发表学术论文200余篇,其中100余篇被SCI和EI检索收录;授权专利80项,软件著作权登记30余项。承担了国防科工委和电力出版社的3项编书任务,主编出版电力出版社“十二五”规划教材《核电站系统与设备》,出版核电教材《非能动概念与技术》、《核电风险与保险》、《细颗粒物现象学》和《能源动力工程导论》。曾获陕西省科学技术一等奖、北京市科技发明金奖、河北省科技发明三等奖、北京市创新发明大赛银山红专项奖、高等学校科学技术二等奖及中核总科技成果等奖励。多次获大学优秀教师、奖教金、科技工作先进个人;教学优秀奖、广核育才奖;党建创新奖;科技成果和大学优秀精品课程。 ①代表性学术论文 [1]Zhou Tao, Peng Changhong, Wang Zenghui, Wang Ruosu. Application of grey model on analyzing the passive natural circulation residual heat removal system of HTR-10[J]. Nuclear Science and Techniques. 2008, 19(5):308-313. [2]Zhou Tao, Yang Ruichang, Wang Shichao, Lei Zhao,Liu Ruolei. Visual experiment research of the inhaled particle thermophoresis deposition rule in the rectangle turbulent flow tube[J]. Applied thermal engineering. 2009, 29(5-6): 1138-1145. [3]Zhou Tao, Yang Ruichang, LI Zhenyang, ZHANG Ming, LIU Mengying. Onset of Nucleate Boiling in Natural Circulation Systems Predicted Using the Second Stir Theory[J].Tsinghua Science & Technology.2010, 15(4): 441–446. [4]Zhou Tao, SunCanhui, Li Zhenyang, Wang Zenghui. Application of thermal comfort theory in probabilistic safety assessment of a nuclear power plant[J]. Nuclear Science and Techniques. 2011,22(5):316-320. [5]Zhou Tao, Chen Juan, Luo Feng, Cheng Wanxu. Fuzzy PSA Evaluation Method for Passive Residual Heat Removal System[J]. Nuclear Engineering and Design. 2012, 24: 230-235. [6]Zhou Tao, Chen Juan, Cheng Wanxu. Thermo Hydraulic Analysis on Narrow Channel Effect of Supercritical-Pressure Light Water Reactor[J]. Annals of Nuclear Energy. 2012, 47: 234-241. [7]Chen Juan, Zhou Tao, HouZhousen, Cheng Wanxu. Thermo-hydraulic Analysis for SCWR during Power-raising Phase of Startup[J]. Nuclear Science and Techniques. 2012, 23(3): 282-286. [8]LiuMengying, Zhou Tao, ZouWenzhong, SuZiwei. Study and analysis of metal coolant thermophysicalproperties[J]. Frontiers of Mechanical Engineering and Materials Engineering. 2012, 184: 1226-1231. [9]Zhou Tao, Hong Dexun, Ran Ke, Su Ziwei. Research on Mechanism of Flow Excursion in Narrow Rectangle Channel under Natural Circulation[J]. Nuclear Engineering and Design. 2013, 254:1-4. [10]Zhou Tao, Duan Jun, Hong De-xun, Liu Ping,Sheng Cheng, Huang Yanping. Characteristics of Single Bubblein Subcooled Boiling Region in Narrow Rectangular Channel under NaturalCirculation[J]. Annuals of Nuclear Energy, 2013, 57:22-31. [11]LiJingjing, Zhou Tao, LiuMengying, SuZiwei, ZouWenzhong. The Choice of Coolants in Accelerate Driven System[J]. Advanced Materials Research. 2013, 681: 195-199. [12]Sheng Cheng, Zhou Tao, Zhang Lei. Nonlinear Analysis of Onset of Nucleate Boiling in Natural Circulation under Different Pressure Conditions[J]. Research Journal of Applied Sciences, Engineering and Technology. 2013, 5(16): 4123-4128. [13]Liu Liang,Zhou Tao,LI Yu,et al.SCWR transient safety analysis code SCAC-CSR1000[J].Progress in Nuclear Energy,2015,83:318-325. [14]SHAHZAD Muhammad Ali,Zhou Tao,LIU Liang.CSR1000 single channel thermal hydraulic stability analysis using response matrix method[J].Progress in Nuclear Energy,2016,91:9-16 [15]Chen J, Zhou T, Chen J, et al. A calculation method for transient flow distribution of SCWR(CSR1000)[J]. Annals of Nuclear Energy, 2017, 110:541-546. [16]Ma D, Zhou T, Chen J, et al. Supercritical water heat transfer coefficient prediction analysis based on BP neural network[J]. Nuclear Engineering & Design, 2017, 320:400-408. [17]周涛,李子超,李兵,秦雪猛,朱亮宇,石顺.核电运行及事故颗粒物运动沉积分析方法研究[J].中国科学:物理学 力学 天文学,2019,49(11):24-46. [18] Shang Mao, Tao Zhou, Dong Wei, Wenbin Liu, Yitong Zhang. Modeling of heat transfer of supercritical water in helical finned double pipe[J]. International Journal of Heat and Mass Transfer, 2021, 180, 121754. [19] Shang Mao, Tao Zhou, Dong Wei, Wenbin Liu, Yitong Zhang. Heat transfer characteristics of supercritical water in channels: A systematic literature review of 20 years of research[J]. Applied Thermal Engineering, 2021, 197, 117403.
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