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张钰浩

作者: | 来源: | 发布日期:2019-12-18

姓名:张钰浩        ef8bf36921064c49a0edb2d98b58a5fc.jpg

职称:讲师

所在院系:亚体育学院

研究方向:

[1]反应堆热工流体与安全分析:三代先进压水堆非能动安全系统实验及传热传质特性分析与验证,多相流复杂流场测试技术,快堆事故安全分析;

Reactor Thermal Hydraulics and Safety Analysis: The Third Generation advanced PWR Passive safety system experiment; Analysis and verification of heat and mass transfer characteristics; Multiphase flow measurement technology; Fast reactor accident safety analysis.

[2]CFD数值计算与分析:核电厂核岛与常规岛热工特性及复杂多相流过程CFD计算与模型验证;快堆全堆复杂流动与传热综合数值计算与评估;

CFD calculation and analysis: CFD calculation and model verification on thermal characteristics and complex multi-phase flow process in nuclear power plant; Comprehensive numerical calculation and evaluation of multi-phase flow; Heat transfer analysis and calculation for the Fast Reactor.

[3]严重事故:核反应堆严重事故下堆内熔融物滞留及缓解措施评价,放射性裂变产物释放过程中的净化与沉降特性分析等。

Severe Accident Analysis: Evaluation of IVR-ERVC in the reactor under serious accident of nuclear reactor; Analysis of purification and settlement characteristics during release of radioactive fission products, etc.

联系方式:

办公地址:主楼G-213

电子邮箱:zhangyuhao@ncepu.edu.cn

办公电话:010-61771672

个人简介及主要荣誉称号:

张钰浩,男,1990年6月生。2012年、2017年在华北电力大学英亚体育学院获得核工程与核技术学士学位、核电与动力工程博士学位,2019年评为硕士生导师。

主要从事反应堆热工流体实验,数值模拟CFD,非能动余热排出系统传热分析,蒸汽直接接触式冷凝传热传质,整体/分离效应实验比例分析,两相流实验与测量技术,快堆热工计算及安全分析等。作为课题负责人主持国家科技重大专项子课题任务1项,主持国家自然科学基金青年项目1项,主持中央高校基本科研业务面上项目1项,作为课题副组长或骨干成员参与完成国家重大科技项目及关键工程研发任务多项。发表论文30余篇,其中以第一作者或通讯作者发表SCI论文9篇,EI论文12篇,相关研究成果通过中国核能行业协会成果鉴定,作为第二完成人,获得中国能源研究会能源创新奖一等奖1项、中国核能行业协会科学技术奖二等奖1项,获得华北电力大学2019年度青年教师教学基本功比赛二等奖。

教学与人才培养情况:

1.教学课程:

核电厂系统与设备,2018-至今,64学时,30-60人

工程流体力学(核),2018-至今,56学时,60-80人

AP1000核电站(研究生),2017,32学时,25人

2.学生培养

与陆道纲教授共同指导研究生多人,共同指导的毕业硕士:欧阳斌,张晓露等

主要科研项目情况:

[1]主持国家科技重大专项子课题,ADS1-3喷放及PRHR换热相关模型评估补充实验研究,2018.04- 2019.12,265.52万元

[2]主持国家自然科学基金,多孔蒸汽射流冷凝传热与压力振荡的机理及模型研究,2020.01- 2022.12,25万元

[3]主持中央高校基本科研业务面上项目,多孔蒸汽喷放直接接触式冷凝机理研究,2018.01- 2019.12,10万元

[4]参与中国原子能科学研究院委托课题,示范快堆堆容器及堆内构件三维热工流体瞬态计算,2018.10-2021.04,845.19万元

[5]参与国核电力规划设计研究院有限公司委托课题,常规岛第一跨防水淹相关建模及模拟计算,2019.10-2020.12,172万元

[6]参与国家科技重大专项子课题,池式沸腾下的冷凝与沸腾研究,2011.01-2015.12,456.37万元

主要获奖:

[1]中国能源研究会,2018.11,大型先进压水堆非能动冷却水箱关键传热模型及其应用,能源创新奖一等奖, 排名第2

[2]中国核能行业协会,2018.11,事故工况下乏燃料贮存水池冷却技术研究及应用,中国核能行业协会科学技术奖二等奖, 排名第9

代表性论著:

[1]Zhang Yuhao, Feng Li; Liu Lifang, et al. Experimental research on heat transfer characteristics of the unstable multi-hole steam jets and development of the lumped condensation model [J]. International Journal of Heat and Mass Transfer, 2019, 139: 46-57. (SCI收录)

[2]Zhang Yuhao, Yuan Yonglong, Feng Li, et al. Application of the modified heat transfer formulas for the C-type Heat Exchanger in Passive Heat Removal System of CAP1400 [J]. Applied Thermal Engineering, 2019, 159: 113876. (SCI收录)

[3]Zhang Yuhao, Lu Daogang; Oyang Bin; Yuan Yonglong. Criteria and comparison of thermal stratification between PRHR HX heating and ADS spraying process in IRWST based on a down-scaled experimental facility [J]. Kerntechnik, 2018, 83: 181-185.(SCI收录)

[4]Zhang Yuhao, Lu Daogang, Wang Zhongyi, et al. Experimental investigation on pool-boiling of C-shape heat exchanger bundle used in PRHR HX[J]. Applied Thermal Engineering, 2017, 114: 186-195. (SCI收录)

[5]Zhang Yuhao, Lu Daogang, Wang Zhongyi, et al. Experimental research on the thermal stratification criteria and heat transfer model for the multi-holes steam ejection in IRWST of AP1000 plant[J]. Applied Thermal Engineering, 2016, 107: 1046-1056.(SCI收录)

[6]Lu Daogang, Zhang Yuhao*, Fu Xiaoliang, et al. Experimental investigation on natural convection heat transfer characteristics of C-shape heating rods bundle used in PRHR HX[J]. Annals of Nuclear Energy, 2016, 98: 226-238.(SCI收录)

[7]Lu Daogang, Zhang Yuhao*, Wang Zhongyi, et al. Numerical and experimental investigation on the baffle design in secondary side of the PRHR HX in AP1000[J]. Annals of Nuclear Energy, 2016, 94: 359-368.(SCI收录)

[8]Zhang Yuhao*, Lu Daogang, Du Zheng, et al. Numerical and experimental investigation on the transient heat transfer characteristics of C-shape rod bundles used in Passive Residual Heat Removal Heat Exchangers[J]. Annals of Nuclear Energy, 2015, 83: 147-160.(SCI收录)

[9]Xia Zihan, Lu Daogang, Zhang Yuhao*, et al. Three-dimensional thermal hydraulic transient calculation of coupled cold and hot sodium pools under a loss of feedwater accident in the China experimental fast reactor[J]. Annals of Nuclear Energy, 2020, 139: 107271.(SCI收录)

[10]张钰浩*, 陆道纲, 王忠毅, 等. AP1000非能动余热排出热交换器缩比C型管束二次侧传热模型实验研究[J]. 原子能科学技术, 2016, 50(10): 1763-1770.(EI收录)