
陈胜利 副教授
研究领域:反应堆物理(中子学模拟与研究、核取证)
中子核数据(评估、处理、检验、使用)
辐照损伤评估(中子、电子、光子、质子等带电粒子辐照离位损伤)
不确定度量化与误差传递
(欢迎感兴趣的同学联系)
基本信息
陈胜利,男,副教授、硕士生导师、中山大学“百人计划”引进,中山大学中法核工程与技术学院
chenshli23(at)mail.sysu.edu.cn
Personal information
Shengli Chen, Associate Professor, Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University
个人经历
2020.12-至今,中山大学,“百人计划”专任教师、硕导
2017.10-2020.10,法国原子能与可替代能源委员会(CEA)、格勒诺布尔-阿尔卑斯大学,能源专业,博士
2015.08-2017.06,中山大学中法核工程与技术学院,核能与核技术工程专业,工学硕士
2011.09-2015.06,中山大学中法核工程与技术学院,核工程与核技术专业,工学学士
Personal experience
2020.12-present, Sun Yat-sen University, Faculty
2017.10-2020.10,French Atomic Energy and Alternative Energies Commission (CEA) & Grenoble Alpes University,Doctor Degree of Fluid Mechanics, Energy, Processes.
2015.08-2017.06,Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University,Master Degree of Nuclear Energy and Technology Engineering;
2011.09-2015.06,Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University,Bachelor Degree of Nuclear Engineering and Technology;
荣誉与奖项
第九届高校学生课外“核+X”创意大赛2024年广东省赛优秀指导老师
Nucl. Sci. Tech. 优秀论文(2022)
广东省优秀学生(研究生阶段)(2017)
国家优秀自费留学生奖学金(2019)
入选NUGENIA论坛学生奖(欧洲共8位)并获资助参加FISA’19(2019)
25届国际核工程大会“钱三强”最佳海报奖(2017)
优秀博士论文(2020)
优秀硕士论文(排名:1/15)(2017)
国家奖学金(2016-2017)
中广核优秀科研奖学金(2017)
中法核工程与技术学院优秀毕业生(2015)
Awards & Honors
Excellent paper of Nucl. Sci. Tech. (2022)
Excellent graduate student in Guangdong Province (2017)
Chinese government award for outstanding self-financed students abroad (2019)
Selected student for NUGENIA Forum Award and financed for FISA’19 (2019)
ICONE-25 Qian Sanqiang Best Poster (2017)
Thesis prize in doctoral school (2021)
Best master thesis in the institute (ranking: 1/15), IFCEN (2017)
CGN outstanding research scholarship (2017)
Chinese national scholarship (2016-2017)
Outstanding graduate of IFCEN (2015)
科研项目
1. 国家自然科学基金,青年科学基金项目,12205390,主持
2. 广东省自然科学基金,面上项目,2023A1515010800,主持
3. 先进燃料有效温度模型研究,主持
4. 堆内低测点功率重构方法研究,主持
5. 国家自然科学基金,专项项目,12242505,参与
6. 国家自然科学基金,面上项目,11775316,参与
7. 龙码***研究,参与
8. 质量***研究,参与
9. 基于有限元模拟的异形燃料性能分析方法研究,参与
研究方向
- 反应堆物理(中子学模拟与研究、核取证)
- 中子核数据(评估、处理、检验、使用)
- 辐照损伤评估(中子、电子、光子、质子等带电粒子辐照离位损伤)
- 不确定度量化与误差传递
Research Interests
1. Irradiation damage calculation from nuclear reactions (n, γ, FPs)
2. Nuclear data evaluation, processing, validation, and application
3. Neutronic analysis
4. Uncertainty quantification and propagation
学术论文(Publications)
期刊文章(一作/通讯):
- T. Wang, C. Zhao, J. Lin, S. Chen* et al., “Enhancing the effective temperature model for typical UO2 fuel in criticality calculations,” Progress in Nuclear Energy, 178: 105523, 2025
- H. Yang#, Z. Li#, S. Chen*, T. Wang, H. Wang, S. Chen, “Review of methods for online power-distribution reconstruction,” Annals of Nuclear Energy, 221: 111531, 2025
- S. Chen*, S. Chen, Z. Li, “A comparative analysis of uncertainty quantification using the deviation-based cost function,” Annals of Nuclear Energy, 214: 111196, 2025
- T. Wang, H. Yang, S. Chen*, C. Yuan*, “Advancing source reactor-type discrimination using machine learning techniques and SFCOMPO-2.0 experimental database,” Annals of Nuclear Energy, 211: 110952, 2025
- T. Wang#, S. Xu#, Z. Li, S. Chen*, “Investigation of the impact of thermal neutron scattering cross sections and angular distributions on criticality calculations,” Annals of Nuclear Energy, 210: 110851, 2025
- 陈胜利*, 王天翔, “两个系列铍反射层临界基准实验的一致性分析与核数据检验,” 物理学报, 74(6): 062801, 2025 (中文SCI)
- S. Chen, S. Chen*, “Evaluation of primary radiation damage cross sections with uncertainties for charged particles,” Journal of Nuclear Materials, 592: 154952, 2024
- S. Chen, S. Chen*, “Systematic study of displacement threshold and the near-threshold primary radiation damage model,” Nuclear Materials and Energy, 41: 101800, 2024
- S. Chen, T. Wang, Z. Zhang et al., “Linear Regression and Machine Learning for Nuclear Forensics of Spent Fuel from Six Types of Nuclear Reactors,” Physical Review Applied, 19: 034028, 2023 (Featured in Physics)
- J. Chen#, M. Liu#, C. Yuan*, S. Chen* et al., “Shell-model-based investigation on level density of Xe and Ba isotopes,” Physical Review C, 107: 054306, 2023
- T. Wang, S. Chen*, S. Xu, Z. Li, S. Chen, X. Wu, “OpenMC interpretation and analysis of two series highly-enriched-uranium thermal-spectrum benchmarks for nuclear data validation,” Annals of Nuclear Energy, 192: 110017, 2023
- S. Chen*, D. Bernard, L. Buiron, “Resonance self-shielded multigroup atomic displacement cross section for assessing neutron irradiation damage,” Nuclear Engineering and Design, 403: 112154, 2023
- S. Chen*, “Assessment of neutron irradiation effects via PKA spectra, displacement damage, and gas production: Application to reactor pressure vessel,” Nuclear Materials and Energy, 37: 101512, 2023
- S. Chen*, “Experimental validation and application of primary radiation damage models near the displacement threshold,” Results in Physics, 51: 106781, 2023
- S. Chen*, “Atomic displacement damage energy model up to high recoil energy,” Nuclear Instruments and Methods in Physics Research B, 536: 104-112, 2023
- S. Chen*, D. Cai, D. Bernard, Y. Peneliau, “Improved methods for calculating electron, positron, and photon radiation-induced displacement damage cross sections,” Nuclear Instruments and Methods in Physics Research B, 535: 137-148, 2023
- 陈胜利、袁岑溪*,“基于核数据的中子诱发原子离位损伤截面评估方法”,原子核物理评论,40(2): 303-313,2023
- S. Chen*, “Effective primary radiation damage model parameters for neutron irradiation experiments,” Journal of Nuclear Materials, 568: 153883, 2022
- S. Chen*, D. Bernard, “Recommendation for computing neutron irradiation damage from evaluated nuclear data,” Journal of Nuclear Materials, 562: 153610, 2022
- S. Chen*, “New evaluation of neutron-induced displacement damage cross section for EUROFER97,” Nuclear Materials and Energy, 33: 101284, 2022
- S. Chen*, B. Cai, C. Yuan*, Z. Li, C. Zhang, “Evaluation of neutron irradiation-induced displacement damage in heat pipe reactor,” Nuclear Materials and Energy, 32: 101216, 2022
- S. Chen*, “Study of neutron capture reaction-induced displacement damage cross section and KERMA factor,” Nuclear Instruments and Methods in Physics Research B, 513: 1-8, 2022
- Z. Zhang, T. Wu, Y. Wang, S. Chen*, C. Yuan*, J. Zhu “Core design and neutronic study on small reactor with advanced fuel designs,” Nuclear Materials and Energy, 29: 101068, 2021
- S. Chen*, D. Bernard, L. Tamagno et al., “Uncertainty assessment for the displacement damage of a pressurized water reactor vessel,” Nuclear Materials and Energy, 28: 101017, 2021
- S. Chen*, Y. Peneliau, D. Bernard, “Comparison of evaluated nuclear data for neutron irradiation damage calculation in fusion spectra,” Fusion Engineering and Design, 171: 112594, 2021
- S. Chen*, E. Vandermeersch, P. Tamagno et al., “Uncertainty propagation from n+56Fe nuclear reaction model parameters to neutron multiplication factor,” Annals of Nuclear Energy, 163: 108553, 2021
- S. Chen*, “Methods for calculating the (n,2n) reaction-induced damage cross section with different approaches of kinematics,” Nuclear Instruments and Methods in Physics Research B, 508: 41-48, 2021
- S. Chen*, “Low-energy atomic displacement model of SRIM simulations,” Nuclear Science and Techniques, 32: 119, 2021
- S. Chen*, P. Tamagno*, D. Bernard et al., “From nuclear physics to displacement damage calculation and uncertainty propagation in CONRAD,” Results in Physics, 17: 103023, 2020
- S. Chen*, D. Bernard, “On the calculation of atomic displacements using damage energy,” Results in Physics, 16: 102835, 2020
- S. Chen*, D. Bernard, “Radiation damage calculations for charged particle emission nuclear reactions,” Chinese Journal of Physics, 166: 135-149, 2020
- S. Chen*, D. Bernard, “Contribution of fission products to displacement damage in fast reactor fuel cladding,” Annals of Nuclear Energy, 145: 107603, 2020
- S. Chen*, D. Bernard, and P. Blaise, “Attenuation of neutron and photon-induced irradiation damage in pressurized water reactor pressure vessels,” Annals of Nuclear Energy, 145: 107601, 2020
- S. Chen*, D. Bernard, “On the beta decay-induced radiation damage,” Nuclear Instruments and Methods in Physics Research B, 467: 58–64, 2020
- S. Chen, C. Yuan*, “Neutronic study of UO2-BeO fuel with various claddings,” Nuclear Materials and Energy, 22: 100728, 2020
- S. Chen, Y. Ge, Y. Zhong, C. Yuan*, “Radial distributions of power and fuel temperature in annular U3Si2 fuel with FeCrAl cladding,” Annals of Nuclear Energy, 135: 106943, 2020
- S. Chen, X. He*, C. Yuan*, “Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors,” Nuclear Science and Techniques, 31: 32, 2020
- S. Chen*, D. Bernard, “Relativistic effect on two-body reaction inducing atomic displacement,” Journal of Nuclear Materials, 522: 236–245, 2019
- S. Chen*, D. Bernard, “Attenuation of atomic displacement damage in the heavy reflector of the PERLE experiment and application to EPR,” Nuclear Engineering and Design, 353: 110205, 2019
- S. Chen*, D. Bernard, L. Buiron, “Study on the self-shielding and temperature influences on the neutron irradiation damage calculations in reactors,” Nuclear Engineering and Design, 346: 85–96, 2019
- S. Chen*, D. Bernard, P. Tamagno et al., “Calculation and verification of neutron irradiation damage with differential cross sections,” Nuclear Instruments and Methods in Physics Research B, 456: 120–132, 2019
- S. Chen*, D. Bernard, C. De Saint Jean, “Calculation and analysis of gamma-induced irradiation damage cross section,” Nuclear Instruments and Methods in Physics Research B, 447: 8–21, 2019
- S. Chen*, D. Bernard, “Application of special relativity in damage calculations,” Nuclear Instruments and Methods in Physics Research B, 440: 107–113, 2019
- S. Chen, C. Yuan*, “Minor Actinides transmutation in candidate accident tolerant fuel-claddings U3Si2-FeCrAl and U3Si2-SiC,” Annals of Nuclear Energy, 127: 204-214, 2019
- S. Chen, C. Yuan*, D. Guo, “Radial distributions of power and isotopic concentrations in candidate accident tolerant fuel U3Si2 and UO2/U3Si2 fuel pins with FeCrAl cladding,” Annals of Nuclear Energy, 124: 460-471, 2019
- S. Chen, C. Yuan*, “Transmutation Study of Minor Actinides in Mixed Oxide Fueled Typical Pressurized Water Reactor Assembly,” Journal of Nuclear Engineering and Radiation Science, 4(4): 041017, 2018
- S. Chen, C. Yuan*, “Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl,” Science and Technology of Nuclear Installations, 2017: 3146985, 2017
会议文章/报告:
- T. Wang, S. Chen*, S. Xu, Z. Li, “Discrepancy across various OpenMC versions due to thermal neutron scattering law,” EPJ Web Conf., 302: 07006, 2024
- S. Chen*, D. Bernard, “Improvements on the damage calculations using evaluated nuclear data and NJOY,” EPJ Web Conf., 294: 06004, 2024
- E. Vandermeersch, S. Chen, S. Xu, P. Tamagno, D. Bernard, P. Blaise, G. Noguere, “From nuclear model parameters to neutronic simulation with the CONRAD and LAST codes”, Consultancy Meeting on model code output & application nuclear data form structure, IAEA, 2021
- S. Chen*, D. Bernard, J. Tommasi, and C. De Saint Jean, “Improved Model for Atomic Displacement Calculation,” EPJ Web Conf., 239: 08003, 2020
- S. Chen*, D. Bernard, and C. De Saint Jean, “Relativistic Effect on Atomic Displacement Damage for Two-Body Inducing Discrete Reactions,” EPJ Web Conf., 239: 08004, 2020
- S. Chen*, G. Noguere, D. Bernard, et al., “PROFIL-2 Experiment and Neutron Capture Cross Sections of Europium Isotopes,” EPJ Web Conf., 239: 01032, 2020
- M. Diakaki*, S. Chen*, G. Noguere, et al., “Evaluation of neutron induced reactions on 56Fe with CONRAD,” EPJ Web Conf., 239: 11005, 2020
- C. De Saint Jean et al., “CONRAD, a code for nuclear data evaluation and more,” in 2019 International Conference on Nuclear Data for Science and Technology (Plenary Session), 2019
- S. Chen*, D. Bernard, P. Archier et al., “Covariance Matrices for Differential and Angle-Integrated Neutron-Induced Elastic and Inelastic Scattering Cross Sections of 56Fe,” EPJ Web Conf., 211: 07002, 2019
- M. Diakaki, S. Chen, G. Noguere, et al., “Status of the evaluation of n + 56Fe reaction data and experimental validation,” in Consultants’ Meeting on INDEN - International Nuclear Data Evaluation Network - on the Evaluated Nuclear Data of the Structural Materials, IAEA, 2019
- S. Chen, P. Tamagno, D. Bernard, and C. De Saint Jean, “Sensitivity and uncertainty analyses of radiation damage cross sections,” in the 9th European Commission Conference on EURATOM Research and Training in Safety of Reactor Systems (FISA 2019), 2019
- S. Chen, D. Bernard, and C. De Saint Jean, “Neutron and photon-induced atomic displacement damage,” in JEFF Meeting – Fusion, EFFDOC-1394, OECD/NEA (Nuclear Energy Agency), 2019
- M. Diakaki, S. Chen, P. Tamagno, and D. Bernard, “Evaluation of n + 56Fe Reaction Data (+Covariances) and Experimental Validation,” in Consultants’ Meeting on INDEN - International Nuclear Data Evaluation Network - on the Evaluated Nuclear Data of the Structural Materials, IAEA, 2018
- S. Chen and C. Yuan*, “Transmutation of Minor Actinides and Power Flattening in PWR MOX Fuel,” in Proceedings of the Reactor Physics Asia 2017 (RPHA17) Conference, 2017
- S. Chen, C. Yuan*, J. Wu, and Y. Zou, “Study of Minor Actinides Transmutation in PWR MOX Fuel,” in Proceedings of the 25th International Conference on Nuclear Engineering, 9: V009T15A006, 2017
- 王天翔,陈胜利*,李茁*,吴小飞,“基于两个含铍系列实验的CENDL-3.2临界计算检验”,第二十届反应堆数值计算与粒子输运学术会议暨2024年反应堆物理会议,哈尔滨,黑龙江,2024年8月27-30日
- 陈胜利*,“基于评价核数据的多体核反应中子辐照损伤截面计算”,中国核科学技术进展报告(第七卷),7-12, 2021
专利 / 软件著作权
- 陈胜利,陈树益,发明专利:“一种材料最低离位阈能的确定方法和装置”,专利号:ZL202410115686.2, 授权时间:2024年4月16日
- 陈胜利,软件名称:“正负电子辐照离位损伤截面计算软件[简称:eDPAXS]”,登记号:2024SR1064508, 授权时间:2024年7月25日
- 陈胜利,软件名称:“基于ENDF核数据的中子辐照损伤截面计算软件[简称:pE2D]”,登记号:2022SR0723395, 授权时间:2022年6月9日
- 袁岑溪(导师),陈胜利,发明专利:“用于嬗变和展平功率的MOX 燃料组件及展平功率的方法”,专利号:ZL201710193424.8, 授权时间:2019年2月5日
- 陈胜利,王天翔,发明专利:“核数据检验方法、装置、电子设备及存储介质”,申请号:202411519346.2, 申请时间:2024年10月29日
- 陈胜利,张纯禹,王海荣,陈树益,发明专利:“基于数据降维和蒙特卡罗抽样的不确定度传递方法”,申请号:202510164188.1, 申请时间:2025年2月14日
学术兼职
- Nuclear Analysis 期刊青年编委
- 第十九、二十届反应堆数值计算与粒子输运学术会议暨2023、2024年反应堆物理会议 分会主席
- Journal of Nuclear Materials、Progress in Nuclear Energy、Nuclear Engineering and Design、Annals of Nuclear Energy、Nuclear Science and Engineering、Nuclear Technology、Nuclear Instruments and Methods B、Nuclear Science and Techniques、Kerntechnik、《核动力工程》、《核技术》等核科学与技术期刊审稿人
- Acta Materialia、Energy、Nuclear Fusion、Carbon、International Journal of Energy Research、Cogent Engineering 等期刊审稿人
- International Conference on Nuclear Data for Science and Technology (ND) 、全国反应堆物理会议(CORPHY)等国内外会议审稿人