一、个人简介
近年来共发表SCI论文20余篇，其中以第一/共一/共同通讯作者身份发表SCI论文16篇，包括1区7篇。现任航空学院特聘副研究员。
二、主要学习与工作经历
科研与学术工作经历：
2025.12-至今，上海电机学院，航空学院，特聘副研究员
2023.10-2025.11，复旦大学，航空航天系，博士后
教育经历：
2018.09-2023.10，复旦大学，力学专业，博士
2014.09-2018.06，复旦大学，理论与应用力学专业，学士
三、代表性科研成果
学术成果：
1. 国家资助博士后研究人员计划, GZC20240284, 中国博士后科学基金会
2. 复旦大学超级博士后
3. 国家自然科学基金重点项目, 事故容错多层级复合核燃料辐照热力耦合变形和破坏的多尺度研究，2022.01-2026.12，参与（主要完成人）
4. XXXXXX，中央 XXXXXXX, XX 预先研究项目, 2022.08-2024.12，参与（主要完成人）
5. 外部约束及非线性材料本构对 UO2 核芯辐照肿胀行为影响研究（横向课题），中国核动力研究设计院，2024.01-2024.07，参与（主要完成人）
6. 大轴向温差下燃料元件包壳脆韧转变行为研究（横向课题），中国核动力研究设计院，2023.07-2023.12，参与（主要完成人）
7. IMDP 分析模型研究（横向课题），中广核研究院有限公司，2020.05-2021.08，参与（主要完成人）
8. 多重复杂非线性结构对燃料组件辐照变形影响的高效数值模拟技术研究（横向课题），中国核动力研究设计院，2018.09-2020.07，参与（主要完成人）
9. 含氢锆合金力学性能模拟研究（横向课题），中广核研究院有限公司，2021.07-2022.06，参与
10. UN-U3Si2复合燃料蠕变性能研究（横向课题），中国核动力研究设计院，2020.11-2022.02，参与
论文：
(1) Jing Zhang, Shurong Ding*. Effects of coating layer thicknesses on the thermo-mechanical coupling behaviors of FCM fuels. Annals of Nuclear Energy, 2026, 229: 112104.
(2) Jing Zhang, Feng Yan, Shurong Ding*. Continuum-mechanics-based multi-scale modeling of fission gas swelling and release coupling behaviors for UO2 fuels. Journal of Nuclear Materials, 2025, 609:155757.
(3) Jing Zhang, Shurong Ding*. An improved volumetric growth model system and the corresponding computational method for porous carbon materials under irradiation. Nuclear Engineering and Design, 2025, 432:113778.
(4) Jing Zhang#, Jingyu Zhang#, Haoyu Wang,Changbing Tang, Pan Yuan, Chunyu Yin, Shurong Ding*, Yuanming Li. Modeling of Mesoscale Creep Behaviors and Macroscale Creep Responses of Composite Fuels Under Irradiation Conditions. Acta Mechanica Solida Sinica, 2022, 35:1040-1054.
(5) Jing Zhang, Haoyu Wang, Hongyang Wei,Jingyu Zhang, Changbing Tang, Chuan Lu, Chunlan Huang, Shurong Ding*, Yuanming Li*. Modelling of effective irradiation swelling for inert matrix fuels. Nuclear Engineering and Technology, 2021, 53:2616-2628.
(6) Jing Zhang, Jingyu Zhang, Haoyu Wang,Hongyang Wei, Changbing Tang, Chuan Lu, Shurong Ding*, Yuanming Li*. Research on the homogenized post-irradiation elasto-plastic constitutive relations for composite nuclear fuels. Frontiers in Materials, 2021, 8:651875.
(7)Luning Chen, Jing Zhang*, Shurong Ding*. Modeling and analysis for the anisotropic irradiation swelling of porous SiC/SiC composites. Journal of Nuclear Materials, 2025, 607:155711.
(8) Jinqiang Wang#, Luning Chen#, Zhiwei Lu, Guochen Ding, Qisen Ren, Jiaxiang Xue, Xiaobin Jian, Jing Zhang*, Shurong Ding*. Modeling of the damage and fracture behaviors of a SiC triplex tube during the burst test with elastomeric insert. Journal of Nuclear Materials, 2025, 603:155420.
(9) Zekun Li, Jing Zhang*, Feng Yan, Shurong Ding*, Qisen Ren. Modeling of the irradiation-induced multi-scale mechanical behaviors for surrogate FCM pellets with interfacial cracking. Nuclear Engineering and Design, 2025, 436:113999.
(10) Li Yong, Yan Feng, Zhang Jing*, Zang Liye, Ding Shurong*. Mechanical constitutive model for equivalent solid of fission gas bubbles in irradiated U-10Mo Fuels. Rare Metal Materials and Engineering, 2025, 54(7):1653-1660.
(11) Yong Li#, Jing Zhang#, Xiaobin Jian, Guochen Ding, Yunxuan Cai, Shurong Ding*, Yuanming Li. A multi-level-variable correlated mechanistic model system for irradiation-induced multi-scale volume growths of U-10Mo/Zr dispersion nuclear fuels.
Journal of Nuclear Materials, 2025, 605:155459.
(12) Yong Li#, Jing Zhang#, Xiaobin Jian, Guochen Ding, Yunxuan Cai, Feng Yan, Shurong Ding*, Yuanming Li. A novel multi-scale model of equivalent irradiation creep rate for U-10Mo/Zr dispersion fuels during irradiation. Progress in Nuclear Energy, 2025, 187:105857.
(13) Hongyang Wei#, Jing Zhang#, Xiaobin Jian, Yongdong Zhang, Lei Li, Shurong Ding*, Qisen Ren*. Effects of the mesostructures and irradiation conditions on the thermo-mechanical coupling behaviors in LWR-used fully ceramic-microencapsulated fuel pellets. Nuclear Materials and Energy, 2023, 34:101387.
(14) Guochen Ding#, Jing Zhang#, Jie Wang#, Yong Li, Xiaobin Jian*, Shurong Ding*, Yongjun Deng. Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C.
Journal of Nuclear Materials, 2023, 587:154726.
(15) Hongyang Wei#, Jing Zhang#, Yongdong Zhang, Lei Li, Shurong Ding*, Qisen Ren*. Modeling of irradiation-induced thermo-mechanical coupling and multi-scale behavior in a fully ceramic-microencapsulated fuel pellet. Journal of Nuclear Materials, 2021, 544:152673.
(16) Hongyang Wei#, Jing Zhang#, Xiaobin Jian, Yongdong Zhang, Lei Li, Shurong Ding*, Qisen Ren*. Effects of the key parameters of TRISO particle buffer layer on in-pile thermo-mechanical behavior in FCM fuel pellets. Journal of Nuclear Materials, 2021, 551:152977.
软件著作权：
1. 丁淑蓉; 张静; 基于骨架各向异性收缩及蠕变的多孔碳材料辐照体积生长变形分析软件, 中国, 2023SR0789262.
2. 丁淑蓉; 张静; 简晓彬; UO2裂变气体肿胀和释放耦合行为分析软件, 中国, 2023SR1015263.
3. 丁淑蓉; 丁国琛;张静; 李勇;含氢锆合金损伤破坏行为分析计算软件, 中国, 2023SR0789263.
4. 丁淑蓉; 魏洪杨;张静; FCM燃料辐照热-力学行为分析软件, 中国, 2023SR0513592.
5. 丁淑蓉; 严峰; 张静; 简晓彬; 孔祥喆; 弥散燃料元件辐照-退火热-力耦合行为计算软件, 中国, 2023SR0380295.
6. 丁淑蓉; 丁国琛; 张静; 金超越; 基于损伤力学的锆合金氢致延迟开裂行为分析计算软件, 中国, 2024SR2064206.
7. 丁淑蓉; 王金强; 张静; 陈露宁; SiC 复合包壳辐照热-力学性能分析软件, 中国, 2024SR0972701.
8. 丁淑蓉; 王金强; 张静; 陈露宁; SiC 复合包壳开裂失效行为分析软件, 中国, 2024SR0971153.
9. 丁淑蓉; 李勇; 丁国琛; 张静; U-10Mo/Zr 弥散核燃料多尺度关联辐照热力耦合行为计算软件, 中国, 2023SR1418285
四、主要社会学术团体兼职
Materials Science & Engineering A、Nuclear Engineering and Design等学术期刊审稿人
五、主要研究方向
核燃料及结构材料辐照条件下多场耦合行为研究
极端环境下复合材料损伤破坏行为研究
复合材料关键力学性能模型研究
六、联系方式
32243@sdju.edu.cn
