2015.10～2018.9   日本东北大学，量子能源工程，工学博士

2012.9～2015.3    上海交通大学，核能科学与工程，硕士

2008.9～2012.6    重庆大学，动力工程学院，核工程与核技术专业

2023.4～今 重庆大学，能源与动力工程学院/核能技术创新研究院，副教授

2021.12～2023.3 中国核动力研究设计院，设计所，高级工程师

2018.9～2021.11 中国核动力研究设计院，设计所，工程师

燃料性能分析与评价

核材料设计与优化

核材料使役行为评价

《核动力工程》青年编委

[1] 其他纵向，铅铋腐蚀产物迁移及沉积行为，2023至2026-06，200万元，在研，主持。

[2] 国家自然科学基金青年科学基金，52201091，2023-01至 2025-12,30万元，在研，主持。

[3] 横向项目，压水堆一回路燃料表面污垢沉积试验，2024至2025,180万元，结题，主持。

[4] 横向项目，FeCrAl腐蚀试验，2024至2026，60万元，在研，主持。

[5] 四川省科学技术厅，应用基础研究, 2021YJ0512 ,2021-04至 2023-03, 10万元,结题，主持。

期刊论文：

[1] Duan Z, Xiang H, Qiao P, et al. Progress in understanding the formation and deposition behaviors of corrosion and oxidation products in lead-cooled fast reactors [J]. Progress in Nuclear Energy, 2025, 184: 105742.

[2] Duan Z, Yuan B, Wen Q, et al. Effects of internal pressure and heating rate on the burst behaviors of Cr-coated cladding during simulated LOCA testing [J]. Annals of Nuclear Energy, 2024, 204: 110548.

[3] Duan Z, Yuan B, Wen Q, et al. Preliminary Investigation on Burst Behaviors of Zr-Based Cladding Under Simulated LOCA Conditions; proceedings of the International Conference on Nuclear Engineering, F, 2024 [C]. American Society of Mechanical Engineers.

[4] Duan Z, Zhao Y, Lv L, et al. Overview of performances and service behaviors of uranyl nitrate solution for medical aqueous homogeneous reactors [J]. Progress in Nuclear Energy, 2023, 157: 104591.

[5] Duan Z, Yang H, Kano S, et al. Investigation on the feasibility of the interaction between NiO and Mo oxide for self-healing intelligence on the nuclear fuel cladding [J]. Journal of Nuclear Science and Technology, 2019, 56(12): 1103-9.

[6] Duan Z, Yang H, Kano S, et al. Oxidation and electrochemical behaviors of Al2O3 and ZrO2 coatings on Zircaloy-2 cladding by thermal spraying [J]. Surface and Coatings Technology, 2018, 334: 319-27.

[7] Duan Z, Yang H, Kano S, et al. Application of chemical interaction between (Fe, Cr) oxides and Mo oxide at high temperature for self-healing intelligence on nuclear fuel cladding in LWRs [J]. Journal of Nuclear Science and Technology, 2018, 55(12): 1402-11.

[8] Duan Z, Yang H, Satoh Y, et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors [J]. Nuclear Engineering and Design, 2017, 316: 131-50.

[9] Duan Z, Arjmand F, Zhang L, et al. Investigation of the corrosion behavior of 304L and 316L stainless steels at high-temperature borated and lithiated water [J]. Journal of Nuclear Science and Technology, 2016, 53...