国家自然科学基金面上项目，ADS用弥散型嬗变核燃料辐照力学行为的多层级均匀化研究， 12472213，2025.01-2028.12，52.39万，主持/在研

国家自然科学基金青年基金，U-10Mo合金的燃料的辐照脆化和强度退化机理研究， 12102094，2022.01-2024.12，30万，主持/在研

上海市“扬帆计划”项目，U-10Mo/Al单片式燃料元件辐照后退火起泡行为研究， 21YF1402200，，2021.05-2024.04，20万，主持/结题

中国核动力研究设计院重点实验室基金，U-10Mo单片型燃料元件的辐照变形与失效机理研究，2021.10-2023.09，20万，主持/结题

 国家自然科学基金面上项目，ADS用弥散型嬗变核燃料辐照力学行为的多层级均匀化研究， 12472213，2025.01-2028.12，52.39万，主持/在研

国家自然科学基金青年基金，U-10Mo合金的燃料的辐照脆化和强度退化机理研究， 12102094，2022.01-2024.12，30万，主持/在研

上海市“扬帆计划”项目，U-10Mo/Al单片式燃料元件辐照后退火起泡行为研究， 21YF1402200，，2021.05-2024.04，20万，主持/结题

中国核动力研究设计院重点实验室基金，U-10Mo单片型燃料元件的辐照变形与失效机理研究，2021.10-2023.09，20万，主持/结题

[1]       Xiaobin Jian, Jing Zhang, YongLi, Shurong Ding*, Skeleton-creep based bubble growth model and multi-scalemechanical constitutive model for U-10Mo fuels under irradiation, InternationalJournal of Plasticity, 2023, 163(103557), 1-26.

[2]       GuochenDing, Jing Zhang, Jie Wang, Yong Li, XiaobinJian*, Shurong Ding*, Yongjun Deng, Modeling and tests on the damage andfracture behaviors of non-irradiated zirconium alloys with different hydrogenconcentrations at RT and 350°C, Journal of Nuclear Materials, 2023, 587(154726),1-20. 

[3]       YunmeiZhao*, Zhenyue Chen, Xiaobin Jian*,A high-generalizability machine learning framework for analyzing thehomogenized properties of short fiber-reinforced polymer composites, Polymers,2023,15(3962), 1-27. 

[4]       Xiaobin Jian, Yunmei Zhao*,Shurong Ding*, Predictionand deformation mechanism analysis of high porosity in U-10Mo monolithic fuelsat high burnup, Metals, 2023, 12(1693), 1-13.

[5]       Xiaobin Jian, Feng Yan,Xiangzhe Kong, Yong Li, Shurong Ding*, Further development of the fission gasswelling model for U-10Mo fuels, Journal of Nuclear Materials, 2022,565(153769),1-13. 

[6]       Xiaobin Jian, Xiangzhe Kong,Shurong Ding*, A mesoscale stress model for irradiated U-10Mo monolithic fuelsbased on evolution of volume fraction/radius/internal pressure of bubbles,Nuclear Engineering and Technology, 2019, 51(6),1575-1588.

[7]       Xiaobin Jian, Feng Yan,Xiangzhe Kong, Shurong Ding*, Effects of U-Mo irradiation creep coefficient onthe mesoscale mechanical behavior in U-Mo/Al monolithic fuel plates, NuclearMaterials and Energy, 2019, 21(100706), 1-11.

[8]       Xiaobin Jian, Shurong Ding*,Thermal creep effects of aluminum alloy cladding on the irradiation inducedmechanical behavior in U-10Mo/Al monolithic fuel plates, Nuclear Engineeringand Technology, 2020, 52(4), 802-810.

[9]       XiaoxiaoMao1, Xiaobin Jian1,Haoyu Wang, Jingyu Zhang, Jibin Zhang, Feng Yan, Hongyang Wei, Shurong Ding*,Yuanming Li*, Thermo-mechanical coupling behavior analysis for a U-10Mo/Almonolithic fuel assembly, Nuclear Engineering and Technology, 2021, 53(9),2937-2952. 

[10]    XiaoxiaoMao1, Xiaobin Jian1,Jingyu Zhang1, Feng Yan, Shurong Ding*, Yongzhong Huo, Haoyu Wang,Lin Zhang, Yuanming Li, Effects of U-Mo irradiation creep performance on theThermo-mechanical coupling behavior in U-Mo/Al monolithic fuel assemblies, Frontiersin Energy Research, 2021, 9(676881), 1-16.