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核能工程系

文青龙

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[中文版]

姓名

文青龙

性别

               

所在部门

核能工程系

职称

副教授

职务

动力工程学院核工程技术中心主任

联系电话

023-65657581

邮箱

qlwen@cqu.edu.cn

 

*个人简介:

副教授,硕士生导师,核工程技术研究中心主任。20155月毕业于上海交通大学核能科学与工程专业,获工学博士学位。20037-20114月在中国核动力研究设计院参加工作,历任助理研究员、助理研究员、组长。20115-20167月在中广核研究院参加工作,历任主管高级工程师、研究所所长。20168月在重庆大学动力工程学院核能工程系工作,现任重庆大学动力工程学院核工程技术中心主任。曾任中国广核集团第八届科学技术委员会委员,中广核研究院第三届科学技术委员会委员。美国ASME会员,中国核学会会员。

长期从事反应堆热工水力试验研究和安全分析工作。曾在中国核动力研究设计院主持XXX堆热工系统的研究和设计工作,负责XXX堆净化系统的研究与设计工作。曾在中广核研究院主要参与国家科技部973项目ITER专项《次临界能源包层工程概念可行性关键技术研究实验项目》、国家863项目《压水堆核电厂安全级冷却链改进研究实验项目》以及能源局《核电关键设计软件自主化课题实验研究项目》。主持和参与中广核集团华龙一号和小型堆试验研究与热工水力分析工作。长期从事反应堆燃料组件热工水力试验研究和设计研究工作。主持和参与STEP系列先进燃料组件设计与热工水力试验研究工作,曾主持中广核集团大型热工水力试验装置的设计、建设、安装和调试工作以及中广核集团STEP系列燃料组件CHF试验研究、压降试验研究和交混试验研究等项目。在国内和国际重要刊物发表学术论文近30余篇,其中20余篇被SCI/EI收录。获创新银奖1项、创新奖4项、二等奖1项目、三等奖2项,申请专利13项。

 

*研究方向:

1 核反应堆热工水力试验研究和安全分析

2 -液沸腾两相流动与沸腾传热

3 核反应堆堆芯安全分析与模型评价

4 子通道交混模型和试验研究

5 棒束临界热流密度模型开发和试验研究

6 先进核能系统研究

 

研究生培养:

(1)       主授本科课程:核安全前沿

(2)       主授研究生课程:反应堆动力学,核燃料循环

 

在研科研项目:

(1)       201609月至今,快堆蒸汽发生器一次侧流动传热特性研究,负责人

(2)       201712月至今,钠水反应事故保护系统试验验证技术研究,负责人

(3)       201709月至今,某型堆自然循环运行特性研究,负责人

(4)       201709月至今,反应堆安全及放射性后果仿真分析系统,负责人

(5)       201709月至今,螺旋管直流蒸汽发生器热工水力分析程序开发,负责人

(6)       201712月至今,蒸汽发生器原型样机试验方案,负责人

(7)       201801月至今,基于AP/CAP反应堆大破口失水事故的比例模化分析,负责人

(8)       201802月至今,文丘里流量测量装置设计加工服务,负责人

(9)       201802月至今,钠钠热交换器热工水力瞬态计算技术服务,负责人

 

已结题科研项目:

2016-2017年,气凝胶管道保温结构设计数值分析,项目负责人

 

*发表论文:

(1)               Q.L.Wen, H.Y. Gu, Numerical investigation of acceleration effect on heat transfer deterioration phenomenon in supercritical water. Progress of Nuclear EnergyVol. 53.Issue 5,July 2011, 480-486.

(2)               Q.L.Wen, H.Y. Gu, Numerical simulation of heat transfer deterioration phenomenon in supercritical water through vertical tube. Annals of Nuclear Energy 37 (2010) 1272–1280.

(3)               文青龙,王弘扬,赵萌等,垂直圆管内超临界水传热关联式研究,核动力工程,20172:15-18.

(4)               文青龙,陈军,卢冬华,倾斜下朝向加热表面汽泡行为可视化实验研究. 核动力工程,2012 Vol. 32.No.1104-121.

(5)               文青龙,陈军,卢冬华,赵华,严重事故条件下压力容器完整性评价的研究进展. 核科学与工程,2011 Vo1.31. No.3222-229.

(6)               文青龙,陈军,赵华,倾斜限制空间内池式沸腾流型特性研究. 核动力工程,2011 Vol. 32.No.1104-121.

(7)               文青龙,陈军,赵华,倾斜限制空间内池式沸腾临界热流密度试验研究. 核动力工程,2011 Vol. 32.No.634-37.

(8)               文青龙,陈军,赵华,倾斜限制空间内池式沸腾临界热流密度分析模型研究. 核动力工程,201031(S1)109-114.

(9)               Cheng Cheng, Qinglong Wen, Xiaohang Wu et.al. Experimental Study on Transient Characteristic of Passive Containment Cooling System. September 2017. Energy Procedia 127:193-200.

(10)           程诚,文青龙,卢冬华,吴小航,牛文华等.非能动安全壳系统瞬态特性试验研究,核动力工程,2017(1)6-9.

(11)           B.H.Yan, Q.L.Wen, Scaling Analysis for the Ocean Motions in Single Phase Natural Circulation. Annals of Nuclear Energy 75 (2015) 521-526.

(12)           张小英,孙庆友,乔磊,卢冬华,文青龙,全结构的5X5定位格架及棒束通道的三维流场分析, 华南理工大学学报:自然科学版,2014,12104-111.

(13)           陈军,周有新,李石磊,毛玉龙,文青龙.跨间交混格架对EPR堆芯.DNBR裕量的影响. 原子能科学技术,2013 Vol.47,No.2,249-253.

(14)           Donghua Lu, Qinglong Wen et. al., A critical heat flux experiment with water flow at low pressure in thin rectangular channels, Nuclear Engineering and Design, 27(2013), 669-678.

 

学术会议交流:

(1)               Q. L. Wen, H.Y. Wang, S.W. Fu. Large Eddy Simulation of Coherent Flow Pulsation towards Turbulent Mixing in 5X5 Rod Bundles with Mixing Vanes. 2nd Sino-German Symposium on Fundamental of Advanced Nuclear Safety Technology.SG-FANS Sept.12-15, 2017, Karlsruhe, Germany.

(2)               文青龙,王弘扬,赵萌,顾汉洋,程旭,超临界水传热恶化起始点预测模型研究,第十五届全国反应堆热工流体学术会议,2017925日至27日,山东荣城.

(3)               文青龙,杨智翔,姚 曦,卢冬华,吴小航,黄洪文,混合堆包层外部冷却系统两相自然循环特性试验研究,第十四届全国反应堆热工流体学术会议,201510月,北京, RGLT2015-50259.

(4)               文青龙,顾汉洋,强浮力作用下超临界流体传热弱化现象的数值研究. 中国工程热物理学会,多相流学术会议论文,厦门,2010年,106099.

(5)               Q.L.Wen, T. Yang, F. Xie. An experimental study of static flow excursion in a two-phase natural circulation system with sub-cooled boiling.In: The 8th International Topical Meeting on Nuclear Thermal- Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14,No. N8P0362.

(6)               Qiang Wen, Qinglong Wen, Modeling of Fouling on Heat Transfer Tube for a Fast Reactor OTSG. The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics. October 22-24, 2017 Yeosu, Korea.

(7)               Ziqiang Yang, Qinglong Wen, Development of a Computer Code for the Flow and Heat Transfer Analysis. The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics. October 22-24, 2017 Yeosu, Korea

(8)               强,文青龙,杨自强等. 钠冷快堆直流蒸汽发生器传热管结垢模型研究. 第十五届全国反应堆热工流体学术会议,2017925日至27日,山东荣城. (通讯作者)

(9)               杨自强,文青龙等王弘扬螺旋管式直流蒸汽发生器热工水力程序研究.第十五届全国反应堆热工流体学术会议,2017925日至27日,山东荣城. (通讯作者)

(10)           Hongyang Wang, Qinglong Wen. CFD investigation of three-dimensional thermo-hydraulic characteristics in primary side of a fast reactor steam generator. 2nd Sino-German Symposium on Fundamental of Advanced Nuclear Safety Technology. SG-FANS Sept.12-15, 2017, Karlsruhe, Germany. (通讯作者)

(11)           李亮国,杨智翔,徐海岩,文青龙,吴小航,卢冬华, 基于RELAP5 的自然循环试验装置自然循环特性分析, 201510月,北京, RGLT2015-50259.

(12)           Donghua Lu, Qinglong Wen et. al., A Discussion on the Several Points about the FA CHF. International seminar on Sub-channel Analysis CFD modeling and verification, CHF experiment and benchmarking, Xian, 2013.

(13)           Donghua Lu, Fan Peng, Qinglong Wen,A new design for SCWR fuel assemblies. ICONE21, CHENGDU, China, 2013.

(14)           Gu, H.Y., Zhang, G., Wen, Q.L., Cheng, X., 2010. Supercritical water heat transfer test in a vertical tube. In: The 8th International Topical Meeting on Nuclear Thermal- Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14,No. N8P0338.

 

授权发明专利:

(1)               卢冬华,文青龙,张戈,杨智翔,吕路路,刘靖宇,张炯,汽液两相流体混合冷凝装置,2014.09.24,中国, CN104061796A

(2)               文青龙,卢冬华,徐海岩,孙奇,程诚,吕路路,蛇形管道的流体预热装置,2014.11.26,中国,CN203964337U

(3)               卢冬华,刘靖宇,文青龙,傅先刚,曹建华,非能动乏燃料水池冷却系统,2014.12.17,中国,CN204029398U

(4)               卢冬华,文青龙,徐海岩,张勇,吴小航,李亮国,管束式稳压器,2015.11.18,中国,CN204790610U

(5)               卢冬华,文青龙,李嘉明,张戈,杨智翔,棒束临界热流密度试验装置,2015.12.16,中国,CN204884582U

(6)               卢冬华,文青龙,吴小航,程诚,陈振辉,杜颖哲,内置式蒸汽稳压器,2016.03.23CN205104238U

(7)               卢冬华,文青龙,王飞,杨珏,姚曦,常春,刘靖宇,次临界能源包层非能动安全系统,2015.05.13,中国,CN104616708A

(8)               文青龙,卢冬华,徐海岩,孙奇,程诚,吕路路,蛇形管道的流体预热装置,2014.09.24,中国,CN104061673A

(9)               卢冬华,牛文华,范冠华,李瑜,文青龙,傅先刚,曹建华,卢向晖,沈永刚,混凝土安全壳非动能冷却系统,2014.11.26,中国,CN104167231A

(10)           卢冬华,文青龙,姚曦,王飞,杨珏,莫小锦,常春,次临界能源包层事故缓解系统,2015.01.07,中国,CN104269193A

(11)           文青龙,卢冬华,张戈,杨智翔,李嘉明,临界热流密度试验用加热棒,2015.10.28,中国,CN105007641A

(12)           卢冬华,文青龙,徐海岩,张云光,李嘉明,吴小航,用于整体效应热工水力试验的堆芯模拟体,2015.10.28,中国,CN105006260A

(13)           卢冬华,文青龙,李嘉明,张戈,杨智翔,棒束临界热流密度试验装置,2015.09.30,中国,CN104952498A


 

[English version]

Qinglong Wen, Professor (Associate), Director of Research Center of Nuclear Engineering & Technology of Chongqing University.

Born in 1979, BSc in 2003 in Instrumentation at Yuzhou University, Master in 2008 in Nuclear Engineering at Nuclear Power Institute of China (NPIC) and Ph.D. in 2015 in Nuclear Engineering at Shanghai Jiao Tong University (SJTU); 2003–2011, Research scientist in NPIC; 2011–2016, Head of Division of Thermal-hydraulic Testing; since 2016, Associate Professor at department of nuclear engineering of Chongqing University and Director of Research Center of Nuclear Engineering & Technology of Chongqing University.

Reviewer of Journal ‘Nuclear Engineering and Design’, ‘Annals of Nuclear Energy’, and ‘Progress in Nuclear Energy’

Research subjects: nuclear safety, nuclear thermal-hydraulics, advanced nuclear systems, thermal-hydraculic testing

Key Recent Publications:

Qiang Wen, Qinglong Wen, Modeling of Fouling on Heat Transfer Tube for a Fast Reactor OTSG. The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics. October 22-24, 2017 Yeosu, Korea.

Ziqiang Yang, Qinglong Wen, Development of a Computer Code for the Flow and Heat Transfer Analysis. The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics. October 22-24, 2017 Yeosu, Korea.

Q. L. Wen, H.Y. Wang, S.W. Fu. Large Eddy Simulation of Coherent Flow Pulsation towards Turbulent Mixing in 5X5 Rod Bundles with Mixing Vanes. 2nd Sino-German Symposium on Fundamental of Advanced Nuclear Safety Technology.SG-FANS Sept.12-15, 2017, Karlsruhe, Germany.

Cheng Cheng, Qinglong Wen, Xiaohang Wu et.al. Experimental Study on Transient Characteristic of Passive Containment Cooling System. September 2017. Energy Procedia 127:193-200.

Hongyang Wang, Qinglong Wen. CFD investigation of three-dimensional thermo-hydraulic characteristics in primary side of a fast reactor steam generator. 2nd Sino-German Symposium on Fundamental of Advanced Nuclear Safety Technology.SG-FANS Sept.12-15, 2017, Karlsruhe, Germany.

Donghua Lu, Qinglong Wen et. al., A critical heat flux experiment with water flow at low pressure in thin rectangular channels,Nuclear Engineering and Design, 27(2013), 669-678.

B.H.Yan, Q.L.Wen, Scaling Analysis for the Ocean Motions in Single Phase Natural Circulation. Annals of Nuclear Energy 75 (2015) 521-526.

Donghua Lu, Qinglong Wen et. al., A Discussion on the Several Points about the FA CHF. International seminar on Sub-channel Analysis CFD modeling and verification, CHF experiment and benchmarking.

Donghua Lu, Fan Peng, Qinglong Wen,A new design for SCWR fuel assemblies. ICONE21, CHENGDU, China, 2013.

Q.L.Wen, H.Y. Gu, Numerical investigation of acceleration effect on heat transfer deterioration phenomenon in supercritical water. Progress of Nuclear EnergyVol. 53.Issue 5,July 2011, 480-486.

Q.L.Wen, H.Y. Gu, Numerical simulation of heat transfer deterioration phenomenon in supercritical water through vertical tube. Annals of Nuclear Energy 37 (2010) 1272–1280.

Gu, H.Y., Zhang, G., Wen, Q.L., Cheng, X., 2010. Supercritical water heat transfer test in a vertical tube. In: The 8th International Topical Meeting on Nuclear Thermal- Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14,No. N8P0338.

Q.L.Wen, T. Yang, F. Xie. An experimental study of static flow excursion in a two-phase natural circulation system with sub-cooled boiling.In: The 8th International Topical Meeting on Nuclear Thermal- Hydraulics, Operation and Safety (NUTHOS-8), Shanghai, China, October 10-14,No. N8P0362.

 

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