姓名: |
郭俊良 |
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性别: |
男 |
英文名: |
Guo Junliang |
人才称号: |
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职称: |
助理研究员 |
职务: |
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专业: |
工程热物理、核能科学与工程 |
所在机构: |
能源与动力工程系 |
个人主页: |
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邮箱: |
guojl@tju.edu.cn |
办公地点: |
热动力大楼(34号楼)A252 |
传真: |
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办公电话: |
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主要学历: |
2019.09-2024.12 西安交通大学,能源与动力工程学院,工学博士
2015.09-2019.06 哈尔滨工程大学,核科学与技术学院,工学学士
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主要学术经历: |
2024.12-至今 天津大学,机械工程学院,博士后
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主要研究方向: |
沸腾传热与汽液两相流;
核反应堆热工水力与安全分析
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主要讲授课程: |
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主要学术兼职: |
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主要学术成就: |
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主要科研项目: |
1.国家重点研发计划,核燃料元件性能分析模型与方法研究,冷壁效应和棒束弯曲对CHF影响规律研究,2019-2023,2476万,参与;
2.国家重点研发计划,核燃料元件性能分析模型与方法研究,高精度子通道分析方法与验证技术研究,2019-2023,228万,参与;
3.中国核动力研究设计院横向课题,混合型并联通道流量、热流分配特性机理研究,2021-2023,145万,参与;
4.中国原子能科学研究院横向课题,环形燃料再淹没试验过程中传热特性研究,2023-2024,433万,参与;
5.中国原子能科学研究院横向课题,混合组件横流试验,148万,参与;
6. 中国原子能科学研究院横向课题,环形燃料3×3棒束再淹没安全性能试验,194万,参与
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代表性论著: |
1. Junliang Guo, Jianqiang Shan, Li Jiang, Yujiao Peng, Miao Gui*. Mechanistic Model of Critical Heat Flux in Rod Bundles Based on a High-Precision Subchannel Code[J]. Nuclear Engineering and Design, 2024, 422: 113161.
2. Junliang Guo, Jianqiang Shan, Bowen Yang, Yujiao Peng, Miao Gui*, Songtao Ji. DNBR Limit Analysis for the Inner channel of Annular Fuel[J]. Annals of Nuclear Energy, 2024, 198: 110295.
3.Junliang Guo, Jianqiang Shan, Li Jiang, Yujiao Peng, Shan Zhou, Miao Gui*. Prediction of Critical Heat Flux in Rod Bowing Geometries by Coupled Subchannel analysis and Mechanistic model[J]. Annals of Nuclear Energy, 2024, 200: 110401.
4. Junliang Guo, Yujiao Peng, Huanjun Kong, Miao Gui, Jianqiang Shan*. A Mechanistic Model for Prediction of Critical Heat Flux in Vertical Internally Heated Annuli[C]. 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10) November 26-29, 2023, Jeju, Korea.
5.Miao Gui, Junliang Guo, Huanjun Kong, Pan Wu, Jianqiang Shan*, Yujiao Peng. Experimental investigation on critical heat flux in bilaterally heated annulus with equal heat flux on both sides[J]. Nuclear Engineering and Technology, 2023, 55: 3313-3319.
6. Miao Gui, Wei Liu, Junliang Guo, Yang Liu, Jianqiang Shan*, Huanjun Kong. Experimental investigation on critical heat flux enhancement by mixing-vanes spacer grid in a vertical annular geometry[J]. Nuclear Engineering and Design, 2023, 401: 112087.
7. Junliang Guo, Huanjun Kong, Miao Gui, Yang Liu, Jianqiang Shan*, Laurence K. H. Leung. Fluid-to-Fluid modelling of CHF at High-Pressure subcooled water conditions[J]. Nuclear Engineering and Design, 2022, 386: 111577.
8.Junliang Guo, Huanjun Kong, Miao Gui, Yujiao Peng, Jianqiang Shan*. The experimental study on critical heat flux in vertical eccentric internally heated annuli[C]. Proceedings of the 2022 29th International Conference on Nuclear Engineering (ICONE29) August 8-12, 2022, Shenzhen, China.
9. Yang Liu, Wei Liu, Jianqiang Shan*, David R. Novog, Bo Zhang, Miao Gui, Junliang Guo. Critical heat flux measurement and visualization in R-134a on a vertical single rod with and without mixing-vanes spacer: The characteristics and phenomenon of critical heat flux[J]. Annals of Nuclear Energy, 2021, 160:108399.
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