能源與動力工程學院
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                            教授

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                            姓 名 楊軍 性 別
                            職 稱 教授(博導) 畢業學校
                            個人主頁 http://faculty.hust.edu.cn/yangjun5/en/index.htm
                            聯系方式
                            郵 箱 yang_jun@hust.edu.cn
                            通訊地址 湖北省武漢市華中科技大學動力樓 430074
                            個人資料簡介
                            楊軍,華中科技大學教授、博士生導師。本科畢業于清華大學,獲美國普渡大學(Purdue University)博士學位,先后在威斯康星大學(University of Wisconsin)、保羅-謝爾研究院(Paul Scherrer Institut) 從事研究工作?,F任核工程與核技術系主任、院長助理,先進核能系統分析計算中心主任。兼任國際清潔能源論壇理事、中國輻射防護學會教育與科普分會理事、教育部核工程類教指委委員、湖北省核學會理事。擔任英文期刊the International Journal of Advanced Nuclear Reactor Design and Technology (JANDT)編委及多個國際期刊審稿人,“核能前沿科技青年學術論壇”發起人?,F主持國家自然科學基金委專項基金項目及多個國防及企業科研項目。已發表期刊和會議論文60余篇,其中SCI論文20余篇,出版專著、譯著多本。(Researcher ID:  J-3541-2014)

                            教育及工作經歷

                              2000              清華大學工程物理系 學士
                              2003              中國原子能科學研究院 碩士
                              2010              美國普渡大學(Purdue University) 博士
                              2011-2013      美國威斯康星大學(University of Wisconsin)博士后
                              2013-2015      瑞士保羅謝爾研究院(Paul Scherrer Institut)研究人員
                              2015-今          華中科技大學能源與動力工程學院教授

                            研究方向

                              反應堆熱工水力與安全分析
                              核能系統最佳估算與不確定性分析
                              先進反應堆非能動安全系統設計
                              燃料組件臨界熱流密度計算與分析
                              整體效應實驗與分離效應實驗及程序驗證與確認(V&V)
                              反應堆安全過濾排放系統及放廢處理

                            科研項目

                              1. 先進核能系統安全分析中的關鍵問題,基金委專項
                              2. 事故模型的?;淮_定性研究,國防項目
                              3. 整體效應實驗相關模型,企業科技項目
                              4. 航行器中的熱物理與控制耦合研究,自主創新項目

                            代表性論文與專利

                              (1)    Deng, C., Zhang, X., Yang, Y., Yang, J*., 2019b. Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review. Ann Nucl Energy 131, 273-290. [Link]

                              (2)    Dong, S.-c., Yang, J*., 2019. Overview of the test facilities and experimental studies and simulation research on the performance of filtered containment venting systems with wet scrubber. Ann Nucl Energy. In press.

                              (3)    Yang, J*., et al., Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5. Annals of Nuclear Energy 127 (2019) pp. 326-340 [Link]

                              (4)    J. Yang*, D. Suckow, T. Lind And H.-M. Prasser, Study of Level Swell at VEFITA Facility for Filtered Containment Venting System, Progress of Nuclear Energy 113 (2019) pp. 7-17[Link].

                              (5)    Deng, C. Chen, L. Yang, J, et al., Best-estimate calculation plus uncertainty analysis of SBLOCA transient for the scale-down passive test facility. Progress in Nuclear Energy 112, (2019) pp. 191-201 [Link]

                              (6)    J. Yang*,Doo Yong Lee, Shuichiro Miwa, Shao-wen Chen, “Overview of filtered containment venting system in Nuclear Power Plants in Asia”, Annals of Nuclear Energy, 119 (2018), pp. 87-97 [Link]

                              (7)    J. Yang*, M. S. Greenwood, M. Angelis, M. Avery, M. Anderson, M. Corradini, J. Matos, F. Dunn, E. Feldman, “Study of Critical Heat Flux in Natural Convection Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries”, Nuclear Science and Engineering, 180 (2015), pp. 1-13 [Link]

                              (8)    J. Yang*, J. Lim, S. W. Choi, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Behaviors of Passive Safety System under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor”, Progress in Nuclear Energy 83 (2015)pp. 35-42 [Link]

                              (9)    J. Lim, J. Yang, S. W. Choi, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii*, “Assessment of Passive Safety System Performance under Gravity Driven Cooling System Drain Line Break Accident”, Progress in Nuclear Energy, 74 (2014), pp. 136-14 [Link]

                              (10)    J. Lim, S. W. Choi, J. Yang, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii*, “Assessment of Passive Safety System Performance under Main Steam Line Break Accident”, Annals of Nuclear Energy, 64 (2014) pp. 287-294 [Link] [Link]

                              (11)    S. Rassame*, M. Griffiths, J. Yang, D. Y. Lee, P. Ju, S.W. Choi, T. Hibiki, and M. Ishii, “Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture,” Annals of Nuclear Energy, 73 (2014) pp. 53-67  [Link]

                              (12)    S. Rassame*, M. Griffiths, J. Yang, D. Y. Lee, P. Ju, S.W. Choi, T. Hibiki, and M. Ishii, “Experimental Investigation of Void Distribution in Suppression Pool Over the Duration of a Loss of Coolant Accident Using Steam-Water Two-Phase Mixture,” Annals of Nuclear Energy, 75, (2014) pp. 570-580 [Link]  

                              (13)    J. Yang*, S. W. Choi, J. Lim, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Counterpart experimental study of ISP-42 PANDA tests on PUMA facility”, Nuclear Engineering and Design, 258 (2013) pp. 249-257 [Link]

                              (14)    J. Yang*, S. W. Choi, J. Lim, D. Y. Lee, S. Rassame, T. Hibiki, M. Ishii, “Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation”, Nuclear Engineering and Design, 247 (2012) pp. 128-135 [Link]

                              (15)    M. Avery, J. Yang*, M. Anderson, M. Corradini, J. Matos, F. Dunn, E. Feldman, “Critical Heat Flux in TRIGA-Fueled Reactors Cooled By Natural Convection”, Nuclear Science and Engineering 172 (2012) pp. 249-258 [Link]

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