紧凑式换热器传热特性实验室

换热器流动分配实验室

主氦风机气体动力学性能试验平台

中间换热器传热特性试验平台

学术论文

1.Geng Xuyao, Wang Jie*. Simplified Reactor Model for Microreactor Coupled with Helium Closed Brayton Cycle. Nuclear Technology, 2024, Mar 7:1-17.

2.Ma Wenkui, Ye Ping, Gao Yue, Hao Yadong, Yang Xiaoyong*. Optimization of thermodynamic performance and mass evaluation for MW-class space nuclear reactor coupled with noble gas binary mixtures Brayton cycle. Energy, 2024, 293.

3.Wei Xu, Wei Peng, Qi Sun*, Lei Shi. Numerical simulation of the transient graphite oxidation process based on a dynamic mesh method. Progress in Nuclear Energy, 2023, 159: 104669.

4.Ma Wenkui, Ye Ping, Gao Yue, Yang Xiaoyong*. Study on the load loss characteristics of a space nuclear power system with multi brayton loops. Annals of Nuclear Energy, 2023, 185.

5.Qi Sun, Shuisheng He, Bo Liu, Lei Shi, Wei Peng*. Study of particle dynamic resuspension in a recirculation flow using large-eddy simulations. Powder Technology, 2023, 428: 118832.

6.Qunxiang Gao, Peng Zhang, Qi Sun, Ping Zhang, Songzhe Chen, Wei Peng*. Experimental and numerical investigation of sulfuric acid decomposition for hydrogen production via iodine-sulfur cycle. Energy Conversion and Management, 2023, 289: 117167.

7.Wang Xin, Zhao Gang, Qu Xinhe*, Yang Xiaoyong, Wang Jie, Wang Peng. Influence of Cooling Water Parameters on the Thermal Performance of the Secondary Circuit System of a Modular High-Temperature Gas-Cooled Reactor Nuclear Power Plant. Energies, 2023, 16 (18), 6560.

8.Hang Ni, Xinhe Qu, Wei Peng*, Gang Zhao, Ping Zhang. Study of two innovative hydrogen and electricity co-production systems based on very-high-temperature gas-cooled reactors. Energy, 2023, 273: 127206.

9.Qingxiang Hu, Xinhe Qu, Wei Peng*, Jie Wang. Experimental and numerical investigation of turbulent heat transfer enhancement of an intermediate heat exchanger using corrugated tubes. International Journal of Heat and Mass Transfer, 2022, 185: 122385.

10.Ma Wenkui, Ye Ping, Gao Yue, Yang Xiaoyong*. Comparative study on sequential and simultaneous startup performance of space nuclear power system with multi brayton loops. ACTA ASTRONAUTICA, 2022, 199: 142-152.

11.Chuping Yang, Yinan Geng*, Jie Wang. Influence of nitrogen impurities on the characteristics of helium discharge at high pressure, Annals of Nuclear Energy, 2022, 171: 109024.

12.Chuping Yang, Yinan Geng*, Jie Wang. Reaction chain used to describe the process and mechanism of helium breakdown under high pressure, Annals of Nuclear Energy, 2022, 168: 108811.

13.Hu Qingxiang, Wang Jie, Gao Yue, Peng Wei*. Numerical study of thermal-hydraulic and dust-deposition of tube bundles in an intermediate heat exchanger. International Journal of Hydrogen Energy, 2022, 47(63): 27187-27198.

14.Yang CP, Geng YN*, Wang J, Liu XN, Shi ZG. Breakdown voltage of high pressure helium parallel plates and effect of field emission. ACTA PHYSICA SINICA, 2021, Vol.70,No.13: 135102.

15.Xinhe Qu, Gang Zhao*, Jie Wang. Thermodynamic evaluation of hydrogen and electricity cogeneration coupled with very high temperature gas-cooled reactors. International Journal of Hydrogen Energy, 2021, 46(57), 2021: 29065-29075.

16.Qi Sun, Wei Peng*, Xiao Hai. Mathematical model and atomic force microscopy measurements of adhesion between graphite particles and rough walls. Applied Surface Science, 2021, 562: 149976.

17.王捷，王宏，赵钢，杨小勇，叶萍，曲新鹤. 高温气冷堆氦气透平压气机和主氦风机研究进展.清华大学学报 （自然科学版）, 2021,61(4): 350-360.

18.Yang Xiaoyong, Qu Xinhe, Wang Jie. Combined cycle-coupled high-temperature and very high-temperature gas-cooled reactors: part i-cycle optimization. Annals of Nuclear Energy, 2019, 134: 193-204

19.Qu X, Yang X, Wang J*. Off-design performance and power-control strategy for combined cycle coupled with high-temperature gas-cooled reactor. Annals of Nuclear Energy, 2019, 130: 338-346.

20.Li Zhi, Yang Xiaoyong, Wang Jie, Zhang Zuoyi. Off-design performance and control characteristics of space reactor closed Brayton cycle system. Annals of Nuclear Energy, 2019, 128: 318-329.

21.Ming Liang, Yang Xiaoyong, Zhang Youjie, Wang Jie. Experimental study on performance of helium low pressure compressor of HTR-10GT. PROGRESS IN NUCLEAR ENERGY, 2019, 111: 156-164.

22.Xiaokai Sun, Gang Zhao, Peixue Jiang, Wei Peng*, Jie Wang. Influence of hole geometry on film cooling effectiveness for a constant exit flow area. Applied Thermal Engineering, 2018, 130: 1404-1415.

23.Gang Zhao, Ping Ye, Hong Wang, Liang Zhu, Qinzhao Zhang, Jie Wang, Zuoyi Zhang. Endurance test of full-scale mock-up helium circulator for HTR-PM, Nuclear Engineering and Design, 2018, 329: 20-24.

24.Ye Ping*, Zhao Gang, Wang Jie.Experimental study progress on mock-up helium circulator with dry gas seal. Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, 2018,118: 721-722.

25.Qinzhao Zhang*，Jinsong Zhang. Study on the Shaft Seal of Circulator in HTR-PM, Proceedings of HTR 2018, Paper HTR 2018-140, 2018, Warsaw, Poland.

26.Zhao Gang*, Ye Ping, Yang Xiaoyong, Wang Jie. Parametric investigation of supercritical carbon dioxide brayton cycle for high temperature gas-cooled reactor (HTGR). POWER2018-7276.

27.Ye Ping*, Zhao Gang, Wang Jie, Peng Wei.Study of ETF-HC for helium circulator with dry gas seal for HTR-PM. ICAPP 2017, April 24-April 28, 2017, Fukui and Kyoto, Japan.

28.赵熹, 原鲲*, 周羽. GH3128高温拉伸强度设计方法的优化. 清华大学学报（自然科学版）, 2015, 55(9) :998-1002.

29.陈志先，张勤昭，王宏，刘兵. 主氦风机叶片扩压器进口安装角优化设计研究. 核动力工程, 2015, 36(6): 133-137.

30.陈志先，张勤昭，王宏，刘兵, 陈凤. 高温气冷堆主氦风机扩压器设计研究, 第十四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2015年度学术年会, 2015, 中国北京.

部分代表性专利

主要研究成果

1） 高温气冷堆氦气透平循环

建立了闭式布雷登循环的理论体系，为核能气体透平循环系统的研发奠定了理论基础。研究设计了10MW高温气冷堆氦气透平发电系统和商用高温气冷堆氦气透平发电系统，并且研制成功氦气透平压气机组原理性样机。研究设计了移动微堆和空间堆气体透平发电系统，并建立了非核系统集成试验系统。

2） 高温气冷堆主氦风机研制

在国家科技重大专项的支持下，研制完成了世界首台套大功率电磁轴承主氦风机工程样机，突破了主氦风机总体集成技术、三维高效叶轮设计及制造技术、兼具能动与非能动功能的风机挡板技术等多项重大关键技术，已获授权12项发明专利。该成果是我国自主创新在先进核能核心装备技术上的重大突破，采用国产电磁轴承的主氦风机具有完全自主知识产权，成果已应用在高温气冷堆示范工程项目及后续多个高温气冷堆工程项目中。主氦风机技术达到世界领先水平，获评教育部2014年度 “中国高等学校十大科技进展”。

3）高温气冷堆工艺热综合利用

开展了高温气冷堆联合循环发电系统的特性研究，提出了高温气冷堆工业供热系统优化设计方法，建立超高温气冷堆热电氢多联产系统设计方案，为高温和超高温气冷堆的工艺热综合利用提供设计参考。同时，开展了超高温气冷堆与工艺热利用系统耦合特性分析，获得耦合系统的主要参数的变化规律，研究了关键参数和设备对耦合特性的影响，设计和制定超高温气冷堆与热化学循环制氢及其他工艺热利用系统耦合方案。研究成果可以为超高温气冷堆工艺热应用提供设计依据。

4）石墨颗粒行为研究

研究事故工况下放射性石墨粉尘行为对于高温气冷堆核安全分析具有重要意义。研究室对石墨粉尘颗粒产生、沉积扩散、凝并碰撞、事故排放等全过程进行了研究，提出了“振动信号和可视化结合”的实验方法，建立了球形燃料元件碰撞磨损的动力学模型，揭示了相干结构及大温度梯度下粉尘输运机理，发展了颗粒演化的“矩-分布”耦合求解方法，建立了“粗糙壁面-颗粒”粘附作用模型，发展了单层/多层颗粒重悬浮模型以及放射性粉尘事故排放评估方法。研究成果成功应用于我国高温气冷堆示范工程HTR-PM核安全评审，并获得了中国颗粒学会青年颗粒学奖和自然科学奖二等奖。