核科學與工程系主要針對國際熱核聚變實驗堆計劃(ITER)、中國聚變工程實驗堆(CFETR)、第四代(GenIV)先進核能系統、核燃料循環等國家重大需求,緊密圍繞等離子體物理與聚變工程、鉛基反應堆堆物理與設計、反應堆熱工水力與核安全、先進核燃料/核材料制備和評價、乏燃料后處理與放射性廢物處理、以及輻射防護與核醫學物理等方向開展研究。

 

主要科研平臺:

(一)磁約束聚變數值模擬平臺

圖片1

平臺用于支持磁約束聚變物理研究的數值模擬。平臺共70個計算節點,1680CPU核,理論峰值計算能力70萬億次/秒。平臺集成了主流的磁約束聚變物理數值模擬軟件,主要包括:EFIT(平衡);GATO、ELITE、CLT(穩定性);TGLF、BOUT++(湍流);TGYRO、ONETWO、SOLPS(輸運)。

目前平臺用戶來自國內外主要聚變研究單位,包括中國科學技術大學、中科院等離子體物理研究所,核工業西南物理研究院、華中科技大學、北京大學、大連理工大學、深圳大學、合肥工業大學、美國通用原子能公司、利弗莫爾國家實驗室、圣彼得堡彼得大帝理工大學等。

(二)磁約束聚變工程設計平臺

    平臺基于GPU虛擬化技術以及ICA協議實現云端的工程設計分析,以及虛擬現實系統提供設計討論及評審功能。平臺安裝了ENOVIA、CATIA、DELMIA、ANSYS、Abaqus、Maple、EnSight等主流的工程管理、設計、分析軟件,以及多款自主研發的中子學分析相關軟件,能夠有效支持聚變裝置設計與分析。

(三)直線等離子體實驗裝置

    緊湊型直線等離子體實驗裝置,主要用于材料的等離子體輻照實驗研究。采用直熱式六硼化鑭陰極產生高密度穩態等離子體。

(四)托卡馬克等離子體診斷系統

依托國內EAST,HL-2A兩大托卡馬克裝置,建成了超快電荷交換復合光譜、電荷交換復合光譜、束發射光譜、快離子Dα、多色噴氣成像、相襯成像等多套先進光學診斷系統。

(五)核材料高能中子輻照損傷研究平臺

    多年來與長期緊密合作單位瑞士PSI研究所有長期合作協議和輻照研究項目,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輻照的強流高能中子源),已積累了大量中國主流先進核材料中子輻照實驗樣品,并可利用其完備的輻照后測試分析半熱室,可進行國際主流先進核材料的高能中子輻照損傷研究。

(六)核材料損傷斷裂力學研究平臺

    研發了引入三維數字圖像相關3D-DIC方法的核材料高溫(真空/氣氛保護)斷裂/損傷力學及原位觀察試驗平臺,可實現應變測量和裂紋演化原位觀察的同步分析,可以研究核材料開裂應力變化及損傷/斷裂微觀力學行為協同作用。

核材料多尺度模擬研究平臺:具備原子尺度模軟件(第一性原理VASP及分子動力學LAMMPS)、介觀團簇動力學軟件CDCode、宏觀有限元模擬軟件(ANSYSABAQUS等)等料多尺度模擬軟件平臺和模擬計算服務器,可進行核材料中子輻照損傷及損傷斷裂力學的模擬研究。

 

3萬居里60Co γ射線源

6

0Co 放射源裝置(水井式)

(七)輻射防護研究平臺


PIPSα探測器ELEMENT 2ICP-MS裝置
GR5021 N型高純鍺γ譜儀超低本底液體閃爍計數器


 

研究方向:

一、核聚變物理與工程

1、核聚變堆物理與工程技術:等離子體物理;先進診斷技術;中子學,聚變堆設計等。

通過數值模擬和EASTHL-2A/2M等實驗裝置,重點研究先進的偏濾器位形、熱和粒子排除、雜質屏蔽、邊界熱脈沖緩解新方法及機理、輸運壘的結構形成機理,與高性能芯部等離子體相兼容的高效穩定的熱與粒子排除控制手段?;?span lang="EN-US">EASTHL-2A/2M等實驗裝置,開展湍流和輸運相關物理實驗研究,包括高-低約束模轉換機制、高比壓、高能粒子模、剪切流、電磁湍流等。

研制超快電荷交換復合光譜、電荷交換復合光譜、束發射光譜、快離子Dα、多色噴氣成像、相襯成像等多套先進光學診斷系統,應用到EASTHL-2A/2M托卡馬克物理實驗。

先進偏濾器的結構設計以及熱工水力;中子學軟件開發以及聚變堆中子學,聚變堆包層結構材料活化以及輻射防護等中子學設計;聚變堆燃料循環的排灰氣系統設計。

2、等離子體與材料相互作用:材料輻照研究;低溫等離子體及診斷技術應用。

通過實驗與理論模擬相結合,研究高能量粒子與材料表面非線性相互作用的機理、離子和中子輻照損傷,材料表面和結構改性、以及聚變燃料氘氚滯留和滲透等行為機理。

自主大型邊界綜合模擬程序研發,獲得預測未來聚變堆等離子體與壁相互作用基本行為的能力。深入研究邊緣等離子體物理、原子分子物理、雜質的產生、遷移和輸運物理過程和機制。

低溫等離子體污水處理、空氣凈化,等離子體航天大比沖推進技術等等。

主要科研項目和成果

2011年以來,團隊成員主持完成中國科學技術部 國家磁約束核聚變能發展研究專項2項,國家磁約束核聚變能發展研究青年人才項目1項,國家自然科學基金面上1項,國家自然科學基金專項1項,國家自然科學基金青年基金1項,安徽省自然科學基金青年項目1項,合肥物質科學技術中心方向項目培育基金創新項目1項,中央高?;究蒲袠I務費專項2項以及若干其他項目等,參與完成國家磁約束核聚變能發展研究專項2項。目前在研究項目有國家自然科學基金重點1項和面上2項;國家磁約束核聚變能發展研究專項課題1項;國家磁約束核聚變能發展研究青年人才項目1項;重點研發項目子課題1項;國家磁約束核聚變能發展研究專項子課題3項等。

已培養的研究生幾十名。有3名博士生獲得中科院院長優秀獎,1名碩士生獲得中科院院長優秀獎,1名博士生2018年獲得校優秀博士論文。

 

部分論文:

1.       Simulation Study of the Impurity Radiation in the Quasi-Snowflake Divertor with Ar Seeding for CFETR, Nuclear Fusion 59096049 (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 Design2017.

40.     Development of ramp up design workflow on CFETR Integrated Design Platform, FusionEngineering and Design2017.

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 Transfer127, 2018.

80.     Neutronics Analysis of Helium Cooled Ceramic Breeder Blanket with S-shaped Lithium Zone and Cooling Plate for CFETR. IEEE Transactions on Plasma Science46, 2018.

81.     The Influence of Divertor Plasma Parameter on Tungsten Screening in High Recycling Regime for CFETR, IEEE Transactions on Plasma Science46, 2018.

82.     Extreme Ultraviolet Spectroscopy Applied to Study RMP Effects on Core Impurity Concentration in EAST, IEEE Transactions on Plasma Science46, 2018.

83.     Development of CFETR Integration Design Platform: Modular Structure, IEEE Transactions on Plasma Science45, 2017.

84.     The Integration Platform Development of System Code for CFETR. Transactions on Plasma Science44, 2016.

85.     Piminary Design and Verification of Divertor Module of CFETR System Code, Transactions on Plasma Science44, 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、先進反應堆設計和熱工安全

1. 小型化先進反應堆設計和關鍵技術研究

圍繞第四代鉛基快堆、小型熱管堆以及聚變堆包層系統等開展概念設計研究和關鍵性能分析,包括自然循環鉛冷快堆SNCLFR-100方案、驅動循環鉛冷快堆M2LFR-1000方案、基于燃料棒與中心冷卻熱管一體化結構的小型熱管堆方案、聚變堆氦冷固態包層系統HCSB設計方案等,針對設計方案開展了中子物理計算、熱工水力學計算、燃料性能分析、瞬態事故安全分析等一系列關鍵性能研究工作。


參考文獻:

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. 數值軟件開發和多物理場耦合平臺研究

開展自主知識產權的計算分析軟件開發及驗證,已開發粒子輸運、熱工水力、結構力學、燃料棒行為、系統安全等計算分析軟件,搭建了基于統一耦合架構的多物理場耦合數值計算平臺KMC,耦合中子物理、熱工、力學等多學科專業計算軟件和關鍵設備系統建模,結合后處理數據可視化等建立數值仿真平臺,開展對反應堆關鍵設備狀態和全工況系統動態仿真。

參考文獻:

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. 關鍵熱工水力分析模型實驗研究

開展反應堆熱工水力關鍵現象和物理模型實驗研究,搭建窄矩形通道板狀燃料元件水回路、液態金屬鉛鉍回路及球床熱物性測量實驗臺架等,研究冷卻劑流動傳熱特性、關鍵物理機理模型和熱物性實驗參數等。

參考文獻:

  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. 張杰,陳紅麗*,張雪,窄矩形通道兩相流動實驗回路設計研究[J].核動力工程,2019: 1-5.

  5. 陳紅麗,張雪,張杰,流體研究用可視化實驗裝置,實用新型專利,專利號:202020184198.4.

 

三、先進核燃料與核材料

1、先進裂變核燃料的設計與制備技術研究。研究包括事故容錯核燃料(ATF)的組成成分和結構形貌設計,并應用微流體控制技術及3D打印技術等進行ATF的制備技術研究。研究還包括核燃料制備裝置的設計與建造,以及核燃料微觀結構和物理機械性能相關的基礎研究。

磁約束聚變反應堆燃料循環工程設計與研究。研究面向中國聚變工程實驗堆(CFETR)大科學工程建設需要,研究內容包括磁約束聚變反應堆的氘氚反應等離子體排出輸運系統的設計以及系統各部件制備技術研究。涉及結構材料在極低溫環境下的物理機械性能的基礎研究以及氫同位素在吸附材料上的吸附-解吸機理研究。

實驗室擁有高分辨率顯微鏡、高速攝像機、掃描電鏡、熱導率測量儀、氣氛及真空燒結爐、手套箱等核燃料研究與分析儀器。

 

發表論文:

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、核材料輻照損傷評價與模擬

長期從事核材料的中子輻照實驗、損傷表征及機理研究,研究內容包括核結構鋼的散裂/裂變中子和離子/電子輻照實驗、輻照硬化/輻照脆化/氦效應、核陶瓷損傷斷裂力學等研究。十多年來致力于研究核能材料輻照損傷核心問題—中子輻照損傷,主要進行周期長和難度大的中子輻照實驗及后測試分析研究,結合材料數值模擬,研究國內外主流核結構鋼(RAFM、316Ti、ODS、W合金、Fe合金、Ni合金等)的中子輻照損傷與氦效應機理,探索中子輻照損傷根源和壽命影響,為核材料研發及反應堆延壽提供實驗與理論支持。

科研項目:

  1. 科技部磁約束核聚變能發展專項項目子課題,CFETR國產先進材料小樣品中子輻照及結構性能測評,2018YFE0307101,2019-2023,200

  2. 國家自然科學基金聯合基金項目,熱-力載荷下陶瓷材料體應力及裂紋演化機制研究,U1730123,2018-2020,70

  3. 國家自然科學基金面上項目,低活化鋼的中子輻照后氦效應機理研究,11375173,2014-2017,80

  4. 中科院合肥物質科學技術中心創新項目培育基金,先進反應堆結構鋼的高能中子輻照損傷研究,2012FXCX004,2013-2014,50

  5. 中科院戰略性先導科技專項項目課題,未來先進核裂變能-ADS嬗變系統-鉛鉍冷卻反應堆-核燃料與關鍵設備研制,XDA03040300,2011-2013,19000

  6. 科技部磁約束核聚變能發展專項人才項目,低活化鋼的中子輻照損傷機制研究,2011GB108001,2011-2014,300

  7. 中科院知識創新工程重要方向項目子課題,高輻照場下的材料研究材料-輻照實驗與評估方法-中子輻照材料研究,KJCX2-YW-N35,2009-2013,150

  8. 科技部磁約束聚變能專項項目課題,液態增殖劑TBM設計和技術可行性研究-低活化鋼的中子輻照及活化特性研究,2009GB109003,2009-2012,325

     

    研究成果

    在中國主流先進核材料中子輻照實驗、核結構鋼中子輻照損傷及氦效應機理、輻照損傷根源及壽命預測研究方面做出了系統性和創新性工作:負責并完成十余種中國主流先進核材料(500余樣品)高劑量中子輻照實驗,為中國先進核材料研發做出了重要貢獻,目前獲得國產核結構鋼的高劑量中子輻照損傷數據,獲得F/M鋼中子輻照氦泡硬化實驗數據,發現聚變低活化鋼高能散裂中子的低溫輻照小尺寸氦泡效應和高溫輻照損傷回復效應;國內外主流聚變核結構鋼高能中子輻照損傷根源機理研究獲得創新性成果,從實驗上確定中子輻照小尺寸氦泡導致硬化影響因子,發現穩定氦泡阻礙位錯移動硬化的氦/空位比例引起的突變效應及超壓臨界排斥機制,提出解釋氦泡誘導晶間脆化的新機理;研發了引入三維DIC方法的核材料高溫(真空/氣氛)斷裂/損傷力學試驗平臺,發現聚變低活化鋼斷裂韌性的溫度效應,初步建立CFETR候選材料數據庫、損傷模型與壽命預測方法。

    代表性論文:

  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) 419429

  13. B. Ma, L. Peng* et al, Irradiation creep lifetime analysis on first wall structure materials for CFETR, Fusion Eng. Des. 118 (2017) 117123

  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、放射化學與輻射化學

    1、放射性廢物處理

    針對核工業活動中產生的放射性廢物,開展氧化石墨烯、氮化硼納米片及結晶硅鈦酸鹽等二維納米材料功能化研究以用于放射性廢物的高效分離與回收;開發用于金屬離子經濟、高效分離的新型膜乳化循環萃取裝置;利用光化學還原/輻射還原方法開發放射性廢液中裂變元素特別是鉑族金屬的分離新技術;開展基于超臨界水氧化技術的放射性有機廢液高效、綠色處理新方法等。

    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: Chemistry380, 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 Technology213, 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 Journal332, 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 Science53(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 Journal341, 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 Journal352, 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 Technology182, 9-18.

  29. 趙旭東, 翁漢欽, 盛六四, 於國兵, & 林銘章. (2019). 用硅鈦酸鹽快速高效清除水中低濃度鉛離子中國科學技術大學學報, (4), 4.

  30. 趙馳, 翁漢欽, 汪謨貞, 葛學武, & 林銘章. (2017). 吡啶基改性纖維狀介孔二氧化硅微球的輻射制備及其對 U (VI) 的吸附性能輻射研究與輻射工藝學報35(5), 50301-050301.

  31. 丁作銘, 李富海, 劉哲, 方仲, & 林銘章. (2017). 光化學分離水溶液中鉑族金屬元素的研究——Pd (Ⅱ) 的光還原核化學與放射化學39(1), 22-29.

  32. 李富海, 丁作銘, 林銘章, 何輝, & 葉國安. (2016). 后處理中錒系元素和貴金屬元素光化學調價方法核化學與放射化學38(2), 65-78.

 

2、輻射化學

在核技術應用過程中,不可避免存在電離輻射與物質的相互作用以及因此產生的各種效應或影響。盡管有些效應是有利的,但很多情況下是有害的,對核設施的安全運行將造成嚴重影響。針對這些問題,我們開展乏燃料后處理中新型萃取劑與溶劑的輻射分解及性能評價研究;新型高分子納米復合材料的輻射效應研究;輻射法制備高分子材料及其功能化改性研究;高溫高壓及強堿強酸等極端條件下水溶液輻射分解模擬計算研究;利用脈沖輻解技術開展水溶液輻射分解基礎過程研究等。

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 Chemistry10(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 Chemistry319(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 Design127, 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 Techniques28(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 Letters657, 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 Advances6(64), 59684-59691.

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

  9. 湯嘉,郭子方,翁漢欽,林銘章.基于多級混合澄清槽的PUREX流程的計算模型.核化學與放射化學,2020,42(03):167-173.

  10. 湯嘉,翁漢欽,何輝,葉國安,林銘章.乏燃料后處理中的輻射化學問題Ⅰ.萃取劑的輻射穩定性.核化學與放射化學,2019,41(01):115-132.

  11. 湯嘉,翁漢欽,何輝,葉國安,林銘章.乏燃料后處理中的輻射化學問題Ⅱ.水溶液和稀釋劑的輻射分解.核化學與放射化學,2020,42(01):1-12.

 

 

五、輻射防護

1、輻射監測與屏蔽研究

射線裝置或放射源會產生射線,對工作場所以及周圍環境帶來一定影響。不同的裝置在周圍產生的輻射場會有很大的差異,對這些裝置在工作過程中產生的輻射場進行監測和研究,掌握其分布特點,從而采取有針對性的必要屏蔽措施,保護環境和人們的身體健康。該研究室利用國家同步輻射實驗室高能電子直線加速器、省內工業電子輻照加速器、合肥離子醫學中心醫用質子加速器以及CFETR等平臺對這些射線裝置的輻射場開展了研究,取得了良好的研究成果。

工業電子輻照加速器     醫用質子治療系統布局圖
0.3MeV光子在不同角度下衰減倍數隨屏蔽墻厚的變化加速器安全聯鎖系統


承擔的項目:

1國家自然科學基金面上項目,電子輻照加速器輻射防護關鍵問題研究

2)安徽省自然科學基金面上項目,醫用質子加速器治療過程中輻射場研究

3)生態環境部核與輻射安全監管項目,高能加速器輻射安全研究

4)中國工程物理研究院科研項目,磁約束聚變堆包層輻射監測軟件系統設計研究

5)教育部基本業務費重要方向培育基金,磁約束聚變堆輻射安全關鍵問題和技術研究

6)安徽省省級環??蒲姓n題項目,工業輻照加速器機房輻射屏蔽能力計算

發表的部分論文:

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、劉紅冬、陽露、裴曦、陳志、徐榭,幾種不同材料降能器對200 MeV質子放療特性的蒙特卡羅模擬,原子核物理評論,2018,351):78-84

4、廖燕、李佳、陳志,光子屏蔽快速評估軟件設計,核電子學與探測技術,2017,378):783-78

5、郭翌、陳志,磁約束聚變堆包層輻射監測軟件系統設計,核電子學與探測技術,Vol.37,No.6,Jun. 2017,617-622

6、喬世吉、蔣帥、陳志,徐榭,CFETR 磁體系統的中子學計算及活化分析,核聚變與等離子體物理,2017-09,373),354-360

7、梁保輝、陳志、徐榭,CT檢查個體化輻射劑量估算研究現狀,輻射防護,2017-03,372),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、於國兵、陳志、顧先寶、杜勤、陳樂、李裕熊,高頻高壓電子輻照加速器主機室輻射場研究,輻射防護,2015,352109-114

10、雷潔瑛、陳志、李玨忻、於國兵、顧先寶、徐榭,3MeV電子輻照加速器主廳內漂移管周圍輻射場分析,核技術,2015-02,382020201-6

11、閻明洋、陳志、王遙、李裕熊、於國兵、顧先寶,3MeV電子輻照加速器通風管道輻射場計算,核技術,2013-08,36831-36

 

2、核素測量與分析

研究方向:主要針對輻射環境監測關注核素進行分析,提出了針對Th-232、Ra-228、Ra-226、Po-210、Pb-210Sr-90等長半衰期核素優化的分析方法。分析的樣品包括常見可食用動植物樣品、水和氣溶膠等,防止放射性核素通過食入或吸入等途徑進入人體對人體造成的內照射損傷。

 

承擔的項目:

1、安徽省省級環??蒲姓n題項目,安徽省石煤礦相關樣品的采集和放射性核素分析

2、安徽省省級環??蒲姓n題項目,安徽省地質環境資料調研和水中放射性核素分析

3、安徽省省級環??蒲姓n題項目,不同粒徑氣溶膠樣品采集與分析

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.

4、J. Wu,Z.L. Chen, G.Y. Wu, Z. Chen and H.Y. Wang,The substitutability of liquid scintillation cocktail for CaF2(Eu) powder in low-level tritiated water measurement, Journal of Instrumentation, 2019,14(1), P01026, https://doi.org/10.1088/1748-0221/14/01/P01026。

5、Suleiman Ameir Suleiman, Yaping Qi, Zhi Chen, X. George Xu,Monte carlo study of organ doses and related risk for cancer in Tanzania from scattered photons in cervical radiation treatment involving Co-60 source,Physica Medica,62 (2019) :13–19

6、梁永廣,王元,於國兵,夏明明,顧先寶,范然,陳志,基于微濾法處理水樣中226Raα能譜分析技術.原子能科學技術

7、夏明明、於國兵、聞德運、顧先寶、王元、梁永、吳其反、陳志,基于液體閃爍能譜分析方法的環境水中228Ra檢測研究,核技術,2019,423):030301-1~6.

8、譚華艷、於國兵、顧先寶、石夏青、祝小惠、陳志、徐榭. 輻射監測氣溶膠濾材過濾效率測試. 核電子學與探測技術,2016-05,365),545-548

9、祝小惠、於國兵、聞德運、譚華艷、徐榭、陳志. 微波消解法快速測定氣溶膠中~(210)Po[J]. 核電子學與探測技術,2016-02,36(2),201-204

10、石夏青、於國兵、顧先寶、張瑜、趙俊、陳志,徐榭. 輻射監測氣溶膠制樣方法測試對比. 核技術,2016-03,39(3):27-32

11、潘靈婧、陳志、於國兵、陳樂、聞德運、徐榭,快速測量多β放射性核素液態樣品中活度的方法研究. 核電子學與探測技術,2014-07,34(7),812-815