基本信息

 

吴 攀

工学博士 副教授

核反应堆安全与运行研究室

能动学院

 

 

   吴攀副教授毕业于西安交通大学,获核工程硕士、博士学位,后赴加拿大麦克马斯特大学从事博士后工作。201510月加入西安交通大学核科学与技术学院,任职至今。目前主持或参与多项国家自然科学基金、国家重点研发计划和校企横向课题,发表论文近50篇。

 

联系方式

 

地址:西安交通大学东校区北二楼8705办公室,710049

办公电话:029-82663769

邮箱:wupan2015@mail.xjtu.edu.cn

个人主页:wupan2015.gr.xjtu.edu.cn

 

站点计数器
学术方向及研究项目

  • 先进反应堆安全系统设计及安全分析
  • 反应堆热工水力分析
  • 反应堆瞬态分析程序开发及改进
  • 超临界二氧化碳布雷顿循环

 

项目编号项目名称主持/参与项目类型 委托单位
1Establish Design-basis Accidents and Perform Preliminary Safety Analyses of CANDU SCWR主持技术服务 Canadian Nuclear Laboratories
2超临界二氧化碳核动力系统热工瞬态分析程序开发主持技术开发 中国核动力研究设计院
3超临界二氧化碳直接冷却快堆的瞬态特性及控制策略研究主持基金委项目 国家基金委
4蒸汽发生器二次侧非能动余热排出系统程序模型优化研究主持技术开发 中国核动力研究设计院
5反应堆辐照生产锎-252理论计算研究主持技术开发 中国原子能科学研究院
6事故分析方法、限制准则及系统分析程序模型验证研究主持技术开发 中国核动力研究设计院
7系统热工分析程序研制主持技术开发 中国核动力研究设计院
8两流体双压力模型在系统分析程序中的应用研究主持技术开发 中国核动力研究设计院
9用于压水堆核电厂多尺度瞬态分析的三维三流场两相流模型及高保真高效算法研究参与基金委项目国家基金委
10两流体双压力模型数值算法研究及其在多尺度核电厂系统瞬态分析中的应用参与基金委项目国家基金委
11MOX堆芯事故分析程序模块化开发与验证参与横向课题中国原子能科学研究院
12超临界二氧化碳******设计分析平台研制参与军工项目中国核工业集团

 

教育工作经历

 2018.9  ——至今         西安交通大学 副教授

 

 2015.10——2018.9     西安交通大学 讲师

 

 2016.06——2017.06   加拿大麦克马斯特大学 博士后

 

 2010.09——2015.09   西安交通大学 博士

 

 2006.09——2010.07   西安交通大学 学士

论文发表情况

SCI 论文

  1. P. Wu, C. Gao, and J. Shan, “Development and Verification of a Transient Analysis Tool for Reactor System Using Supercritical CO2 Brayton Cycle as Power Conversion System,” Sci. Technol. Nucl. Install., vol. 2018, no. Article ID 6801736, 2018.
  2. P. Wu and D. Novog, “Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water Pan,” Nucl. Technol., vol. 0, no. 0, pp. 1–13, 2018. DOI: 10.1080/00295450.2018.1495000.
  3. F. Chao, J. Shan, J. Gou, P. Wu, and L. Ge, “Study on the algorithm for solving two-fluid seven-equation two-pressure model,” Ann. Nucl. Energy, vol. 111, pp. 379–390, 2018.
  4. F. Chao, D. Liu, J. Shan, J. Gou, and P. Wu, “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,” Int. J. Numer. Methods Fluids, vol. 88, pp. 169–192, 2018.
  5. P. Wu, Y. Yuan, J. Pan, and J. Shan, “The stability-analysis code FIAT development for density wave oscillations and its application to PV/PT SCWR,” Ann. Nucl. Energy, vol. 110, 2017.
  6. P. Wu, F. Chao, D. Wu, J. Shan, and J. Gou, “Implementation and Comparison of High-Resolution Spatial Discretization Schemes for Solving Two-Fluid Seven-Equation Two-Pressure Model,” Sci. Technol. Nucl. Install., vol. 2017, 2017.
  7. Z. Yang, J. Gou, J. Shan, and P. Wu, “Analysis of SBLOCA on CPR1000 with a passive system,” Nucl. Sci. Tech., vol. 28, no. 10, 2017.
  8. P. Wu, J. Shan, X. Xiang, B. Zhang, J. Gou, and B. Zhang, “The development and application of a sub-channel code in ocean environment,” Ann. Nucl. Energy, vol. 95, pp. 12–22, 2016.
  9. P. Wu, X. Xiong, J. Shan, J. Gou, B. Zhang, and B. Zhang, “Improvement and validation of the wall heat transfer package of RELAP5/MOD3.3,” Nucl. Eng. Des., 2016.
  10. P. Wu, J. Shan, J. Gou, L. K. H. Leung, B. Zhang, and B. Zhang, “Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario,” Ann. Nucl. Energy, vol. 81, pp. 306–319, 2015.
  11. P. Wu, J. Q. Shan, J. L. Gou, B. Zhang, B. Zhang, and H. N. Wang, “No-core-melt assessment for Canadian-SCWR under LOCA/LOECC,” Nucl. Sci. Tech., vol. 26, no. 2, 2015.
  12. P. Wu, J. Gou, J. Shan, B. Zhang, and X. Li, “Preliminary safety evaluation for CSR1000 with passive safety system,” Ann. Nucl. Energy, vol. 65, pp. 390–401, 2014.
  13. P. Wu, J. Gou, J. Shan, Y. Jiang, J. Yang, and B. Zhang, “Safety analysis code SCTRAN development for SCWR and its application to CGNPC SCWR,” Ann. Nucl. Energy, vol. 56, pp. 122–135, 2013.

 

一般期刊论文及会议论文:

  1. P. Wu, C. Gao, H. Wang, and J. Shan, “Supercritical CO2 Brayton CycleDesign for Lead Fast Reactor withan Integrated Thermodynamic anlaysis code,” in Advances inSupercriticalCarbon Dioxide(SCO2) in Thermaland Enengy Sciences, 2018.
  2. P. Wu, “Safety analyses of CSR1000 during the sliding pressure startup procedure,” in 2018 SCWR Information Exchange Meeting, 2018.
  3. C. Gao, P. Wu, J. Shan, and B. Zhang, “Development of A Transient Analysis Code for S-CO2 Power Conversion System,” in The 6th International Supercritical CO2 Power Cycles Symposium, 2018.
  4. 吴攀, “超临界二氧化碳布雷顿循环在核能领域的应用,” 2018核科学技术军民融合创新发展论坛, 2018.
  5. P. Wu and D. Novog, “Comparison of the Subchannel Code Ctf To Steady-State and Transient Heat Transfer Experiments At Intermediate Pressures in Water,” in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2017.
  6. P. Wu and J. Shan, “Transient Analysis Code Development for S-CO2 Brayton Cycle Based Reactor System,” in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2017.
  7. P. Wu, Y. Yuan, J. Pan, and J. Shan, “Startup Procedure Optimization of Canadian SCWR in Consideration of Density-Wave Oscillations,” in The 8th International Symposium on Super-Critical Water-cooled Reactors, 2017.
  8. F. Chao, Y. Wu, J. Shan, P. Wu, and J. Gou, “Comparison Of Different High-Resolution Spatial Discretization Schemes for Two-Fluid Seven-Equation Two-Pressure Model,” in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2017.
  9. Y. Yuan, J. Shan, P. Wu, and J. Gou, “The Startup Control System Analysis of a SupercriticalPressure Light Water-Cooled Reactor CSR1000,” in The 8th International Symposium on Super-Critical Water-cooled Reactors, 2017.
  10. Y. Yuan, J. Shan, P. Wu, and J. Gou, “Improvement at wide-scope wall heat transfer package model of SCTRAN,” in The 8th International Symposium on Super-Critical Water-cooled Reactors, 2017.
  11. 巢飞, 单建强, 吴怡睿, 吴攀, “高阶精度空间离散化方案在两流体双压力模型中应用研究,” 西部核学会2017年联合学术年会, 2017.
  12. 巢飞, 单建强, 张勇, 吴攀, 苟军利, 李健, “两流体双压力模型半隐数值算法研究,” 国防科技工业核动力技术创新中心暨核反应堆系统设计技术重点实验室2017年度学术年会, 2017.
  13. 巢飞, 吴怡睿, 单建强, 吴攀, “两流体双压力模型高阶精度数值算法研究,” 第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会, 2017.
  14. P. Wu, F. Chao, J. Shan, L. Leung, and J. Gou, “Safety analysis of loss of coolant accident events for the Canadian Supercritical Water-cooled Reactor,” CNL Nucl. Rev., pp. 1–13, 2016.
  15. 巢飞, 单建强, 吴攀, 杨萌, “经典两流体模型不适定性分析及改进研究,”西部核学会2016年联合学术年会, 2016.