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倪木一副院長/教授

電子郵箱：nimuyi@mail.sysu.edu.cn

研究領域：放射性核素遷移、環境影響、輻射防護、事故安全

郵箱：  nimuyi@mail.sysu.edu.cn

研究領域：堆內放射性核素行為（氚、釙、碘、銫、碲）、環境影響、輻射防護、事故安全

 

教育經歷

2008/09 - 2013/06：中國科學技術大學，核科學與技術學院，工學博士，核能科學與工程專業               

2004/09 - 2008/06：中國科學技術大學，物理學院，理學學士，近代物理系

 

工作經歷

2018/05 – 今：          中山大學        中法核工程與技術學院，教授（自2025/03）、博導、副院長（自2025/09）

                                                       先進技術研究院，平臺管理處，副處長（掛職，自2024/06）

2020/08 - 2024/02：深圳綜合粒子設施研究院（借調）            黨委委員、同步輻射經理部總經理助理、工程辦主任

2018/01 – 2024/12：國際熱核聚變實驗反應堆組織（ITER）     ITER Scientist fellow

2016/10 - 2017/12：國際熱核聚變實驗反應堆組織（ITER）     高級訪問學者

2013/07 – 2018/04：中國科學院合肥物質科學研究院（中科院核安全所）      副研究員（自2017/03）

 

科研項目

  1. 縱向項目：
    廣東省重點研發項目課題：鉛鉍快堆燃料元件多環境服役評價模型方法（2025B0101090001），2025/04 – 2028/04，主持，350萬
    國家自然科學基金委-NSAF聯合基金：結構材料快中子驅動的氚超滲透效應及其定量模型研究（U2230109），2023/01 – 2025/12，主持，49萬
    廣東省重點研發項目子課題： “多場耦合的鉛鉍堆Po-210遷移理論與仿真技術”. 2021/08 – 2024/08，主持，50萬
    KGJ科研平臺經費：“基于同步XXX物性研究” （KFKT-24-202108）. 2021/07 – 2023/06、主持，36萬
    KGJ基礎科研項目：“熱循環吸附XXX研究”. 2021/01-2022/12，主持，15萬
    KGJ科研平臺經費：“多物理XXX方法研究”（XKFZ-201908）. 2020/01 – 2021/12，主持，30萬
    軍委ZFYY：“XXX安全特性”. 2020/01 – 2020/12，主持，36萬
    國家自然科學基金委-青年基金：再蒸發作用下氣載氚動態環境遷移特性研究（11505218），2016/01 – 2018/12，主持，23萬
    安徽省自然科學基金-青年項目：螺旋流道液態第一壁在磁場作用下流動穩定性研究（1608085QA09），2016/07 – 2018/06，主持，8萬
  2. 橫向項目：
    GF橫向項目：“關鍵核素XXX研究”. 2023/06 – 2023/12，主持，692萬
    GF橫向項目：涂層包殼氫滲透性能評價和微觀結構表征. 2024/10-2025/02，主持，60萬
    GF橫向項目：“鉛鉍堆運行及換料放射性XXXX”. 2022/03 – 2023/09，主持，64萬
    GF橫向項目：“輻射源項XXX行為研究”. 2020/09 – 2021/09，主持，76萬
    GF橫向項目：“鉛XXX機理及行為研究”. 2019/11 – 2020/10，主持，82.68萬
    企業橫向項目：芯塊包殼化學相互作用堆外模擬試驗研究. 2023/06-2024/06，主持，72.1萬
    企業橫向項目：“新型堆化學參數分析—系統設備內氚化學行為研究”. 2023/05 – 2024/06，主持，225萬
    企業橫向項目：新型堆化學參數分析—一回路氚化學行為研究”. 2022/05 – 2022/12，主持，72萬
  3. 國際合作項目：
    國際原子能機構技術合作項目（IAEA TC Program，CPR2024002），Research on the Migration, Transformation, Dose Assessment, and Quality Improvement of Tritium in Coastal Waters，2025-2026周期，中山大學合作方-主持
    ITER task：Tritium Management for ITER Dummy TBM & Connection Pipe. 2017/06-2017/12，主持
    ITER task：Tritium Management for ITER TBM Port Cell. 2016/10-2017/04，主持
     

學術論文

  1. Chenyu Liu, Hanyu Wu, Yuqing Wang, Lili Li, Jiang Zhou, Jiewei Wu, Peng Lin*, Muyi Ni*. Exploring the iodine adsorption and deposition behavior: An out-of-pile experiment on accident conditions of lead-bismuth fast reactor. Journal of Hazardous Materials. Volume 495, 2025, 139116
  2. Ao Gan, Hui Du, Lijie Shi, Man Jiang*, Muyi Ni*. Density functional theory study of radiotoxic PbPo adsorption on Ag surfaces. Progress in Nuclear Energy, Volume 183, May 2025, 105680
  3. Jiang Y, Ji F, Ye X, M Ni*. A Mass-Energy-Momentum conservation model for optimizing the Thermal Cycling Absorption Process: Insights from Model optimization and Parameters sensitivity analysis, Fusion Science and Technology. 2025
  4. Junyang Zeng, Lili Li, Yingzhe Du, Ziliang Hou, Youting Wu, Shiying Li, Hanyu Wu, Zhihao Liu, Peng Lin**, Muyi Ni*, Xiajie Liu. Public dose assessment for Yangjiang nuclear power plant effluents: A multi-media numerical model of tritium transport in the South China sea. Journal of Environmental Radioactivity 286 (2025) 107684
  5. Y Wang, H Du, Y Tan, Y Chen, F Jing, J Wu, Y Jiang, H Wu, F Jia, M Ni,*, M Jiang*. Deposition behavior of PbTe doped LBE aerosol and Te valence prediction: platform test and first-principles calculation. Journal of Hazardous Materials. Volume 483, 5，2025, 136524
  6. Y Jiang, S Li, Y Du, Y Pu, J Yang, S Zhang, P Lin, M Ni*. In-situ measurement of hydrogen isotope behavior in high temperature LBE: Diffusivity, permeability, and solubility. Journal of Nuclear Materials 603, 155392, 2025
  7. 王雨晴, 翁炎運, 鄧理鄰, 倪木一*, 譚怡, 張明昊. 基于DPM方法的安全殼內氣溶膠輸運特性初步研究. 核動力工程. 45(6), 2024:1-7
  8. 張明昊, 吳榮俊, 陳艷, 倪木一*, 等. 基于準可逆方法的封閉空間內放射性氣溶膠溯源研究. 輻射防護. 2024,44:18-23
  9. Junyang Zeng, Yuqing Wang, Minghao Zhang, Muyi Ni*. A Preliminary Study on the Transport of Critical Radionuclide Polonium in the Marine Environment After Source Term Release. ICONE-31 Conference Proceeding. Prague, 2024, Aug.4-8.
  10. Y Jiang, J Wu, F Ji, Y Wang, M Ni*, M Jiang*. Tritium management in ITER test blanket systems port cell for maintenance operations. Nuclear Fusion 64 (6), 066035. 2024
  11. 王雨晴, 鄧理鄰, 倪木一*, 武杰偉, 譚怡, 景福庭, 夏明明, 田超. 鉛鉍氣溶膠動力學實驗平臺研制與初步參數測量. 核動力工程, 2024, 45(1): 178-185.
  12. H Du, A Gan, J Wu, M Jiang*, M Ni*. Effects of surface defects and Bi2 pollution on adsorption of Po on Ag surface. Progress in Nuclear Energy 166, 104969. 2023
  13. M Jiang, H Du, A Gan, M Ni*, B Zhao. Density functional calculation of adsorption and dissociation of PbPo molecule on Pd (100), Pd (110) and Pd (111) surfaces. Journal of Nuclear Materials 581, 154452. 2023
  14. Y Jiang, D Xie, J Wu, H Li, J Zhu, M Ni, T Gao, X Ye*. Dynamic Simulation of the Temperature Field of LiH Single Crystal Growth. Crystals 13 (3), 504, 2023
  15. Y Jiang, F Ji, Y Feng, X Ye*, M Ni*. Effect of alumina on thermodynamic performance of palladium-H2 (D2) system. International Journal of Hydrogen Energy 47 (41), 18088-18097, 2022
  16. M Jiang, Z Zhao, H Du, Z Chen, M Ni*. Role of surface defects in trap of monoatomic polonium on Pd surface. Journal of Nuclear Materials 557, 153205, 2021
  17. J Wu, R Wu, Y Wang, J He, C Hu, X Zeng, M Ni*. Prediction of dissolved impurities and movement of oxide particles in the primary circuit of LBE fast reactor. Coatings 11 (10), 1263, 2021
  18. D Lilin, W Yuqing, Z Zian, H Bochen, W Jiewei, H Jianbo, N Muyi*. Multi-physics model development for polonium transport behavior in a lead-cooled fast reactor. Frontiers in Energy Research 9, 711916, 2021
  19. X Ye, G Li, C Liang, B Ma, X Xiang, Z Zheng, M Ni, C Chen. Determination of the detrapping energy of tritium in tungsten. Journal of Nuclear Materials 544, 152662, 2021
  20. B Nie, S Fang, M Jiang, L Wang, M Ni, J Zheng, Z Yang, F Li*. Anthropogenic tritium: Inventory, discharge, environmental behavior and health effects, Renewable and Sustainable Energy Reviews 135, 110188, 2021
  21. M Jiang, B Nie, Z Yang*, M Ni, Z Chen, First principles investigation of hydrogen adsorption and dissociation on Fe doped α-Al2O3 (0001) surface, Journal of Nuclear Materials 533, 152102, 2020
  22. X Zhao, M Ni, B Nie, B Zhang, L Chen, K Huang*, S Liu. 3D tritium transport analysis for WCCB blanket based on COMSOL. Fusion Engineering and Design 151, 111405, 2020
  23. B Nie, G Ran, Q Zeng, H Du, Z Li, Y Chen, Z Zhu, X Zhao, M Ni*, F Li*. Insights into fuel start‐up and self‐sufficiency for fusion energy: The case of CFETR. Energy Science & Engineering 7 (2), 457-468, 2019
  24. B Nie, M Jiang, M Ni*, F Li*. Preliminary environmental radiation considerations for CFETR. Fusion Engineering and Design 140, 16-22, 2019
  25. B Nie, M Ni*, J Liu, Z Zhu, Z Zhu, F Li*. Insights into potential consequences of fusion hypothetical accident, lessons learnt from the former fission accidents. Environmental Pollution 245, 921-931, 2019
  26. Z Meng, S Zhang, J Jia, Z Chen, M Ni*. AK‐Epsilon RANS turbulence model for incompressible MHD flow at high Hartmann number in fusion liquid metal blankets. International Journal of Energy Research 42 (1), 314-320, 2018
  27. B Nie, M Ni*, S Wei. Individual dose due to radioactivity accidental release from fusion reactor. Journal of hazardous materials 327, 135-143, 2017
  28. 胡星，賈江濤，孟孜，倪木一，陳志斌，張斌. 中國氦冷固態實驗包層模塊 In-box LOCA 事故分析研究, 核科學與工程 37 (3), 405-412, 2017
  29. Z Meng, M Ni, J Jiang, Z Zhu, T Zhou*. Code validation for magnetohydrodynamic buoyant flow at high Hartmann number, Journal of Fusion Energy 35, 148-153, 2016
  30. 張世超，孟孜，倪木一*，梁參軍，蔣潔瓊. 聚變堆螺旋流道液態第一壁流動穩定性分析. 核科學與工程 36 (3), 354-359, 2016
  31. B Nie, M Ni*, J Jiang, Y Wu. Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor. Journal of environmental radioactivity 148, 137-140. 2015
  32. Z Meng, Z Zhu, J He, M Ni*. Experimental studies of MHD pressure drop of PbLi flow in rectangular pipes under uniform magnetic field. Journal of Fusion Energy 34, 759-764, 2015
  33. B Nie, M Ni*, J Jiang, Y Wu. A Dynamic Modeling 3H Transfer to the Environment Under Accidental Release from the Fusion Reactor. Journal of Fusion Energy 34, 739-745, 2015
  34. M Ni*, C Lian, S Zhang, B Nie, J Jiang, FDS Team. Structural design and preliminary analysis of liquid lead–lithium blanket for China Fusion Engineering Test Reactor, Fusion Engineering and Design 94, 61-66, 2015
  35. G Sun, C Lian, M Ni, J Song, M Wang, J Jiang, L Hu. Preliminary Shielding Design and Analysis of Liquid Lead–Lithium Blanket for Chinese Fusion Engineering Testing Reactor. Journal of Fusion Energy 34, 443-447, 2015
  36. D Chen, J Jiang, Y Hou, W Duan, M Ni, C Xing. Preliminary Cost Assessment and Compare of China Fusion Engineering Test Reactor. Journal of Fusion Energy 34, 127-132, 2015
  37. B Nie, M Ni*, C Lian, J Jiang. Preliminary analysis of public dose from CFETR gaseous tritium release. Fusion Engineering and Design 91, 25-29, 2015
  38. M Ni, M Li, J Jiang, W Wang, Y Wu. Numerical investigation on hydrodynamic performance of liquid lead lithium bubble column using population balance model. Fusion Engineering and Design 89 (6), 871-874, 2014
  39. 聶保杰，倪木一*，廉超，宋勇，吳宜燦. 基于湍流擴散理論的氚大氣彌散程序開發與校驗. 原子能科學技術 47, 541-546, 2013
  40. M Ni, Y Wang, B Yuan, J Jiang, Y Wu. Tritium supply assessment for ITER and DEMOnstration power plant. Fusion Engineering and Design 88 (9-10), 2422-2426, 2013
  41. M Ni, Y Song, M Jin, J Jiang, Q Huang. Design and analysis on tritium system of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX). Fusion Engineering and Design 87 (7-8), 1004-1008, 2012
  42. Y Wang, M Ni, J Jiang, Y Wu. Preliminary evaluation of the adequacy of lithium resources of the world and China for DT fusion reactors. Plasma Science and Technology 14 (7), 636, 2012
  43. Y Song, A Sagara, T Muroga, Q Huang, M Ni, Y Wu. Analysis on tritium management in FLiBe blanket for LHD-type helical reactor FFHR2. Plasma and Fusion Research 7, 2405016-2405016, 2012
  44. Y Song, Q Huang, M Ni, X Chen. Analysis on initial tritium supply for starting up fusion power reactor FDS-II. Fusion Science and Technology 60 (3), 1121-1124, 2011
  45. M Ni, Q Huang, Y Song, X Chen. Tritium Safety Assessment on High Temperature Liquid Blanket for Fusion-Based Hydrogen Production Reactor FDS-III. Fusion Science and Technology 60 (3), 1125-1128, 2011
  46. Y Song, Q Huang, M Ni. Tritium analysis of fusion-based hydrogen production reactor FDS-III. Fusion engineering and design 85 (7-9), 1044-1047, 2010
  47. S Yong, H Qunying, N Muyi. Analysis of Plasma-Driven Tritium Permeation Through the First Wall of DFLL-TBM in ITER. Plasma Science and Technology 11 (6), 730, 2009
  48. Y Song, Q Huang, M Ni, Y Wang. Preliminary tritium safety analysis on China DFLL-TBM for ITER. Fusion engineering and design 84 (12), 2114-2117, 2009
  49. Y Song, Q Huang, Y Wang, M Ni. Analysis on tritium controlling of the dual-cooled lithium lead blanket for fusion power reactor FDS-II. Fusion engineering and design 84 (7-11), 1779-1783, 2009
  50. 倪木一，宋勇，黃群英，吳宜燦. 聚變堆氚分析程序 TAS1. 0 的設計與開發. 核科學與工程, 355-361, 2009