发表论文
2024年：
He X, Wu D*, Cheng J, et al. Numerical investigation of flow and heat transfer characteristics of special-shaped fuel[J]. International Communications in Heat and Mass Transfer, 2024, 156: 107691.
Kong DY, Gao ZB, Wu D*, et al. Uncertainty analysis of neutronic/thermal-hydraulic coupling in pressurized water reactor fuel assemblies[J]. Annals of Nuclear Energy, 2024, 207: 110783.
Wu D, Gui MY*, Cheng J, et al. Research on the applicability of the IWF model to coupled heat transfer between intra- and inter-assembly in LFR[C]. 31st International Conference on Nuclear Engineering, Prague, Czech Republic, Aug. 4-8, 2024.
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.
