一、第一作者论文（共25篇）

1. **Wu P**; Zhu Y; Ouyang Z; Shan J; Yan X. 不同热电转换系统的热管堆反应性引入事故特性研究. 核技术, 2024.

2. **Wu P**; Liu W; Ouyang Z; Shan J. Research on safety characteristics of heat pipe reactor with semiconductor thermoelectric conversion system. Annals of Nuclear Energy, 2023.

3. **Wu P**; Ouyang Z; Zhu Y; Shan J. 基于KRUSTY带核实验的热管冷却反应堆瞬态分析程序验证. 核技术, 2023.

4. **Wu P**; Liu W; He L; Tang T; Feng M; Shan J; Luo B; Sha H. Experimental study of bottom reflooding for 5×5 non-uniformly heated rod bundle with spacer grid. Progress in Nuclear Energy, 2022.

5. **Wu P**; Ren Y; Feng M; Shan J; Huang Y; Yang W. A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics. Progress in Nuclear Energy, 2022.

6. **Wu P**; Ren Y; Shan J; Huang Y. 压力管式超临界水堆极限事故下"无堆芯熔化"概念评估. 核动力工程, 2021.

7. **Wu P**; Zhang L; Shan J; Zhang B. Researches on Special Thermal Hydraulic Phenomena of Annular Fuel Assembly by Sub-Channel Analysis Code-NACAF. Frontiers in Energy Research, 2021.

8. **Wu P**; Ma Y; Gao C; Liu W; Shan J; Huang Y; Wang J; Zhang D; Ran X. A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications. Nuclear Engineering and Design, 2020.

9. **Wu P**; Gao C; Huang Y; Zhang D; Shan J. Supercritical CO2 Brayton Cycle Design for Small Modular Reactor with a Thermodynamic Analysis Solver. Science and Technology of Nuclear Installations, 2020.

10. **Wu P**; Liu W; Gao C; Ma Y; Shan J. Preliminary safety evaluation of a supercritical carbon dioxide Brayton cycle cooled reactor system under loss-of-flow accident. Nuclear Engineering and Design, 2020.

11. **Wu P**; Novog D. Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water. Nuclear Technology, 2019.

12. **Wu P**; Gao C; Shan J. Development and verification of a transient analysis tool for reactor system using supercritical CO2 Brayton cycle as power conversion system. Science and Technology of Nuclear Installations, 2018.

13. **Wu P**; Yuan Y; Pan J; Shan J. The stability-analysis code FIAT development for density wave oscillations and its application to PV/PT SCWR. Annals of Nuclear Energy, 2017.

14. **Wu P**; Shan J. Transient analysis code development for S-CO2 Brayton cycle based reactor system. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017.

15. **Wu P**; Novog D. Comparison of the subchannel code CTF to steady-state and transient heat transfer experiments at intermediate pressures in water. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017.

16. **Wu P**; Chao F; Wu D; Shan J; Gou J. Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model. Science and Technology of Nuclear Installations, 2017.

17. **Wu P**; Shan J; Xiang X; Zhang B; Gou J; Zhang B. The development and application of a sub-channel code in ocean environment. Annals of Nuclear Energy, 2016.

18. **Wu P**; Xiong X; Shan J; Gou J; Zhang B; Zhang B. Improvement and validation of the wall heat transfer package of RELAP5/MOD3.3. Nuclear Engineering and Design, 2016.

19. **Wu P**; Shan J; Gou J; Leung LKH; Zhang B; Zhang B. Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario. Annals of Nuclear Energy, 2015.

20. **Wu P**; Shan J-Q; Gou J-L; Zhang B; Zhang B; Wang H-N. No-core-melt assessment for Canadian-SCWR under LOCA/LOECC. Nuclear Science and Techniques, 2015.

21. **Wu P**; Gou J; Shan J; Zhang B; Li X. Preliminary safety evaluation for CSR1000 with passive safety system. Annals of Nuclear Energy, 2014.

22. **Wu P**; Gou J; Shan J; Jiang Y; Yang J; Zhang B. Safety analysis code SCTRAN development for SCWR and its application to CGNPC SCWR. Annals of Nuclear Energy, 2013.

23. **Wu P**; Gou J; Shan J; Zhang B; Li X. Preliminary safety analysis of CSR1000. International Conference on Nuclear Engineering, Proceedings, ICONE, 2013.

24. **Wu P**; Dang G-J; Gou J-L; Shan J-Q; Jiang Y; Zhang B; Li X. 超临界水冷堆安全分析程序开发. 核动力工程, 2013.

25. **Wu P**; Gou J; Shan J; Jiang Y; Zhang B; Yang J. LOFA and LOCA analysis on CGNPC SCWR. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, 2012.

二、通讯作者论文（共17篇）

26. Zeng R; Shan J; Ge L; Wang J; **Wu P***. 锂冷快堆斯特林热电转换系统瞬态安全特性研究. 核技术, 2026.

27. Feng M; Ouyang Z; **Wu P***; Shan J. Development and validation of transient analysis code for heat pipe reactor system. Annals of Nuclear Energy, 2026.

28. Liu W; Song Q; Xia Y; Li X; Guo J; Liu Y; **Wu P***; Li Z; Shan J. Research on multi-scale coupling computational methods and code development for pebble bed high-temperature gas-cooled reactors. Annals of Nuclear Energy, 2026.

29. Liu M; **Wu P***; Huang K; Shan J. Development and application of safety analysis code for He-Xe cooled space reactor. Nuclear Engineering and Design, 2025.

30. Zhu J; **Wu P***; Huang Y; Zhu Y; Shan J. Experimental and numerical study of straight channel SCO2 recuperator with transcritical-temperature flow on both side. Nuclear Engineering and Design, 2025.

31. Liu W; Hu S; Xu L; Tang T; Li X; Wang L; **Wu P***; Shan J. 基于全隐算法的螺旋管蒸汽发生器瞬态分析程序开发及验证. 核技术, 2025.

32. Jillani G; Shan J; Xue Q; Liu W; **Wu P***. Design and evaluation of control strategies and control methods for supercritical CO2 Brayton cycle directly cooled reactor system. Applied Thermal Engineering, 2025.

33. Jillani G; Shan J; Xue Q; **Wu P***; Mujahid M. Design of an integrated simulation platform and its application to control system for supercritical CO2 Brayton cycle cooled reactor system. Annals of Nuclear Energy, 2024.

34. Liu W; **Wu P***; Gui M; Shan J; Li Z. Experimental investigation of quench front propagation during reflooding in 5 × 5 rod bundle channel with axial uniform power distribution. Annals of Nuclear Energy, 2024.

35. Xue Q; **Wu P***; Liu M; Shan J; Huang Y. Thermal hydraulic design and mass optimization of a 100-kWe S-CO2 cooled Mars-surface fission reactor system. Annals of Nuclear Energy, 2023.

36. Liu W; **Wu P***; Feng M; Tang T; Shan J; Gui M. 5×5均匀加热棒束底部再淹没实验研究及热工安全分析程序评价. 核技术, 2023.

37. Gui M; Zhu K; Shan J; **Wu P***. Experimental study on coupled quenching behavior in a dual-cooled annular rod channel. Progress in Nuclear Energy, 2023.

38. Xue Q; Feng M; Ma Y; **Wu P***; Shan J; Huang Y. 超临界二氧化碳核能系统负荷运行策略研究. 西安交通大学学报, 2023.

39. Liu W; Yuan H; **Wu P***; Wang T; Shan J. EXPERIMENTAL INVESTIGATION ON THE REFLOODING IN A 5×5 ROD BUNDLE. International Conference on Nuclear Engineering, Proceedings, ICONE, 2022.

40. Gao C; **Wu P***; Liu W; Ma Y; Shan J. Development of a bypass control strategy for supercritical CO2 Brayton cycle cooled reactor system under load-following operation. Annals of Nuclear Energy, 2021.

41. Gao C; **Wu P***; Shan J; Huang Y; Zhang J; Wang L. Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system. Annals of Nuclear Energy, 2020.

42. Gao C; **Wu P***; Shan J. The preliminary safety analysis of a S-CO2 Brayton cycle cooled reactor system. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019.

三、其他合作论文（共19篇）

43. Nava Dominguez A; Azih C; Mendoza Espana AD; Zahlan H; Mazzini G; Musa-Ruscak A; Kassem S; Pucciarelli A; Ambrosini W; Wiltschko F; Otic I; Varju T; Kiss A; **Wu P**; Poplavskaia E. A state-of-the-art review of R&D for the super critical water-cooled reactor technology. Part I economics, thermalhydraulics, safety and licensing. Nuclear Engineering and Design, 2026.

44. Wu Z; Hua Y; **Wu P**; Shan J. 球床式高温气冷堆系统分析程序开发及应用. 原子能科学技术, 2026.

45. Gao C; Zou J; **Wu P**; Shan J; Wang G; Hou Y. Reactor power control system design and dynamic simulation for load maneuvers over full range and entire lifetime of an integrated supercritical CO2 reactor plant. Annals of Nuclear Energy, 2025.

46. Liu W; Shi J; Liu Y; Chen Y; **Wu P**; Hou K; Li X; Zhang Y; He M. Measurement of helium thermophysical properties and modification of the calculation models in the KTA 3102.1 report. Progress in Nuclear Energy, 2025.

47. Gui M; Wang J; Zhou S; Liu Y; Shan J; Liang Y; **Wu P**. Investigation on heat split in a vertical 3 × 3 dual-cooled annular rod bundle. Annals of Nuclear Energy, 2025.

48. Deng Y; Lei X; Liu Q; Liu S; **Wu P**. 并联竖直上升通道内二氧化碳流动不稳定性实验研究. 中国电机工程学报, 2024.

49. Gui M; Guo J; Kong H; **Wu P**; Shan J; Peng Y. Experimental Investigation on Critical Heat Flux in Bilaterally Heated Annulus with equal heat flux on both sides. Nuclear Engineering and Technology, 2023.

50. Gui M; Shan J; Liu Y; **Wu P**; Liang Y; Zhang F. Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle. Annals of Nuclear Energy, 2023.

51. Fan J; Gou J; Shan J; Ge L; **Wu P**. Development and validation of a two-fluid three-field model for the vertical upward flow. Progress in Nuclear Energy, 2021.

52. Mao H; Zhang D; Gao C; **Wu P**; Liu Y; Bi S; Mi Z. 二氧化碳冷却反应堆始发事件和验收准则研究. 核技术, 2020.

53. Zhang B; Chao F; **Wu P**; Gou J; Shan J. Application of high-order numerical algorithm for two-fluid two-pressure model: Hydraulic load analysis. Annals of Nuclear Energy, 2020.

54. Chao F; Shan J; Gou J; **Wu P**; Ge L. Assessment of time and space high-order schemes for two-fluid seven-equation two-pressure model using the reversed water faucet problem. International Conference on Nuclear Engineering, Proceedings, ICONE, 2018.

55. Chao F; Liu D; Shan J; Gou J; **Wu P**. Development of temporal and spatial high-order schemes for two-fluid seven-equation two-pressure model and its applications in two-phase flow benchmark problems. International Journal for Numerical Methods in Fluids, 2018.

56. Chao F; Shan J; Zhang Y; **Wu P**; Gou J; Li J. 两流体双压力模型半隐数值算法研究. 核动力工程, 2018.

57. Chao F; Shan J; Gou J; **Wu P**; Ge L. Study on the algorithm for solving two-fluid seven-equation two-pressure model. Annals of Nuclear Energy, 2018.

58. Yang Z-J; Gou J-L; Shan J-Q; **Wu P**. Analysis of SBLOCA on CPR1000 with a passive system. Nuclear Science and Techniques, 2017.

59. Chao F; Shan J; **Wu P**; Gou J. Comparison of different high-resolution spatial discretization schemes for two-fluid seven-equation two-pressure model. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017.

60. Gou J; **Wu P**; Shan J; Zhang B; Yang J. Development of a safety analysis code SCTRAN for SCWR. International Conference on Nuclear Engineering, Proceedings, ICONE, 2012.

61. Chen X-X; **Wu P**; Shan J-Q. 快堆子通道分析程序ATHAS-LMR模型研究. 原子能科学技术, 2012.