banner
图片

倪木一 院长助理/教授

电子邮箱：nimuyi@mail.sysu.edu.cn

研究领域：放射性核素迁移、环境影响、辐射防护、事故安全

邮箱：  nimuyi@mail.sysu.edu.cn

研究领域：放射性核素行为（氚、钋）、放射性环境影响、辐射防护、事故安全

 

教育经历

2008/09 - 2013/06：中国科学技术大学，核科学与技术学院，工学博士，核能科学与工程专业               

2004/09 - 2008/06：中国科学技术大学，物理学院，理学学士，近代物理系

 

工作经历

2018/05 – 今：          中山大学        中法核工程与技术学院，教授（自2025/03）、博导、院长助理（自2024/04）

                                                       先进技术研究院，平台管理处，副处长（挂职，自2024/06）

2020/08 - 2024/02：深圳综合粒子设施研究院（借调）            党委委员、同步辐射经理部总经理助理、工程办主任

2018/01 – 2024/12：国际热核聚变实验反应堆组织（ITER）     ITER Scientist fellow

2016/10 - 2017/12：国际热核聚变实验反应堆组织（ITER）     高级访问学者

2013/07 – 2018/04：中国科学院合肥物质科学研究院（中科院核安全所）      副研究员（自2017/03）

 

科研项目

  1. 国际原子能机构技术合作项目（IAEA TC Program，CPR2024002），Research on the Migration, Transformation, Dose Assessment, and Quality Improvement of Tritium in Coastal Waters，2026-2027周期，中山大学合作方-主持
  2. 国家自然科学基金委-NSAF联合基金：结构材料快中子驱动的氚超渗透效应及其定量模型研究（U2230109），2023/01 – 2025/12，主持，49万
  3. 国家自然科学基金委-青年基金：再蒸发作用下气载氚动态环境迁移特性研究（11505218），2016/01 – 2018/12，主持，23万
  4. GFJG项目：“关键核素XXX研究”. 2023/06 – 2023/12，主持，692万
  5. 军委ZFYY：“XXX安全特性”. 2020/01 – 2020/12，主持，36万
  6. KGJ基础科研项目：“热循环吸附XXX研究”. 2021/01-2022/12，主持，15万
  7. KGJ科研平台经费：“基于同步XXX物性研究” （KFKT-24-202108）. 2021/07 – 2023/06、主持，36万
  8. KGJ科研平台经费：“多物理XXX方法研究”（XKFZ-201908）. 2020/01 – 2021/12，主持，30万
  9. 广东省重点研发项目子课题： “多场耦合的铅铋堆Po-210迁移理论与仿真技术”. 2021/08 – 2024/08，主持，50万
  10. 安徽省自然科学基金-青年项目：螺旋流道液态第一壁在磁场作用下流动稳定性研究（1608085QA09），2016/07 – 2018/06，主持，8万
  11. 企业横向项目：“新型堆化学参数分析—系统设备内氚化学行为研究”. 2023/05 – 2024/06，主持，225万
  12. 企业横向项目：芯块包壳化学相互作用堆外模拟试验研究. 2023/06-2024/06，主持，72.1万
  13. 企业横向项目：新型堆化学参数分析—一回路氚化学行为研究”. 2022/05 – 2022/12，主持，72万
  14. GF横向项目：涂层包壳氢渗透性能评价和微观结构表征. 2024/10-2025/02，主持，60万
  15. GF横向项目：“铅铋堆运行及换料放射性XXXX”. 2022/03 – 2023/09，主持，64万
  16. GF横向项目：“辐射源项XXX行为研究”. 2020/09 – 2021/09，主持，76万
  17. GF横向项目：“铅XXX机理及行为研究”. 2019/11 – 2020/10，主持，82.68万
  18. ITER task：Tritium Management for ITER Dummy TBM & Connection Pipe. 2017/06-2017/12，主持
  19. ITER task：Tritium Management for ITER TBM Port Cell. 2016/10-2017/04，主持
  20. ITER专项：磁约束聚变堆高氚增殖比及高能量放大倍数包层的设计研究（2015GB108005），2015/01-2010/12，课题骨干，750万
  21. ITER专项：液态氚增殖包层概念设计优化与氚分析研究，2011/09-2014/06，课题骨干，120万

 

学术论文

  1. 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
  2. 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
  3. 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
  4. 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
  5. 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
  6. 王雨晴, 翁炎运, 邓理邻, 倪木一*, 谭怡, 张明昊. 基于DPM方法的安全壳内气溶胶输运特性初步研究. 核动力工程. 45(6), 2024:1-7
  7. 张明昊, 吴荣俊, 陈艳, 倪木一*, 等. 基于准可逆方法的封闭空间内放射性气溶胶溯源研究. 辐射防护. 2024,44:18-23
  8. 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.
  9. 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
  10. 王雨晴, 邓理邻, 倪木一*, 武杰伟, 谭怡, 景福庭, 夏明明, 田超. 铅铋气溶胶动力学实验平台研制与初步参数测量. 核动力工程, 2024, 45(1): 178-185.
  11. 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
  12. 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
  13. 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
  14. 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
  15. 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
  16. 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
  17. 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
  18. 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
  19. 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
  20. 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
  21. 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
  22. 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
  23. B Nie, M Jiang, M Ni*, F Li*. Preliminary environmental radiation considerations for CFETR. Fusion Engineering and Design 140, 16-22, 2019
  24. 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
  25. 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
  26. B Nie, M Ni*, S Wei. Individual dose due to radioactivity accidental release from fusion reactor. Journal of hazardous materials 327, 135-143, 2017
  27. 胡星，贾江涛，孟孜，倪木一，陈志斌，张斌. 中国氦冷固态实验包层模块 In-box LOCA 事故分析研究, 核科学与工程 37 (3), 405-412, 2017
  28. 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
  29. 张世超，孟孜，倪木一*，梁参军，蒋洁琼. 聚变堆螺旋流道液态第一壁流动稳定性分析. 核科学与工程 36 (3), 354-359, 2016
  30. 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
  31. 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
  32. 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
  33. 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
  34. 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
  35. 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
  36. 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
  37. 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
  38. 聂保杰，倪木一*，廉超，宋勇，吴宜灿. 基于湍流扩散理论的氚大气弥散程序开发与校验. 原子能科学技术 47, 541-546, 2013
  39. 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
  40. 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
  41. 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
  42. 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
  43. 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
  44. 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
  45. 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
  46. 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
  47. 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
  48. 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
  49. 倪木一，宋勇，黄群英，吴宜灿. 聚变堆氚分析程序 TAS1. 0 的设计与开发. 核科学与工程, 355-361, 2009