镧阴极产生高密度稳态等离子体。

（四）托卡马克等离子体诊断系统

依托国内EAST，HL-2A两大托卡马克装置，建成了超快电荷交换复合光谱、电荷交换复合光谱、束发射光谱、快离子Dα、多色喷气成像、相衬成像等多套先进光学诊断系统。

（五）核材料高能中子辐照损伤研究平台

    多年来与长期紧密合作单位瑞士PSI研究所有长期合作协议和辐照研究项目，基于PSI的瑞士散裂中子源SINQ（目前世界上唯一可用于核材料辐照的强流高能中子源），已积累了大量中国主流先进核材料中子辐照实验样品，并可利用其完备的辐照后测试分析半热室，可进行国际主流先进核材料的高能中子辐照损伤研究。

（六）核材料损伤断裂力学研究平台

    研发了引入三维数字图像相关3D-DIC方法的核材料高温（真空/气氛保护）断裂/损伤力学及原位观察试验平台，可实现应变测量和裂纹演化原位观察的同步分析，可以研究核材料开裂应力变化及损伤/断裂微观力学行为协同作用。

核材料多尺度模拟研究平台：具备原子尺度模软件（第一性原理VASP及分子动力学LAMMPS）、介观团簇动力学软件CDCode、宏观有限元模拟软件（ANSYS及ABAQUS等）等料多尺度模拟软件平台和模拟计算服务器，可进行核材料中子辐照损伤及损伤断裂力学的模拟研究。

 

3万居里60Co γ射线源

6

0Co 放射源装置（水井式）

（七）辐射防护研究平台


PIPS型α探测器ELEMENT 2型ICP-MS装置
GR5021 N型高纯锗γ谱仪超低本底液体闪烁计数器


 

研究方向：

一、核聚变物理与工程

1、核聚变堆物理与工程技术：等离子体物理；先进诊断技术；中子学，聚变堆设计等。

通过数值模拟和EAST和HL-2A/2M等实验装置，重点研究先进的偏滤器位形、热和粒子排除、杂质屏蔽、边界热脉冲缓解新方法及机理、输运垒的结构形成机理，与高性能芯部等离子体相兼容的高效稳定的热与粒子排除控制手段。基于EAST和HL-2A/2M等实验装置，开展湍流和输运相关物理实验研究，包括高-低约束模转换机制、高比压、高能粒子模、剪切流、电磁湍流等。

研制超快电荷交换复合光谱、电荷交换复合光谱、束发射光谱、快离子Dα、多色喷气成像、相衬成像等多套先进光学诊断系统，应用到EAST和HL-2A/2M托卡马克物理实验。

先进偏滤器的结构设计以及热工水力;中子学软件开发以及聚变堆中子学，聚变堆包层结构材料活化以及辐射防护等中子学设计;聚变堆燃料循环的排灰气系统设计。

2、等离子体与材料相互作用：材料辐照研究；低温等离子体及诊断技术应用。

通过实验与理论模拟相结合，研究高能量粒子与材料表面非线性相互作用的机理、离子和中子辐照损伤，材料表面和结构改性、以及聚变燃料氘氚滞留和渗透等行为机理。

自主大型边界综合模拟程序研发，获得预测未来聚变堆等离子体与壁相互作用基本行为的能力。深入研究边缘等离子体物理、原子分子物理、杂质的产生、迁移和输运物理过程和机制。

低温等离子体污水处理、空气净化，等离子体航天大比冲推进技术等等。

主要科研项目和成果：

2011年以来，团队成员主持完成中国科学技术部 国家磁约束核聚变能发展研究专项2项，国家磁约束核聚变能发展研究青年人才项目1项，国家自然科学基金面上1项，国家自然科学基金专项1项，国家自然科学基金青年基金1项，安徽省自然科学基金青年项目1项，合肥物质科学技术中心方向项目培育基金创新项目1项，中央高校基本科研业务费专项2项以及若干其他项目等，参与完成国家磁约束核聚变能发展研究专项2项。目前在研究项目有国家自然科学基金重点1项和面上2项；国家磁约束核聚变能发展研究专项课题1项；国家磁约束核聚变能发展研究青年人才项目1项；重点研发项目子课题1项；国家磁约束核聚变能发展研究专项子课题3项等。

已培养的研究生几十名。有3名博士生获得中科院院长优秀奖，1名硕士生获得中科院院长优秀奖，1名博士生2018年获得校优秀博士论文。

 

部分论文：

1.       Simulation Study of the Impurity Radiation in the Quasi-Snowflake Divertor with Ar Seeding for CFETR, Nuclear Fusion 59, 096049 (18pp) 2019.

2.       Asymmetry of parallel flow on LHD, Nuclear Fusion 59(10), 106036(11pp) 2019.

3.       Validation of Alfvén Eigenmode simulations on DIII-D and Projection for CFETR scenario, Nuclear Fusion 59(6), 066005(14pp) 2019.

4.       Modeling of inter- and intra-edge-localizedmode tungsten erosion during DIII-D H-mode discharges, Nuclear Fusion 59, 126018(13pp) 2019.

5.       The time-dependent simulation of CFETR baseline steady-state scenarios, Nuclear Fusion, 2018

6.       Validating the energy transport modeling of the DIII-D and EAST ramp up experiments using TSC, Nuclear Fusion57, 2017.

7.       Edge turbulence and divertor heat flux width simulations of Alcator C-Mod discharges using an electromagnetic two-fluid model, Nuclear Fusion 57, 2017.

8.       Overview of the present progress and activities on the CFETR [J] Nuclear Fusion57, 2017.

9.       Evaluation of performance for the EAST upgraded divertor targets during type I ELMy H-mode, Nuclear Fusion 56, 2016.

10.     Suppression of blister formation and deuterium retention on tungsten surface due to mechanical polishing and helium pre-exposure Nuclear Fusion45, 669-674, 2005

11.     Overview of ASDEX Upgrade results - development of integrated operating scenarios for ITER, Nuclear Fusion 45, 2005.

12.     Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths (Invited talk of APS DPP), Physics of plasmas 25, 2018.

13.     Modeling of divertor geometry effects in China fusion engineering testing reactor by SOLPS/B2-Eirene, Physics of Plasmas, 21, 2014.

14.     Effect of Space-Charge Limited Emission on Measurements of Plasma Potential Using Emissive Probes, Physics of Plasmas 7, 2000.

15.     Heat flows through plasma sheath (Invited talk of APS DPP), Physics of Plasmas 5, 1998

16.     Nonlinear interactions between high heat flux plasma and electron- emissive hot material surface, Physics of Plasmas 3, 1996

17.     Effect of energy dependent cross-section on flow velocity measurements with charge exchange spectroscopy in magnetized plasma, Physics Letters A 383, 2019.

18.     Developments of Divertor Target-Imbedded Langmuir Probes for W7-X, Contributions to Plasma Physics 50, 2010.

19.     Space-charge limited current from plasma facing material,(Invited talk of 9th PET Workshop, 2003) Contributions to Plasma Physics 44, 2004.

20.     2-D PIC simulation on Space-Charge Limited Emission current from Plasma-Facing components, Contributions to Plasma Physics 40, 2000.

21.     Synthesis of UO2 nanocrystals with good oxidation resistance in water at room temperature, Journal of Nuclear Materials512, 2018.

22.     Evaluation of target-plate heat flux for a possible snowflake divertor in CFETR using SOLPS, Journal of Nuclear Materials463, 2015.

23.     Tungsten limiter tests in ASDEX Upgrade, Journal of Nuclear Materials, 2005.

24.     Interaction of ELMs and fast particles with in vessel components in ASDEX Upgrade, Journal of Nuclear Materials 337-339, 2005.

25.     Characteristic changes of deuterium retention on tungsten surface due to low-energy helium plasma ore-exposure, Journal of Nuclear Materials337-339, 2005.

26.     Formation mechanism of bubbles and holes on tungsten surface with low-energy and high-flux helium plasma irradiation in NAGDIS-II, Journal of Nuclear Materials 329-333, 2004.

27.     Blister formation on tungsten surface under low energy and high flux hydrogen plasma irradiation in NAGDIS-I, Journal of Nuclear Materials313-316, 2003.

28.     Incident ion energy dependence of bubble formation on tungsten surface with low energy and high flux helium plasma irradiation, Journal of Nuclear Materials 313-316, 2003.

29.     Experimental evaluation of space charge limited emission current from tungsten surface in high density helium plasma, Journal of Nuclear Materials 313-316, 2003.

30.     Hot Spot Formation on Electron-Emissive Target Plate with Plasma Potential Variation across Magnetic Field, Journal of Nuclear Materials 266-269, 1999.

31.     Study of hot tungsten emissive plate in high heat flux plasma on NAGDIS-I, Journal of Nuclear Materials 241-243, 1997.

32.     Modifications of Tungsten Surface Irradiated by Low Energy and High Flux Helium Plasma, Journal of Plasma and Fusion Research Series, 3, 2000.

33.     Effects of low energy and high flux Helium/Hydrogen plasma irradiation on tungsten as plasma facing material, Plasma Science & Technology 7(3), 2005.

34.     CFETR integration design platform: overview and recent progress, FusionEngineering and Design,2019.

35.     Tomographic reconstruction for a tangentially viewing visible light imaging diagnostic on EAST, FusionEngineering and Design 131, 2018.

36.     Simulation study of the radiative divertor with argon seeding for CFETR phase II, FusionEngineering and Design, 2018.

37.     The comparison between near-infrared and traditional CO 2 phase contrast imaging on HL-2A tokamak. FusionEngineering and Design n133, 2018.

38.     Evaluation of electromagnetic interaction between the PCI platform and HL-2A tokamak, FusionEngineering and Design 126, 2018.

39.     Parameter study on helium cooled ceramic breeder blanket neutronics with CFETR integration design platform, FusionEngineering and Design, 2017.

40.     Development of ramp up design workflow on CFETR Integrated Design Platform, FusionEngineering and Design, 2017.

41.     Cyclic loading tests on ceramic breeder pebble bed by discrete element modeling,FusionEngineering and Design 118, 2017.

42.     Design of phase contrast imaging on the HL-2A tokamak, FusionEngineering and Design, 2017.

43.     Evaluation of CFETR key parameters with different scenarios using system analysis code, FusionEngineering and Design 112, 2016.

44.     Thermo-mechanical and damage analyses of EAST carbon divertor under type-I ELMy H-mode operation, FusionEngineering and Design 105, 2016.

45.     Assessment of the W7-X high heat flux divertor with thermo-mechanical analysis, FusionEngineering and Design 109, 2016.

46.     Evaluation of CFETR key parameters with different scenarios using system analysis code, FusionEngineering and Design 112, 2016.

47.     Data exchange between zero dimensional code and physics platform in the CFETR integrated system code, FusionEngineering and Design 109, 2016.

48.     Estimation of peak heat flux onto the targets for CFETR with extended divertor leg,FusionEngineering and Design 109, 2016.

49.     DEM-CFD simulation of purge gas flow in a solid breeder pebble bed, FusionEngineering and Design 113, 2016.

50.     Toroidal charge exchange recombination spectroscopy on EAST, FusionEngineering and Design, 2015.

51.     Preliminary results of absolute wavelength calibration of imaging X-ray crystal spectrometer on EAST, FusionEngineering and Design, 2015.

52.     Engineering design for the magnetic diagnostics of Wendelstein 7-X, FusionEngineering and Design 100, 2015.

53.     Concept design of the CFETR central solenoid, FusionEngineering and Design, 2015.

54.     Engineering conceptual design of CFETR divertor, FusionEngineering and Design, 2015.

55.     Concept design on RH maintenance of CFETR Tokamak reactor, FusionEngineering and Design, 89, 2014.

56.     Concept design of CFETR superconducting magnet system based on different maintenance ports, FusionEngineering and Design 88, 2013.

57.     Thermal analysis of the Mirnov coils of Wendelstein 7-X, FusionEngineering and Design 88, 2013.

58.     Thermo-mechanical analysis of Wendelstein 7-X plasma facing components, FusionEngineering and Design 88, 2013.

59.     The structure analysis of ITER cryostat based on the finite element method, FusionEngineering and Design88, 2013.

60.     Thermo-mechanical analysis of the Wendelstein 7-X divertor, FusionEngineering and Design86, 2011.

61.     Thermo-mechanical analysis of retro-reflectors for interferometry and polarimetry in W7-X, Engineering and Design 86, 2011.

62.     Designs of Langmuir probes for W7-X, FusionEngineering and Design 86, 2011.

63.     Thermo-mechanical analysis of plasma facing components of diagnostics in the Wendelstein 7-X stellarator, FusionEngineering and Design 84, 2009.

64.     FE Simulation of Wendelstein 7-X cryostat System, FusionEngineering and Design 84, 2009.

65.     Structural analysis of W7-X: Overview, FusionEngineering and Design 84, 2009.

66.     Progress in the design and development of a test divertor (TDU) for the start of W7-X operation, FusionEngineering and Design 84, 2009.

67.     Upgrade of X-ray crystal spectrometer for high temperature measurement using neon-like xenon lines on EAST. Review of Scientific Instruments89, 2018.

68.     Development of wavelength calibration techniques for high-resolution x-ray imaging crystal spectrometers on the EAST tokamak. Review of Scientific Instruments 89(10), 2018.

69.     Influence of neutral beam attenuation on beam emission spectroscopy and charge exchange recombination spectroscopy, Review of Scientific Instruments 89, 2018.

70.     Development of beam emission spectroscopy diagnostic on EAST, Review of Scientific Instruments 88, 2017.

71.     Fast-ion D-alpha spectrum diagnostic in the EAST, Review of Scientific Instruments 87, 2016.

72.     Measurement of helium-like and hydrogen-like argon spectra using double-crystal X-ray spectrometers on EAST, Review of Scientific Instruments 87, 2016.

73.     Upgrades of poloidal and tangential x-ray imaging crystal spectrometers for temperature and rotation measurements on EAST, Review of Scientific Instruments 87, 2016

74.     Improved spatial calibration for the CXRS system on EAST, Review of Scientific Instruments 87, 2016.

75.     Upgrades of imaging x-ray crystal spectrometers for high-resolution and high-temperature plasma diagnostics on EAST, Review of Scientific Instruments, 85, 2014.

76.     Development of the charge exchange recombination spectroscopy and the beam emission spectroscopy on the EAST tokamak, Review of Scientific Instruments, 85, 2014.

77.     Preparations for the motional Stark effect diagnostic on EAST, Review of Scientific Instruments, 85, 2014.

78.     Diagnostic developments for quasicontinuous operation of the Wendelstein 7-X stellarator, Review of Scientific Instruments 79, 2008.

79.     DNS of turbulent mixed convection over a vertical backward-facing step for lead-bismuth eutectic, International Journal of Heat and Mass Transfer, 127, 2018.

80.     Neutronics Analysis of Helium Cooled Ceramic Breeder Blanket with S-shaped Lithium Zone and Cooling Plate for CFETR. IEEE Transactions on Plasma Science, 46, 2018.

81.     The Influence of Divertor Plasma Parameter on Tungsten Screening in High Recycling Regime for CFETR, IEEE Transactions on Plasma Science, 46, 2018.

82.     Extreme Ultraviolet Spectroscopy Applied to Study RMP Effects on Core Impurity Concentration in EAST, IEEE Transactions on Plasma Science, 46, 2018.

83.     Development of CFETR Integration Design Platform: Modular Structure, IEEE Transactions on Plasma Science, 45, 2017.

84.     The Integration Platform Development of System Code for CFETR. Transactions on Plasma Science, 44, 2016.

85.     Piminary Design and Verification of Divertor Module of CFETR System Code, Transactions on Plasma Science, 44, 2016.

86.     Plasma Fusion at 10 MK with Extremely Heated Ions, Plasma Science, IEEE Transactions on Plasma Science, 42, 2014.

87.     Concept design of CFETR tokamak machine, Plasma Science, IEEE Transactions on Plasma Science, 42, 2014.

88.     Concept design of optimized snowflake diverted equilibria in CFETR, IEEE Transactions on Plasma Science, 4, 2014.

 

二、先进反应堆设计和热工安全

1. 小型化先进反应堆设计和关键技术研究

围绕第四代铅基快堆、小型热管堆以及聚变堆包层系统等开展概念设计研究和关键性能分析，包括自然循环铅冷快堆SNCLFR-100方案、驱动循环铅冷快堆M2LFR-1000方案、基于燃料棒与中心冷却热管一体化结构的小型热管堆方案、聚变堆氦冷固态包层系统HCSB设计方案等，针对设计方案开展了中子物理计算、热工水力学计算、燃料性能分析、瞬态事故安全分析等一系列关键性能研究工作。


参考文献：

1. Hongli Chen, Xilin Zhang, Yongsong Zhao, Liankai Cao, Kangli Shi, Haitao Fang, Chong Shen, Haoran Zhang, Qin Zeng. Preliminary design of a medium-power modular lead-cooled fast reactor with the application of optimization methods[J] International Journal of Energy Research, 2018, 42: 3643-3657

2. Chen H, Chen Z, Chen C, et al. Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100[J]. International Journal of Hydrogen Energy, 2016.5, 41(17): 7158-7168.

3. Liankai Cao, Guangliang Yang, Hongli Chen*. Transient sub-channel code development for lead-cooled fast reactor using the second-order upwind scheme[J]. Progress in Nuclear Energy, 2019, 110: 199-212.

4. Chong Shen, Xilin Zhang, Chi Wang, Liankai Cao, Hongli Chen*. Transient safety analysis of M2LFR-1000 reactor using ATHLET[J]. Nuclear Engineering and Technology, 2019-02, 51(1):116-124

5. Hongli Chen, Qingqing Xu, Cheng Jin and Shuai Wang, Model development and electromagnetic analysis of a vertical displacement event for the Chinese Fusion Engineering Test Reactor helium cooled solid blanket, Nuclear Fusion, 2019, 59, 056022.

2. 数值软件开发和多物理场耦合平台研究

开展自主知识产权的计算分析软件开发及验证，已开发粒子输运、热工水力、结构力学、燃料棒行为、系统安全等计算分析软件，搭建了基于统一耦合架构的多物理场耦合数值计算平台KMC，耦合中子物理、热工、力学等多学科专业计算软件和关键设备系统建模，结合后处理数据可视化等建立数值仿真平台，开展对反应堆关键设备状态和全工况系统动态仿真。

参考文献：

1. Cao, Liankai, Zhang, Xilin, Chen, Hongli*, Sub-channel-based multiscale thermal-hydraulic analysis of a medium-power, lead-cooled fast reactor, International Journal of Energy Research, 2020, 44(7): 5305-5319.

2. Zhang, Xilin, Zhang, Kanglong, Sanchez-Espinoza, V.H., Chen, Hongli, Multi-scale coupling of CFD code and sub-channel code based on a generic coupling architecture, Annals of Nuclear Energy, 2020, 141,107353.

3. Zhang, Xuebei, Zeng, Qin, Chen, Hongli*, Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications, Annals of Nuclear Energy, 2020, 139,107243

4. Chi Wang, Liankai Cao, Xilin Zhang, Chong Shen, Hongli Chen*. Development and application of CFD and subchannel coupling analysis code for lead-cooled fast reactor[J]. International Journal of Energy Research, 2019;43,8447-8462.

5. Shuzhou Li, Jingchao Feng, Liankai Cao, Muhammad Shehzad Khan, Hongli Chen*. A thermal neutronics coupling analysis method for lead based reactor core [J]. Annals of Nuclear Energy, 2017.9, 107:82-88.

3. 关键热工水力分析模型实验研究

开展反应堆热工水力关键现象和物理模型实验研究，搭建窄矩形通道板状燃料元件水回路、液态金属铅铋回路及球床热物性测量实验台架等，研究冷却剂流动传热特性、关键物理机理模型和热物性实验参数等。

参考文献：

  1. Xue Zhang, Wenpei Feng, Jie Zhang, Simao Guo, Wenjie Ding, Hongli Chen*，Experimental study on flow instability for downward flow in a narrow rectangular channel with flow pattern transition，International communications in heat and mass transfer. 2020; 114C:104586.

  2. Xue Zhang, Wenpei Feng, Jie Zhang, Hongli Chen*. Simulation study on flow instability in parallel narrow rectangular channels for downward flow with different heating modes[J]. Annals of Nuclear Energy, 2019, 133: 669-77.

  3. Hongli Chen, Shuang Wang, Cheng Jin, Shuai Wang, Qingqing Xu. Theoretical and Experimental Study on Effective Thermal Conductivity of Pebble Beds for Fusion Blanket. Fusion Engineering and Design, 2017, 124: 792-796.

  4. 张杰，陈红丽*，张雪，窄矩形通道两相流动实验回路设计研究[J].核动力工程，2019: 1-5.

  5. 陈红丽，张雪，张杰，流体研究用可视化实验装置，实用新型专利，专利号：202020184198.4.

 

三、先进核燃料与核材料

1、先进裂变核燃料的设计与制备技术研究。研究包括事故容错核燃料（ATF）的组成成分和结构形貌设计，并应用微流体控制技术及3D打印技术等进行ATF的制备技术研究。研究还包括核燃料制备装置的设计与建造，以及核燃料微观结构和物理机械性能相关的基础研究。

磁约束聚变反应堆燃料循环工程设计与研究。研究面向中国聚变工程实验堆（CFETR）大科学工程建设需要，研究内容包括磁约束聚变反应堆的氘氚反应等离子体排出输运系统的设计以及系统各部件制备技术研究。涉及结构材料在极低温环境下的物理机械性能的基础研究以及氢同位素在吸附材料上的吸附-解吸机理研究。

实验室拥有高分辨率显微镜、高速摄像机、扫描电镜、热导率测量仪、气氛及真空烧结炉、手套箱等核燃料研究与分析仪器。

 

发表论文：

1. Dengyu Luo; Lin Guo; Yuan Wang; Pingping Wang; Zhenqi Chang*, Novel synthesis of PVA/GA hydrogel microspheres based on microfluidic technology, Journal of Flow Chemistry, 2020, 10(3), p551-562

2. Tong Song; Yixiao Wang;Zhenqi Chang*; Lin Gu, In-situ fabrication of dispersion nuclear fuel with a core-shell structure, Annals of Nuclear Energy, 2019, 134, p258-262

3. Tong Song; Lin Guo; Ming Chen; Zhenqi Chang*, Influences of heating processes on properties and microstructure of porous CeO2 beads as a surrogate for nuclear fuels fabricated by a microfluidic sol-gel process, Nuclear Engineering and Technology, 2019, 51, p257-262

4. Xiao-Xiao Li, Miao Zhang, Wei-Yue Zhou, Zhen-Qi Chang*, Chung-King Liu, Da-Qiao Meng; Fabrication of the Li2TiO3 tritium breeder pebbles by a capillary-based microfluidic wet process, Journal of Nuclear Science and Technology, 2016, 53(2), p250-257

5. Jun Wei; Xiang Li; Tong Song; Zifan Song; Zhenqi Chang; Daqiao Meng UV-induced polymerization of size-controlled platinum/poly(styrene-divinylbenzene-tri(propylene glycol)diacrylate) hydrophobic catalyst beads in microfluidics, Nuclear Engineering and technology, 2015, 47, p738-745

6. Ya-Ting Yang, Xiang Li, Cao-Fei Fu, Tong Song, Zhen-Qi Chang*, Da-Qiao Meng, Christophe A. Serra; Fabrication of uniform Ce/Eu oxide microparticles by a microfluidic co-sol-gel process as an analog preparation of MA-bearing ceramic nuclear fuel particles, Nuclear Science and Engineering, 2015, 181(2), p216-224

 

2、核材料辐照损伤评价与模拟

长期从事核材料的中子辐照实验、损伤表征及机理研究，研究内容包括核结构钢的散裂/裂变中子和离子/电子辐照实验、辐照硬化/辐照脆化/氦效应、核陶瓷损伤断裂力学等研究。十多年来致力于研究核能材料辐照损伤核心问题—中子辐照损伤，主要进行周期长和难度大的中子辐照实验及后测试分析研究，结合材料数值模拟，研究国内外主流核结构钢（RAFM、316Ti、ODS、W合金、Fe合金、Ni合金等）的中子辐照损伤与氦效应机理，探索中子辐照损伤根源和寿命影响，为核材料研发及反应堆延寿提供实验与理论支持。

科研项目：

  1. 科技部磁约束核聚变能发展专项项目子课题，CFETR国产先进材料小样品中子辐照及结构性能测评，2018YFE0307101，2019-2023，200万

  2. 国家自然科学基金联合基金项目，热-力载荷下陶瓷材料体应力及裂纹演化机制研究，U1730123，2018-2020，70万

  3. 国家自然科学基金面上项目，低活化钢的中子辐照后氦效应机理研究，11375173，2014-2017，80万

  4. 中科院合肥物质科学技术中心创新项目培育基金，先进反应堆结构钢的高能中子辐照损伤研究，2012FXCX004，2013-2014，50万

  5. 中科院战略性先导科技专项项目课题，未来先进核裂变能-ADS嬗变系统-铅铋冷却反应堆-核燃料与关键设备研制，XDA03040300，2011-2013，19000万

  6. 科技部磁约束核聚变能发展专项人才项目，低活化钢的中子辐照损伤机制研究，2011GB108001，2011-2014，300万

  7. 中科院知识创新工程重要方向项目子课题，高辐照场下的材料研究材料-辐照实验与评估方法-中子辐照材料研究，KJCX2-YW-N35，2009-2013，150万

  8. 科技部磁约束聚变能专项项目课题，液态增殖剂TBM设计和技术可行性研究-低活化钢的中子辐照及活化特性研究，2009GB109003，2009-2012，325万

     

    研究成果

    在中国主流先进核材料中子辐照实验、核结构钢中子辐照损伤及氦效应机理、辐照损伤根源及寿命预测研究方面做出了系统性和创新性工作：负责并完成十余种中国主流先进核材料（500余样品）高剂量中子辐照实验，为中国先进核材料研发做出了重要贡献，目前获得国产核结构钢的高剂量中子辐照损伤数据，获得F/M钢中子辐照氦泡硬化实验数据，发现聚变低活化钢高能散裂中子的低温辐照小尺寸氦泡效应和高温辐照损伤回复效应；国内外主流聚变核结构钢高能中子辐照损伤根源机理研究获得创新性成果，从实验上确定中子辐照小尺寸氦泡导致硬化影响因子，发现稳定氦泡阻碍位错移动硬化的氦/空位比例引起的突变效应及超压临界排斥机制，提出解释氦泡诱导晶间脆化的新机理；研发了引入三维DIC方法的核材料高温（真空/气氛）断裂/损伤力学试验平台，发现聚变低活化钢断裂韧性的温度效应，初步建立CFETR候选材料数据库、损伤模型与寿命预测方法。

    代表性论文：

  9. W. Zhang, Y. Xie, L. Peng*, et al, Fracture toughness determination from load-line displacement of 3-point bend specimen using 3D digital image correlation method for CLF-1 steel, J. Nucl. Mater. 543 (2020) 152565

  10. J. Shi, Xing Liu, L. Peng*, et al, Atomic-scale mechanisms of He/V ratio effect on helium bubble hardening in iron for neutron irradiated F/M steels, J. Nucl. Mater. 542 (2020) 152495

  11. Y. Xie, L. Peng*, et al, Temperature effect on fracture toughness of CLF-1 steel with miniature three-point bend specimens, J. Nucl. Mater. 531 (2020) 151992

  12. Y. Bai, J. Shi, L. Peng* et al, First principles study on HenV clusters in α-Fe bulk and grain boundaries, Computational Mater. Sci. 139 (2017) 419–429

  13. B. Ma, L. Peng* et al, Irradiation creep lifetime analysis on first wall structure materials for CFETR, Fusion Eng. Des. 118 (2017) 117–123

  14. J. Shi, L. Peng* et al, Molecular Dynamics Study: Effects of He Bubble and Cr Precipitate on Tensile Deformation of Grain Boundaries in α-Fe, IEEE Transactions on Plasma Science 45 (2017) 289~293

  15. L. Peng*, et al, Microstructure and microhardness of CLAM steel irradiated up to 20.8 dpa in STIP-V, J. Nucl. Mater. 468 (2016) 255–259

  16. H. Ge, L. Peng*, et al, Tensile properties of CLAM steel irradiated up to 20.1 dpa in STIP-V, J. Nucl. Mater. 468 (2016) 240–245

  17. X. Zhang, L. Peng*, et al, Creep Lifetime Analysis on First Wall Structure Material for CFETR, J. Fusion Energy 34 (2015) 1433–1437

  18. S. Jiang, L. Peng*, et al, He and H irradiation effects on the nanoindentation hardness, J. Nucl. Mater. 455 (2014) 335–338

  19. L. Peng, Y. Dai, Helium-induced hardening effect in ferritic/martensitic steels F82H and Optimax-A irradiated in a mixed spectrum of high energy protons and spallation neutrons, J. Nucl. Mater. 417 (2011) 996–1000

  20. L. Peng*, et al, Swelling of CLAM steel irradiated by electron/helium to 17.5 dpa with 10 appm He/dpa, Fusion Eng. Des. 86 (2011) 2624–2626

  21. L. Peng*, et al, Preliminary Analysis of Irradiation Effects on CLAM after Low Dose Neutron Irradiation, J. Nucl. Mater. 386-388 (2009) 312-314.

     

     

    四、放射化学与辐射化学

    1、放射性废物处理

    针对核工业活动中产生的放射性废物，开展氧化石墨烯、氮化硼纳米片及结晶硅钛酸盐等二维纳米材料功能化研究以用于放射性废物的高效分离与回收；开发用于金属离子经济、高效分离的新型膜乳化循环萃取装置；利用光化学还原/辐射还原方法开发放射性废液中裂变元素特别是铂族金属的分离新技术；开展基于超临界水氧化技术的放射性有机废液高效、绿色处理新方法等。

    部分研究成果：

  22. Wang, Y., Wu, Z., Weng, H., Ding, X., Wang, L., Li, F. & Lin, M. (2019). Separation of Re(VII) from aqueous solution by acetone-enhanced photoreduction: an insight into the role of acetone. Journal of Photochemistry and Photobiology A: Chemistry, 380, 111823.

  23. He, K., Tang, J., Weng, H., Chen, G., Wu, Z., & Lin, M. (2019). Efficient extraction of precious metal ions by a membrane emulsification circulation extractor. Separation and Purification Technology, 213, 93-100.

  24. Li, F., Yang, Z., Weng, H., Chen, G., Lin, M., & Zhao, C. (2018). High efficient separation of U(VI) and Th(IV) from rare earth elements in strong acidic solution by selective sorption on phenanthroline diamide functionalized graphene oxide. Chemical Engineering Journal, 332, 340-350.

  25. Yang, Z., Chen, G., Weng, H., Shen, W., Huang, Z., & Lin, M. (2018). Efficient and selective separation of U(VI) and Th(IV) from rare earths using functionalized hierarchically mesoporous silica. Journal of Materials Science, 53(5), 3398-3416.

  26. Shang, Y., Xiao, J., Weng, H., Li, F., Cheng, S., Yamashita, S., & Lin, M. (2018). Efficient separation of Re(VII) by radiation-induced reduction from aqueous solution. Chemical Engineering Journal, 341, 317-326.

  27. Zhao, X., Meng, Q., Chen, G., Wu, Z., Sun, G., Yu, G., & Lin, M. (2018). An acid-resistant magnetic Nb-substituted crystalline silicotitanate for selective separation of strontium and/or cesium ions from aqueous solution. Chemical Engineering Journal, 352, 133-142.

  28. Li, F., Shang, Y., Ding, Z., Weng, H., Xiao, J., & Lin, M. (2017). Efficient extraction and separation of palladium (Pd) and ruthenium (Ru) from simulated HLLW by photoreduction. Separation and Purification Technology, 182, 9-18.

  29. 赵旭东, 翁汉钦, 盛六四, 於国兵, & 林铭章. (2019). 用硅钛酸盐快速高效清除水中低浓度铅离子. 中国科学技术大学学报, (4), 4.

  30. 赵驰, 翁汉钦, 汪谟贞, 葛学武, & 林铭章. (2017). 吡啶基改性纤维状介孔二氧化硅微球的辐射制备及其对 U (VI) 的吸附性能. 辐射研究与辐射工艺学报, 35(5), 50301-050301.

  31. 丁作铭, 李富海, 刘哲, 方仲, & 林铭章. (2017). 光化学分离水溶液中铂族金属元素的研究——Pd (Ⅱ) 的光还原. 核化学与放射化学, 39(1), 22-29.

  32. 李富海, 丁作铭, 林铭章, 何辉, & 叶国安. (2016). 后处理中锕系元素和贵金属元素光化学调价方法. 核化学与放射化学, 38(2), 65-78.

 

2、辐射化学

在核技术应用过程中，不可避免存在电离辐射与物质的相互作用以及因此产生的各种效应或影响。尽管有些效应是有利的，但很多情况下是有害的，对核设施的安全运行将造成严重影响。针对这些问题，我们开展乏燃料后处理中新型萃取剂与溶剂的辐射分解及性能评价研究；新型高分子纳米复合材料的辐射效应研究；辐射法制备高分子材料及其功能化改性研究；高温高压及强碱强酸等极端条件下水溶液辐射分解模拟计算研究；利用脉冲辐解技术开展水溶液辐射分解基础过程研究等。

部分研究成果：

  1. Chen, G., Wang, Y., Weng, H., Wu, Z., He, K., Zhang, P., & Lin, M. (2019). Selective separation of Pd(II) on pyridine-functionalized graphene oxide prepared by radiation-induced simultaneous grafting polymerization and reduction. ACS Applied Materials & Interfaces.

  2. Weng, H., Wu, Z., Zhao, C., Wang, M., Ge, X., Yamashita, S., & Lin, M. (2019). Construction of polyporous polymer microspheres with a tailored mesoporous wall. Polymer Chemistry, 10(12), 1508-1518.

  3. Fang, Z., Tang, J., Xiao, J., Tong, L., Cao, X., Weng, H., & Lin, M. (2019). Modelling electrical corrosion potential of 304 stainless steel under fusion power plant environment. Journal of Radioanalytical and Nuclear Chemistry, 319(1), 303-314.

  4. Fang, Z., Cao, X., Tong, L., Muroya, Y., Whitaker, G., Momeni, M., & Lin, M. (2018). An improved method for modelling coolant radiolysis in ITER. Fusion Engineering and Design, 127, 91-98.

  5. Liu, Z., Fang, Z., Wang, L., He, H., & Lin, M. Z. (2017). Alpha radiolysis of nitric acid aqueous solution irradiated by 238Pu source. Nuclear Science and Techniques, 28(4), 54.

  6. Liu, Z., Fang, Z., Muroya, Y., Fu, H., Yan, Y., Katsumura, Y., & Lin, M. (2016). Local density augmentation of supercritical water probed by 4, 4′-bpyH radical: A pulse radiolysis study. Chemical Physics Letters, 657, 78-82.

  7. Weng, H., Liao, F., Wang, M., Lin, M., & Ge, X. (2016). One-pot synthesis of porous Au-nanoparticles@ polymer/reduced graphene oxide composite microspheres by γ-ray radiation and their application as a recyclable high-performance catalyst. RSC Advances, 6(64), 59684-59691.

  8. Lin, M. (2015). Pulse radiolysis studies of water and alcohols at high temperatures and supercritical conditions. 放射線化学, 3.

  9. 汤嘉,郭子方,翁汉钦,林铭章.基于多级混合澄清槽的PUREX流程的计算模型.核化学与放射化学,2020,42(03):167-173.

  10. 汤嘉,翁汉钦,何辉,叶国安,林铭章.乏燃料后处理中的辐射化学问题Ⅰ.萃取剂的辐射稳定性.核化学与放射化学,2019,41(01):115-132.

  11. 汤嘉,翁汉钦,何辉,叶国安,林铭章.乏燃料后处理中的辐射化学问题Ⅱ.水溶液和稀释剂的辐射分解.核化学与放射化学,2020,42(01):1-12.

 

 

五、辐射防护

1、辐射监测与屏蔽研究

射线装置或放射源会产生射线，对工作场所以及周围环境带来一定影响。不同的装置在周围产生的辐射场会有很大的差异，对这些装置在工作过程中产生的辐射场进行监测和研究，掌握其分布特点，从而采取有针对性的必要屏蔽措施，保护环境和人们的身体健康。该研究室利用国家同步辐射实验室高能电子直线加速器、省内工业电子辐照加速器、合肥离子医学中心医用质子加速器以及CFETR等平台对这些射线装置的辐射场开展了研究，取得了良好的研究成果。

工业电子辐照加速器     医用质子治疗系统布局图
0.3MeV光子在不同角度下衰减倍数随屏蔽墙厚的变化加速器安全联锁系统


承担的项目：

1）国家自然科学基金面上项目，电子辐照加速器辐射防护关键问题研究

2）安徽省自然科学基金面上项目，医用质子加速器治疗过程中辐射场研究

3）生态环境部核与辐射安全监管项目，高能加速器辐射安全研究

4）中国工程物理研究院科研项目，磁约束聚变堆包层辐射监测软件系统设计研究

5）教育部基本业务费重要方向培育基金，磁约束聚变堆辐射安全关键问题和技术研究

6）安徽省省级环保科研课题项目，工业辐照加速器机房辐射屏蔽能力计算

发表的部分论文：

1、Yu Lu , Zhi Chen，Evaluation of shielding effciency of using boric acid as coolant in CFETR vacuum vessel，Fusion Engineering and Design，160 (2020) 111974

2、Chen Z，Qiao S，Jiang S，Xu XG. Activation calculation and radiation analysis for China Fusion Engineering Test Reactor. Fusion Engineering & Design，2016，109-111:290-293

3、刘红冬、阳露、裴曦、陈志、徐榭，几种不同材料降能器对200 MeV质子放疗特性的蒙特卡罗模拟，原子核物理评论，2018,35（1）：78-84

4、廖燕、李佳、陈志，光子屏蔽快速评估软件设计，核电子学与探测技术,2017，37（8）：783-78

5、郭翌、陈志，磁约束聚变堆包层辐射监测软件系统设计，核电子学与探测技术，Vol.37,No.6，Jun. 2017，617-622

6、乔世吉、蒋帅、陈志，徐榭，CFETR 磁体系统的中子学计算及活化分析，核聚变与等离子体物理，2017-09，37（3），354-360

7、梁保辉、陈志、徐榭，CT检查个体化辐射剂量估算研究现状，辐射防护，2017-03，37（2），39-46

8、Yaping Qi, Lijuan He, Zhi Wang，Yuanyuan Liu, Hongdong Liu, Wanli Huo, X. George Xu and Zhi Chen,* EVALUATION OF SECONDARY DOSE AND CANCER RISK FOR OUT-OF-FIELD ORGAN IN ESOPHAGEAL CANCER IMRT IN A CHINESE HOSPITAL USING ATOM PHANTOM MEASUREMENTS, Radiation Protection Dosimetry (2017), Vol.177, No.4 389-396.

9、於国兵、陈志、顾先宝、杜勤、陈乐、李裕熊，高频高压电子辐照加速器主机室辐射场研究，辐射防护，2015,35（2）109-114

10、雷洁瑛、陈志、李珏忻、於国兵、顾先宝、徐榭，3MeV电子辐照加速器主厅内漂移管周围辐射场分析，核技术，2015-02，38（2）020201-6

11、阎明洋、陈志、王遥、李裕熊、於国兵、顾先宝，3MeV电子辐照加速器通风管道辐射场计算，核技术，2013-08，36（8）31-36

 

2、核素测量与分析

研究方向：主要针对辐射环境监测关注核素进行分析，提出了针对Th-232、Ra-228、Ra-226、Po-210、Pb-210和Sr-90等长半衰期核素优化的分析方法。分析的样品包括常见可食用动植物样品、水和气溶胶等，防止放射性核素通过食入或吸入等途径进入人体对人体造成的内照射损伤。

 

承担的项目：

1、安徽省省级环保科研课题项目，安徽省石煤矿相关样品的采集和放射性核素分析

2、安徽省省级环保科研课题项目，安徽省地质环境资料调研和水中放射性核素分析

3、安徽省省级环保科研课题项目，不同粒径气溶胶样品采集与分析

部分研究成果：

1、Ling-Jing Pan，Guo-Bing Yu，Zhi Chen，Liu-Si Sheng，X. George Xu，A modified sampling preparation method for rapid determination of Pb-210 radioactivity in plants in China using crown ether and liquid scintillation counting of beta particles，Journal of Radioanalytical and Nuclear Chemistry，(2018) 317:565–570

2、J. Wu, Z. Chen, H. Wang, Z. Chen, J. Li and C. Lai，A new low-level tritiated water measurement system using CaF2(Eu) powders, Journal of Instrumentation, 2019,14(7), P07019, https://doi.org/10.1088/1748-0221/14/07/P07019. 

3、J. Wu，Z. Chen, Z.L. Chen, J.M.Li and H. Wang，The use of optical fibers as passageways for the scintillation light produced in CaF2 (Eu) powder in water for low-level tritiated water measurement, Journal of Instrumentation, 2019,14(6), P06015, https://doi.org/10.1088/1748-0221/14/06/P06015.

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9、祝小惠、於国兵、闻德运、谭华艳、徐榭、陈志. 微波消解法快速测定气溶胶中~(210)Po[J]. 核电子学与探测技术，2016-02，36(2)，201-204

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