吴迪 - 哈尔滨工程大学 - 核科学与技术学院

个人简介

吴迪，女，黑龙江哈尔滨人，工学博士，2022年6月毕业于西安交通大学核科学与技术专业，2022年7月进入哈尔滨工程大学核学院工作。主要研究方向为先进核反应堆热工水力特性研究、反应堆系统多物理场耦合技术研究、装载事故容错燃料的反应堆热工安全特性研究、核动力系统多目标优化算法研究。现作为负责人主持国家自然科学基金1项（青年），黑龙江省自然科学基金1项（联合引导），中央高校基本业务费1项，中国船舶工业集团公司第七〇八研究所及中国核电工程公司横向课题各1项。发表论文20余篇，其中SCI论文14篇，授权或申请发明专利3项。教育经历 2018.09-2022.06：西安交通大学-核科学与技术-博士学位 2016.09-2018.06：西安交通大学-核能与核技术工程-硕士学位（推免） 2012.08-2016.06：哈尔滨工程大学-核科学与核技术-学士学位工作经历 2022.07-至今：哈尔滨工程大学核科学与技术学院讲师 2020.11-2021.12：慕尼黑工业大学核能系访问学者

研究领域

1. 先进核反应堆热工水力特性研究 2. 反应堆系统多物理场耦合技术研究 3. 装载事故容错燃料的反应堆热工安全特性研究 4. 核动力系统多目标优化算法研究

近期论文

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2023年： Wu D, Gui MY*, Cheng J, et al. Condensation enhancement experiment investigation of pure steam and steam-air mixture over the chrome-plated tube with different plating thickness[J]. Progress in Nuclear Energy, 2023, 166: 104971. Han Y, Wu D*, Cheng J, et al. Optimal design and analysis of lubricating oil system in marine nuclear power based on adaptive genetic algorithm[J]. Progress in Nuclear Energy, 2023, 166: 104937. 2021年： Wang CL†, Wu D†, Gui MY, et al. Flow blockage analysis for fuel assembly in a lead-based fast reactor[J]. Nuclear Engineering and Technology, 2021. (SCI: 000687132200010) (共同一作) 2020年： Wu D, Wang CL, Gui MY, et al. Improvement and validation of a sub-channel analysis code for a lead-cooled reactor with wire spacers[J]. International Journal of Energy Research, 2020. (SCI: 000577703000001; EI: 20204209361593) Wu D, Gui MY, Sun H, et al. Preliminary neutronic/ thermal-hydraulic evaluation and safety system optimization of PWR loaded with fully ceramic microencapsulated fuel[J]. Progress in Nuclear Energy, 2020, 122: 103261. (SCI: 000525863200004; EI: 20200508117970) Wu D, Gui MY, Zhang R, et al. Preliminary optimization of emergency core cooling system with accident-tolerant fuels[J]. Annals of Nuclear Energy, 2020, 142: 107411. (SCI: 000526111700038; EI: 20200908236709) Wu D, Gui MY, Zhang DL, et al. Preliminary neutronic/thermal-hydraulic and safety assessment of pressurized water reactor loaded with fully ceramic microencapsulated fuel[C]. International Topical Meeting on Advances in Thermal Hydraulics, Paris, France, Mar. 31~Apr. 3, 2020. Song GL, Wu D, Sun R, et al. Theoretical study of steady-state characteristics of natural circulation system[J]. Annals of Nuclear Energy, 2020, 147: 107663. (SCI: 000561485300010; EI: 20202708903389) Gui MY, Tian WX, Wu D, et al. Study on CHF characteristics in narrow rectangular channel under complex motion condition[J]. Applied Thermal Engineering, 2020, 166: 114629. (SCI: 000512220900029; EI: 20194807747582) Gui MY, Tian WX, Wu D, et al. Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition[J]. Nuclear Engineering and Technology, 2020. (SCI: 000636560800011) Deng J, Lu Q, Wu D, et al. Sub-channel code development of Lead-Bismuth eutectic fast reactor available for multiple fuel assembly structures[J]. Annals of Nuclear Energy, 2020, 149: 107769. (SCI: 000581278600014; EI: 20203609130361) 2019年： Wu D, Gui MY, Zhang J, et al. Code development and characteristics analysis for Leak Before Break in the pipelines of Sodium-cooled Fast Reactor[J]. Annals of Nuclear Energy, 2019: 777~794. (SCI: 000484649800075; EI: 20192907205037) Wu D, Gui MY, Wang CL, et al. Neutronic and Thermal-hydraulic Safety Analysis of Pressurized Water Reactor Loaded with Fully Ceramic Microencapsulated Fuel[C]. 12th Joint International Symposium on Nuclear Science and Technology, UT-XJTU-SJTU joint Workshop, Shanghai, China, Dec. 1-4, 2019.