张大林西安交通大学教师主页管理系统 Welcome 中文主页

教授
博士生导师
硕士生导师
电子邮箱：
入职时间：2010-03-10
学历：硕博连读
性别：女
学位：博士
在职信息：在职
毕业院校：西安交通大学
所属院系：能源与动力工程学院
学科：核科学与技术

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基本信息

张大林，教授，博导

西安交通大学核科学与技术学院

主要研究方向：先进核能系统（熔盐堆、钠冷快堆、行波堆等）物理热工耦合及安全特性研究。

国家级青年人才（12, 2021）

中核菁英人才（5, 2021）

西安交大青年拔尖人才（10, 2019）

王宽诚青年学者（8,2018）

陕西高等学校科学技术一等奖（2, 2021）

陕西高等学校科学技术一等奖（4, 2020）

国家技术发明二等奖(3, 2017)

教育部技术发明一等奖(3, 2016)

陕西省科学技术二等奖(3, 2007)

中国研究生教育成果二等奖(3 ,2018)

陕西省教学成果一等奖(3, 2018)

联系方式

张大林

西安交通大学能动学院核科学与技术系

陕西省西安市咸宁西路28号邮编：710049

办公电话：029-82664460

Email：dlzhang@mail.xjtu.edu.cn

Q Q：4562916

教学和人才培养

一、近五年来讲授的主要课程

1. 《核反应堆热工分析》(国家级精品课程)，本科生A模块必修课、B模块选修课，56学时，主讲。

2. 《先进核电技术（双语）》，本科生选修课，32学时，主讲。

3. 《核反应堆热工水力近代进展》，研究生专业课，40学时，主讲。

4. 《先进核反应堆经济性分析》，研究生专业课，40学时，主讲。

二、承担的实践性教学及人才培养

1. 本科毕业设计：每届2-3名，主要方向为新型反应堆热工水力及安全。

2. 本科生科研训练（项目设计）：每年指导4-5人。

3. 专业实习：2015届本科专业实习带队老师，赴江苏田湾核电站实习；2019届本科专业实习带队老师，赴中国原子能科学研究院实习。

4. 接收大创项目和开放实验室项目实习生（长期有效）。

5. 硕士研究生：每年独立指导硕士研究生4名。

6. 博士研究生：每年独立指导博士研究生2名，已毕业4名，其中3名获国家奖学金，1名获陕西省优博。

科研与学术交流

一、承担研究课题

1. 国家重点研发计划项目（2020YFB1902000）：固有安全一体化小型氟盐冷却高温堆技术研究，项目经费888万，项目负责人。

2. 国家自然科学基金面上项目（12075184）：液态金属冷却快堆严重事故下多组分多相态多物理耦合特性研究，项目经费63万，项目负责人。

3. 国家自然科学基金面上项目（11675127）：横向非均匀加热大宽高比矩形窄缝通道内流动换热特性研究，项目经费70万，项目负责人。

4. 国家自然科学基金面上项目（11475132）：球床钍基熔盐堆有内热源多孔介质堆芯热工水力特性的实验和理论研究，项目经费96万，项目负责人。

5. 国家自然科学基金青年项目（11105103）：行波堆增殖-燃耗波机制的数值计算研究，项目经费29万，项目负责人。

6. 国家重点实验室基金（ HT-LW-02-2014001 ）：板状燃料元件热工、机械及材料耦合分析程序开发，项目经费25万，项目负责人。

7. “十三五”核能开发项目：GINKGO等系统瞬态分析软件的自主化研发与示范应，课题经费122.4万，课题负责人。

8. 中国原子能科学研究院（2019-DGB-I-FWCG-16）：一回路自然循环能力验证实验程序开发，项目经费599万，项目负责人。

9. 中广核工程公司服务合同项目（ 20140603 ）：核电厂安全壳喷淋效果试验与数值计算专题采购项目，项目经费171.927万，项目负责人.

10. 环境保护部核与辐射安全中心（ 20140713 ）： 10MW 钍基熔盐实验堆安全热工限值研究，项目经费35万，项目负责人。

二、代表性期刊论文

0. Dianqiang Jiang, Dalin Zhang*, XinYu Li, et al. Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook[J/OL]. Renewable and Sustainable Energy Reviews, 2022, 161: 112345. DOI:10.1016/j.rser.2022.112345.（IF:14.97）

1. Zhang DL, Rineiski A, Wang CL, et al. Development of a kinetic model for safety studies of liquid-fuel reactors [J]. Progress in Nuclear Energy, 2015, 81: 104-112. (SCI: CG2FN, EI: 20150500483257, IF: 1.119)

2. Zhang DL, Zheng MY, An HZ, et al. Numerical studies of stepwise radial fuel shuffling in a Traveling Wave Reactor [J]. SCIENCE CHINA Technological Sciences, 2014, 57(6): 1229-1237. ( SCI: AI3GQ, EI: 20142817914314, IF: 1.113)

3. Zhang DL, Chen XN, Flad M, et al. Theoretical and numerical studies of TWR based on ESFR core design [J]. Energy Conversion and Management, 2013, 20132516431747, IF: 3.59)72: 12-18. (SCI: 170HO, EI:

4. Zhang DL, Chen XN, Gabrielli F., et al. Numerical studies of axial fuel shuffling [J]. Fusion Science and Technology, 2012, 61: 287-292. (SCI: 883BR, EI: 20121014832580, IF: 0.591)

5. Zhang DL, Chen XN, Gabrielli F., et al. Numerical studies of nuclear traveling waves in a supercritical water cooled fast reactor [J]. Progress in Nuclear Energy, 2011, 53: 806-813. (SCI: 854JE, EI: 20114214438281, IF: 0.879)

6. Zhang DL, Qiu SZ, Su GH, et al. Development of a Safety Analysis Code for Molten Salt Reactors [J]. Nuclear Engineering and Design, 2009, 239(12): 2778-1785. (SCI: 537IN, EI: 20094812501185, IF: 0.952)

7. Zhang DL, Qiu SZ, Su GH, et al. Development of a steady state analysis code for a molten salt reactor [J]. Annals of Nuclear Energy, 2009, 36(5): 590-603. (SCI: 447IS, EI: 20091612040328, IF: 0.96)

8. Zhang DL, Qiu SZ, Su GH, et al. Analysis on the neutron kinetics for a molten salt reactor [J]. Progress in Nuclear Energy, 2009, 51(4-5): 624-636. (SCI: 438QI, EI: 20091412017219, IF: 1.119)

9. Zhang DL, Qiu SZ, Su GH, et al. Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fuel salt [J]. Chinese Physics C, 2008, 32(8): 624-628. (SCI: 337GJ, IF: 1.313)

10. Zhang DL, Qiu SZ, Su GH, et al. Steady thermal hydraulic analysis for a molten salt reactor [J]. Nuclear Science and Techniques, 2008, 19(3): 187-192. (SCI: 344EV, IF: 0.401)

11. Zhou JJ, Zhang DL, Qiu SZ, et al. Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition [J]. Nuclear Engineering and Design, 2015, 282: 93-105. (SCI: CA5PY, EI: 20150200405523, IF: 0.952)

12. Guo ZP, Zhang DL, Xiao Y, et al. Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor [J]. Annals of Nuclear Energy, 2013, 53: 309-319. (SCI: 098LJ, EI: 20141517553855, IF: 1.02)

13. Xiao Y, Zhang DL, Guo ZP, et al. Numerical analysis for a molten salt reactor in the presence of localized perturbations [J]. Progress in Nuclear Energy, 2012, 60: 61-72. (SCI: 000LB, EI: 20123215311336, IF: 0.879)

14. Chen XN, Zhang DL, and Maschek W. Theoretical modeling of radial standing wave reactor [J]. Fusion Science and Technology, 2012, 61: 275-280. (SCI: 883BR, EI: 20121014832578, IF: 0.591)

15. Chen XN, Zhang DL, Maschek W, et al. Solitary breeding/burning waves in a supercritical water cooled fast reactor [J]. Energy Conversion and Management, 2010, 51: 1792-1798. (SCI: 607NP, EI: 20103213134718, IF: 3.59)

三、参加国际会议

1. Zhang DL, Guo ZP, Wang CL, et al. FLUENT-based Neutronics and Thermal-Hydraulics Coupling Calculation for a Liquid-Fuel Molten Salt Reactor, The 10 ^th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), December 14-18, 2014, Okinawa, Japan, NUTHOS10-1145.

2. Zhang DL, Zhai ZG, Rineiski A, et al. COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR, Proceedings of the 2014 22nd International Conference on Nuclear Engineering (ICONE22), July 7-11, 2014, Prague, Czech Republic, ICONE22-30609.

3. Zhang DL, Zhai ZG, Chen XN, et al. COUPLE, A Coupled Neutronics and Thermal-Hydraulics Code for Transient Analyses of Molten Salt Reactors, 2013 ANS Annual Meeting - Next Generation Nuclear Energy: Prospects and Challenges, June 16- 20, 2013, Atlanta, GA, US.

4. Zhang DL, Chen XN, Flad M, et al. Theoretical and Numerical Studies of TWR Based on ESFR Core Design, International Conference on Nuclear & Renewable Energy Resources, 20-23 May 2012, İstanbul, TURKEY.

5. Zhang DL, Chen XN, Gabrielli F, et al. Numerical Studies of Radial Fuel Shuffling in a Travelling Wave Reactor, Proceedings of GLOBAL 2011, Dec. 11-16, 2011, Makuhari, Japan, Paper No. 392011.

6. Zhang DL, Rineiski A, Qiu SZ, Kinetics Models for Safety Studies of Fluid –Fuel Reactors, ANS Annual Meeting, June 28-July 2, 2011, Hollywood, US.

7. Zhang DL, Chen XN, Gabrielli F, et al. Numerical Studies of Axial Fuel Shuffling, 15th International Conference on Emerging Nuclear Energy Systems, May 15-19, 2011, San Francisco, California, US.

8. Zhang DL, Chen XN, Gabrielli F, et al. Numerical studies of nuclear traveling waves in a super critical water cooled fast reactor, The Third International Symposium on Innovative Nuclear Energy Systems (INES-3), 31 October – 3 November 2010, Tokyo, Japan.

9. Zhang DL, Rineiski A, Qiu SZ. Comparison of Modeling Options for Delayed Neutron Precursor Movement in a Molten Salt Reactor, 2009 ANS Annual Meeting, June 14-18, 2009 Atlanta, GA, US, Track No. 204658.

10. Zhang DL, Qiu SZ, Su GH, et al. Numerical Research on One-Dimensional Coupling of Physics and Thermal- Hydraulics for a Molten Salt Reactor, The 7 ^th International Topic Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS7), Oct.5-9, 2008, Seoul, Korea, No.NUTHOS7-360.

11. Zhang DL, Qiu SZ, Su GH, et al. STEADY THERMAL HYDRAULIC ANALYSIS FOR A GRAPHITE-MODERATED CHANNEL TYPE MOLTEN SALT REACTOR, 16 ^th International Conference on Nuclear Engineering (ICONE16), May 11-15, 2008, Orlando, Florida, US, No.ICONE16-48944.

12. Zhang DL, Qiu SZ, Su GH, et al. NUMERICAL RESEARCH ON STEADY COUPLING OF NEUTRONICS AND THERMAL-HYDRAULICS FOR A MOLTEN SALT REACTOR, 16 ^th International Conference on Nuclear Engineering (ICONE16), May 11-15, 2008, Orlando, Florida, US, No.ICONE16-48096.

13. Zhang DL, Qiu SZ, Su GH, et al. Evaluation of Static Thermodynamic Properties of the Ternary Molten Salt System Li, Na, Be/F, Based on the Modified Peng-Robinson Equation[CD]. 15^th International Conference on Nuclear Engineering (ICONE15), April 22-2, 2007, Nagoya, Japan, No. ICONE15-10451.