张斌
1. 职称：教授、博士生导师
2. 研究方向：核反应堆热工与安全、核反应堆严重事故分析和现象学研究、核反应堆事故后源项分析研究、移动粒子法模型开发及在严重事故分析中的应用研究
3. 学习经历：
1995年9月至1999年7月在西安交通大学核热能与工程专业学习获学士学位，研究方向核热能与工程；
1999年9月至2006年3月在西安交通大学核科学与技术专业学习获博士学位，研究方向为核反应堆安全分析；
2007年10月至2010年6月在日本国立九州大学应用量子物理和核工程专业学习获博士学位，研究方向为核安全分析；
4. 工作经历：
2001年2月至今在西安交通大学能动学院核科学与技术学院任助教、讲师、副教授、教授；
2010年7月至2011年3月在日本国立九州大学应用量子物理和核工程系任客座副教授；
2011年4月至2013年3月在日本国立九州大学应用量子物理和核工程系任副教授。
5. 主讲课程：
《核反应堆安全分析》、《核电厂系统与动力设备》、《核工程概论》（英语）、《压水堆核电厂运行》及《核安全概论》等5门本科生课程和《核反应堆工程设计方法》、《核电厂严重事故分析》、《Advance in Severe Accident Analysis of Nuclear Reactors》等3门研究生课程
6. 代表著作和论文：
a) 代表论文

1) Bin Zhang*, Fei Chao, Pan Wu, et al. Application of high-order numerical algorithm for two-fluid two-pressure model: Hydraulic load analysis[J]. Annals of Nuclear Energy, 2020, 143.

2) Bin Zhang*, Jian Deng, Maolin Jing, et al. A newly-Developed Suppression Pool Model Based on ISAA Code[J]. Nuclear Science and Engineering, 2021, 195(8): 853-863.

3) Bin Zhang*, Mengwei Zhang, Cheng Peng, et al. Numerical Investigation of Dryout Heat Flux and Heat Transfer Characteristics in Core Debris Bed of SFR After Severe Accident[J]. Nuclear Engineering and Design, 2019, 193(1-2): 115-130.

4) Bin Zhang*, Pengcheng Gao, Tao Xu, et al. Performance Evaluation of Accident Tolerant Fuel under Station Blackout Accident in PWR Nuclear Power Plant by Improved ISAA code [J]. Nuclear Engineering and Technology, 2022, 54(7): 2475-2490.

5) Bin Zhang*, Pengcheng Gao, Tao XU, et al. Severe Accident Analysis of the Dual-Functional Lithium-Lead Test Blanket Module Using Isaa-Dfll Code[J]. Thermal Science, 2022, 26(5): 4079-4093.

6) PengchengGao, BinZhang*, JishenLi, ShaoweiTang, JianqiangShan. Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: Module verification and application in CAP1400 [J]. Annals of Nuclear Energy, 2021, 158(2-3):108305.

7) PengchengGao, BinZhang*, JishenLi, ShaoweiTang, JianqiangShan. Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment[J]. Nuclear Engineering and Technology, 2021, 54(1):138-151.

8) PengchengGao, BinZhang*, JishenLi, ShaoweiTang, JianqiangShan. Development of Mechanistic Cladding Rupture Model for Integrated Severe Accident Code ISAA. Part II: DVI Line Small-Break LOCA in CAP1400[J]. Annals of Nuclear Energy, 2021, 164(2-3):108613.

9) Pengcheng Gao, Bin Zhang*, Jianqiang Shan. Study on the effect of Flow Blockage due to Rod Deformation in QUENCH Experiment [J]. Nuclear Engineering and Technology, 2022, 54(8): 3154-3165.

10) Pengcheng Gao, Bin Zhang*, Jishen Li, et al. Study on the Influence of Flow Blockage in Severe Accident Scenario of CAP1400 Reactor [J]. Nuclear Engineering and Technology, 2023, 55(3):999-1008.

11) Jianping Long, Bao-Wen Yang, Ting Wu, Bin Zhang*. Numerical investigation of turbulent mixed convection flow and heat transfer characteristics of 2×2 subchannels with spacer grid [J]. Energy Science & Engineering, 2023, 11(3):1005-1024.

12) Jianping Long, Bao-Wen Yang, Bin Zhang*, Sipeng Wang. Research on the effects of local throttling on thermal-induced two-phase flow instabilities in the typical coolant open-channel system in the nuclear reactor core[J]. Thermal Science, 2022, 26, (5B): 4095-4105.

13) Jianping Long, Bin Zhang, Bao-Wen Yang, Sipeng Wang, Review of researches on coupled system and CFD codes[J]. Nuclear Engineering and Technology, 2021, 53(9): 2775-2787.

14) Jianping Long, Bao-Wen Yang, Bin Zhang*, Sipeng Wang. Computational case study on upward two-phase flow in vertical circular pipe based on CFD approach: Multidimensional flow instabilities investigation[J]. Progress in Nuclear Energy, 2022, 144(Feb.): 104085.1-104085.15.

15) Chunming Teng, Bin Zhang*, Jianqiang Shan, et al. Development of relocation model for debris particles in core disruptive accident analysis of sodium-cooled fast reactor[J]. Nuclear Engineering and Design, 2020, 368: 110795.

16) Chunming Teng, Bin Zhang*, Jianqiang Shan. Study on relocation behavior of debris bed by improved bottom gas-injection experimental method[J]. Nuclear Engineering and Technology, 2021, 53(1): 111-120.

17) Shengfeng Zhang, Bin Zhang*, Xiaoxing Liu, et al. Application of a particle-grid hybrid method in multiphase flow calculation[J]. Journal of Nuclear Science and Technology, 2020, 57(11): 1199-1214.

18) Yuan Yuan, Jianqiang Shan, Bin Zhang*, et al. Accident analysis of heat pipe cooled and AMTEC conversion space reactor system[J]. Annals of Nuclear Energy, 2016, 94(2016): 706-715.

19) Yuan Yuan, Jianqiang Shan, Bin Zhang*, et al. Study on startup characteristics of heat pipe cooled and AMTEC conversion space reactor system[J]. Progress in Nuclear Energy, 2016, 86(2016): 18-30.

20) Pengcheng Gao, Hao Yang, Bin Zhang*, Jianqiang Shan. Development of PWR Lower Head Failure Model for Severe Accident Analysis[J]. Nuclear Engineering and Design, 2022.03, volume 403: 112142.

21) Pengcheng Gao, Bin Zhang*, Hao Yang, Jishen Li, Fan Miao, Shaowei Tang, Sheng Cao, Jianqiang Shan. Study on the lower head failure in severe accident Part I: Model development and validation[J]. Annals of Nuclear Energy, 2022.07, volume 190: 109871.

22) Long JP, Yang BW, Zhang B*, Wang S. Case study of flow instabilities in subchannels via multidimensional CFD approach [J]. Annals of Nuclear Energy, 2023.184

23) Hao Yang, Bin Zhang*, Pengcheng Gao, Runze Zhai, Jianqiang Shan. Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head[J]. Nuclear Science and Engineering, 2023, 197(7): 1436-1453.

24) Hao Yang, Jishen Li, Zhiran Zhang, Bin Zhang*, Jianqiang Shan. Uncertainty and Sensitivity Analysis of In-Vessel Phenomena under Severe Accident Mitigation Strategy Based on ISAA-SAUP Program[J]. Nuclear Science and Techniques, 2023.

25) 杨皓，高鹏程，李济深，翟润泽，张斌*. 基于热力学分析的核反应堆压力容器下封头完整性研究[J]. 机械工程学报, 2023.

26) 杨皓，张斌*，李济深，缪凡，张芷然，单建强. 严重事故工况下反应堆热工水力参数对源项释放行为影响研究[J]. 西安交通大学学报, 2023.

27) Tang SW, Zhang B*, Shan J. Research on the performance enhancement of accident tolerant fuel for eliminating core melting based on ISAA [J]. Annals of Nuclear Energy, 2023, 186: 109747.

28) Jishen Li, Bin Zhang*, Fan Miao, Hao Yang, Jiangqiang Shan. Improvement and validation of containment spray removal aerosol models based on single droplet collection particle mechanism[J]. Journal of Aerosol Science, 2023, 174:106234.

29) Jishen Li, Bin Zhang*, Pengcheng Gao, Fian Miao, Jianqiang Shan. Improvement and validation of aerosol models for natural deposition mechanism in reactor containment[J]. Nuclear Engineering and Technology, 2023, 55(7):2628-2641.

30) 李济深，张斌*，缪凡，杨皓，单建强. 反应堆安全壳中高精度喷淋去除放射性气溶胶模型的开发及验证[J]. 西安交通大学学报. https://link.cnki.net/urlid/61.1069.T.20230816.1215.006

31) Wenpeng Wang, Bin Zhang*, Sheng Cao, Jianqiang Shan. Experimental study on design optimization of the core catcher for the CEFR[J].Journal of Nuclear Science and Technology, 2023, 60(11):1406-1416.

32) Sheng Cao, Bin Zhang*, Wenpeng Wang, Jianqiang Shan. Numerical investigation on design optimization of core catcher in sodium cooled fast breeder reactor[J].Nuclear Engineering and Design，2023, 414.

b) 著作
1) 朱继洲, 单建强, 奚树人, 张斌. 核反应堆安全分析[M]. 第3版. 西安：西安交通大学出版社，2018.

2) 朱继洲, 单建强, 张斌. 压水堆核电厂的运行[M]. 第二版. 北京: 原子能出版社, 2008. 

3) 单建强, 朱继洲, 张斌. 压水堆核电厂调试与运行[M]. 北京: 中国电力出版社, 2008.

4) 朱继洲, 奚树人, 单建强, 张斌. 核反应堆安全分析[M]. 第二版. 西安：西安交通大学出版社,北京：原子能出版社，2004.

5) 单建强，张斌，张建民，朱继洲. CANDU核电厂系统与运行[M]. 西安：西安交通大学音像出版社，2005.