发表研究论文30余篇；获清华大学优秀博士论文。入职以来代表性论文如下： [1]Lin Pan-dong, Nie Jun-feng, Cui Wen-dong, et al. Comparative analysis of irradiation-stimulated hardening in the austenite and ferrite phases of F321 stainless steel [J]. Acta Materialia, 2024, 281:120409. [2]Lin Pan-dong, Nie Jun-feng, Cui Shu-gang, et al. Molecular dynamics study on the ductile-to-brittle transition in W-Re alloy systems [J]. Acta Materialia, 2025, 285:120684. [3]Lin Pan-dong, Nie Jun-feng, Lu Yu-peng, et al. Atomic irradiation defects induced hardening model in irradiated tungsten based on molecular dynamics and CPFEM [J]. International Journal of Plasticity, 2024, 174:103895. [4]Lin Pan-dong, Nie Jun-feng, Cui Wen-dong, et al. Understanding stacking fault tetrahedron formation in FCC stainless steel: a fusion of transmission electron microscopy, molecular dynamics, and machine learning [J]. International Journal of Plasticity, 2024, 183:104157. [5]Lin Pan-dong, Nie Jun-feng, Cui Wen-dong, et al. Experimental and modeling study on irradiation effect of A508-III steel [J]. International Journal of Mechanical Sciences, 2024, 277:109371. [6]Lin Pan-dong, Nie Jun-feng, Cui Shu-gang, et al. Exploring the impact of pre-existing helium bubbles on nanoindentation in tungsten through molecular dynamics simulation [J]. Journal of Materials Research and Technology, 2024, 31:2708-2722. [7]Lin Pan-dong, Nie Jun-feng, Cui Shu-gang, et al. Atomic-scale three-dimensional irradiation-induced defect kinetics models for bcc Fe-based alloys [J]. Journal of Materials Research and Technology, 2024, 31:1250-1257. [8]Lin Pan-dong, Nie Jun-feng, Cui Wen-dong, et al. A multiscale study on the microstructure and hardening models of the irradiation defects on reactor pressure vessel steels: Modelling and experiment [J]. Journal of Materials Research and Technology, 2024, 30:520-531. [9]Lin Pan-dong, Nie Jun-feng, Lu Yu-peng, et al. The effects of different factors on obstacle strength of irradiation defects: An atomistic study[J]. Nuclear Engineering and Technology, 2024, 56(6):2282-2291 [10]Lin Pan-dong, Cui Shu-gang, Nie Jun-feng, et al. Molecular Dynamics Simulations of Displacement Cascades in BCC-Fe: Effects of Dislocation, Dislocation Loop and Grain Boundary[J]. Materials, 2023, 16:7497. [11]Lin Pan-dong, Nie Jun-feng, Cui Wen-dong, et al. Molecular dynamics study on displacement cascade in F321 austenitic stainless steel[J], Applied Physics A, 2024, 130:640. [12]Lin Pan-dong, Nie Jun-feng, Liu Mei-dan, et al. Crystal plasticity finite element model of the brittle-ductile transition temperature and fracture toughness of irradiated A508-3 steel[J], Applied Physics A, 2024, 130:137. [13]Lin Pan-dong, Nie Jun-feng, Lu Yu-peng, et al. Effect of irradiation on mechanical properties of symmetrical grain boundaries in BCC tungsten: an atomistic study[J], Applied Physics A, 2024, 130:69. [14]Cui Wen-dong, Nie Jun-feng, Lin Pan-dong, et al. Molecular dynamics study on the interactions of 1/2[110] edge dislocations with voids and Ni3Al precipitates in FCC Ni[J]. Acta Mechanica Solida Sinica, 2024. 其他论文如下： [15]Lin Pandong, Nie Junfeng, Liu Meidan. Nanoindentation experiment and crystal plasticity study on the mechanical behavior of Fe-ion-irradiated A508-3 steel[J]. Journal of Nuclear Materials. 2022, 571:154002. [16]Lin Pandong, Nie Junfeng, Liu Meidan. Multiscale crystal plasticity finite element model for investigating the irradiation hardening and defect evolution mechanism of A508-3 steel[J]. Nuclear Materials and Energy, 2022, 32:101214. [17]Lin Pandong, Nie Junfeng, Liu Meidan. Study on irradiation effect in stress-strain response with CPFEM during nano-indentation[J]. Nuclear Materials and Energy, 2020, 22:100737. [18]Lin Pandong, Nie Junfeng, Liu Meidan. Investigation of the effects of point defects on the tensile strength of BCC-Fe using molecular dynamics[J]. Applied Physics A, 2021, 127:565. [19]Lin Pandong, Nie Junfeng, Liu Meidan. Study on displacement cascade and tensile simulation by molecular dynamics: the formation and property of point defect[J]. International Journal of Modern Physics B, 2021, 35(10), 2150140. [20]林盼栋，聂君锋，刘美丹. BCC-Fe中1/2[-1-11]刃型位错与[010]位错环相互作用的分子动力学研究[J]. 清华学报(自然科学版)，2022，62(12)：2029-2034. [21]Lin Pandong, Nie Junfeng, Liu Meidan. Modelling the brittle-ductile transition temperature of irradiated A508-3 Steel with CPFEM[C]// Proceedings of the 2022 29th International Conference on Nuclear Engineering. Virtual, Online, 2022. [22]Lin Pandong, Nie Junfeng, Liu Meidan. Study on the effect of different factors of displacement cascades in alpha-Fe by molecular dynamics simulation[C]// Proceedings of the 2020 International Conference on Nuclear Engineering, ICONE 2020. Virtual, Online, 2020. [23]Lin Pandong, Nie Junfeng, Liu Meidan. Point defect effects on tensile strength of BCC-Fe studied by molecular dynamics[C] // Proceedings of the 2020 International Conference on Nuclear Engineering, ICONE 2020. Virtual, Online, 2020. [24]Lin Pandong, Nie Junfeng, Liu Meidan. Effect of annealing temperature on dislocation loop strength and evolution in Fe by molecular dynamics study[C]// Proceedings of the 2021 28th International Conference on Nuclear Engineering. Virtual, Online, 2021. [25]Nie Junfeng, Lin Pandong, Liu Yunpeng, et al. Simulation of the irradiation effect on hardness of Chinese HTGR A508-3 steels with CPFEM [J]. Nuclear Engineering and Technology, 2019, 51(8):1970-1977 [26]Nie Junfeng, Liu Yunpeng, Lin Pandong, et al. A crystal plasticity model with irradiation effect for the mechanical behavior of FCC metals[J]. Acta Mechanica Solida Sinica, 2019,32(6):675-687. [27]Liu Yunpeng, Nie Junfeng, Lin Pandong, et al. Irradiation tensile property and fracture toughness evaluation study of A508-3 steel based on multi-scale approach[J]. Annals of Nuclear Energy, 2020, 138:107157. [28]Liu Meidan, Nie Junfeng, Lin Pandong. Experimental and numerical analysis of the uniaxial tensile properties of F321 austenitic stainless steel at different temperatures[J]. Acta Mechanica Solida Sinica, 2022, 35:409-420. [29]Liu Meidan, Nie Junfeng, Lin Pandong. Irradiation effect on F321 austenitic stainless-steel: nanoindentation and modeling with the crystal plasticity method[J]. Frontiers in Materials, 2022, 9:823539. [30]Liu Yunpeng, Nie Junfeng, Lin Pandong, et al. Study on irradiation fracture property of A508-3 steel by crystal plasticity model[C]// Proceedings of the 27th International Conference on Nuclear Engineering: Nuclear Power Saves the World! ICONE 2019. Tsukuba, Ibaraki, Japan. 2019. [31]Liu Meidan, Nie Junfeng, Lin Pandong. Nanoindentation test of F321 austenitic stainless steel under Fe-ion irradiation[C]// Proceedings of the 2021 28th International Conference on Nuclear Engineering. Virtual, Online, 2021. [32]Wang Dexin, Lin Pandong, Sun Libin, et al. Molecular dynamics study on the effects of temperature and dislocation loop diameter on nano-indentation of Fe[C]// Proceedings of the 2022 29th International Conference on Nuclear Engineering. Virtual, Online, 2022. |