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以第一作者及通讯作者发表SCI期刊论文25篇，含期刊高被引论文5篇，特邀综述（Invited Review）1篇，上述成果总被引超400次。
相关成果被传热学专家陶文铨院士、美国普渡大学终身教授Takashi Hibiki、韩国原子能研究院的研究员Jeon Soon-Hyeok（全顺赫）、国家级高层次人才苏光辉教授及于广锁教授等多次引用在Physics of Fluids、IEEE Access、Chemical Engineering Science等多个中科院Top期刊上。
代表性第一作者论文：
[1]Wang Bo*, Xu Shunhao, Wang Bin, Wang Weibing, Liu Yongchao, Li Tong, Hu Shaochun, Zhang Jiayi, Wang Mengyao**. Review of recent research on heat pipe cooled reactor. Nuclear Engineering and Design, 2023, 415, 112679.（SCI，中科院小类2区，JCR 2区，影响因子1.9，被引3次）
[2]Wang Bo, Ke Bingzheng, Chen Bowen, Li Ru, Tian Ruifeng*. Study on the size of secondary droplets generated owing to rupture of liquid film on corrugated plate wall. International Journal of Heat and Mass Transfer, 2020, 147, 118904.（SCI:000505101200011，JCR 1区，中科院top期刊，影响因子5.431，被引13次）
[3]Wang Bo, Tian Ruifeng*. Investigation on Flow and Breakdown Characteristics of Water Film on Vertical Corrugated plate Wall. Annals of Nuclear Energy, 2019, 127, 120-129.（SCI:000463120200012，中科院小类1区，JCR 2区，影响因子1.81，被引49次，期刊高被引论文（Most cited））
[4]Wang Bo, Tian Ruifeng. Judgement of critical state of water film rupture on corrugated plate wall based on SIFT feature selection algorithm and SVM classification method. Nuclear Engineering and Design, 2019, 347, 132-139.（SCI:000465217900013，中科院小类1区，JCR 2区，影响因子1.9，被引37次，期刊高被引论文（Most cited））
[6]Wang Bo, Chen Bowen, Tian Ruifeng. Review of Research Progress on Flow and Rupture Characteristics of Liquid Film on Corrugated Plate Wall. Annals of Nuclear Energy, 2019, 132, 741-751.（SCI:000482247600067，中科院小类1区，JCR 2区，影响因子1.81，被引38次，期刊高被引论文（Most cited））
[7]Wang Bo, Tian Ruifeng. Study on characteristics of water film breakdown on the corrugated plate wall under the horizontal shear of airflow. Nuclear Engineering and Design, 2019, 343, 76-84.（SCI:000456923500008，中科院小类2区，JCR 2区，影响因子1.81，被引32次，期刊高被引论文（Most cited））
[8]Wang Bo, Chen Bowen, Wang Gongqing, Li Ru, Wen Jiming, Lu Chuan, Tian Ruifeng*, Deng Jian**. Back Propagation (BP) Neural Network Prediction and Chaotic Characteristics Analysis of Free Falling Liquid Film Fluctuation on Corrugated Plate Wall. Annals of Nuclear Energy, 2020, 148, 107711.（SCI:000568756900031，中科院小类1区，JCR 2区，影响因子1.81，被引30次）
[9]Wang Bo, Ke Bingzheng, Chen Bowen, Li Ru, Tian Ruifeng. A technical review of research progress on thin liquid film thickness. Experimental and Computational Multiphase Flow, 2020, 4, 199-211.（特邀综述（Invited Review），被引11次）
[10]Wang Bo*, Chen Bowen, Wen Jiming, Tian Ruifeng**. A mini review of research progress of nuclear physics and thermal hydraulic characteristics of lead-bismuth research reactor in China. Frontiers in Energy Research, 2020, 8.（EI:20203909246380，JCR3区，影响因子4.597，被引2次）
[11]Wang Bo*, Chen Bowen, Ke Bingzheng, Wang Gongqing, Li Ru, Wen Jiming, Lu Chuan, Tian Ruifeng**. Analysis of the flow characteristics of the liquid film on the wall surface of the corrugated plate dryer based on PSD method: a short communication. Frontiers in Energy Research, 2020, 8.（SCI:000574271900001，JCR3区，影响因子4.597，被引3次）
[12]Wang Bo*, Chen Bowen, Ke Bingzheng, Wang Gongqing, Li Ru, Wen Jiming, Lu Chuan, Tian Ruifeng**. Study on Breakdown Mechanism of Water Film on Corrugated Plate Wall Under the Horizontal Shear of Airflow: A Short Communication. Frontiers in Energy Research, 2020, 8.（SCI:000574272100001，JCR3区，影响因子4.597，被引2次）
[13]Wang Bo, Chen Bowen, Wang Gongqing, Ke Bingzheng, Wen Jiming, Lu Chuan, Tian Ruifeng*, Jian Deng**. Analysis of influencing factors of rupture phenomenon of liquid film on the wall of corrugated plate dryer. Annals of Nuclear Energy, 147, 107694.（SCI:000561485300028，中科院小类1区，JCR 2区，影响因子1.81，被引2次）
[14]Wang Bo, Chen Bowen, Ke Bingzheng, Li Ru, Tian Ruifeng. Study on strip-shaped liquid film in the corrugated plate dryer. Annals of Nuclear Energy, 2020, 139, 107237.（SCI:000517662400017，中科院小类1区，JCR 2区，影响因子1.81，被引5次）
[15]Wang Bo, Chen Bowen, Ke Bingzheng, Li Ru, Tian Ruifeng. Effect of physical property parameters on critical airflow velocity of a corrugated plate dryer. Annals of Nuclear Energy, 2020, 140, 107330.（SCI:000526110100020，中科院小类1区，JCR 2区，影响因子1.81，被引3次）
[16]Wang Bo, Lu Chuan, Tian Ruifeng*. Characteristics of liquid film rupture at wave plate corner: A short communication. Annals of Nuclear Energy, 2021, 151, 107880.（SCI:000595796000012，中科院小类1区，JCR 2区，影响因子1.81，被引1次）
[0] Wang Bo*. ICONE31.
[1] Wang Bo*, Xu Shunhao. WORTH-10.
通讯作者论文：
[0] 谈灿逸，王博*. 基于CNN的核电站故障诊断技术研究. 核反应堆技术2024年全国重点实验室年会-优秀论文一等奖（专题（四）核动力控制与智能化）.
[1] Liu Yongchao, Li Tong, Xiao Kai, Chen Jie, Tan Xin, Cheng Jiahao, Tan Sichao* , Wang Bo* , He Zhengxi, Shen Jihong, Gao Puzhen, Tian Ruifeng. Research on sensor data optimization technology for thermal hydraulic experiment of nuclear reactor. Nuclear Engineering and Design, 2024, 423, 113176.
[2] 刘震，梁彪，王博*，丁鹏，谭思超**，李江宽，段承杰，李瀚生，田瑞峰. Research on optimization of key thermal parameters of the secondary loop of PWR based on improved BP neural network. Annals of Nuclear Energy, 2024, 202, 110466.
[3] 刘永超，李桐，成以恒，王博*，高璞珍，谭思超**，田瑞峰. 基于深度确定性策略梯度算法的自适应核反应堆功率控制器设计. 原子能科学技术，2023.
[4] Qiao Hong, Ma Jun, Wang Bo*, Tan Sichao**, Zhang Jiayi, Liang Biao, Li Tong, Tian Ruifeng. Application of Data-Driven technology in nuclear Engineering: Prediction, classification and design optimization. Annals of Nuclear Energy, 2023, 194, 110089.（SCI，中科院小类1区，JCR 2区，影响因子1.81，被引2次，学院20级本科生一作）
[5]Zhang Jiayi, Wang Mengyao, Wang Yang, Chao Zhiyang, Hu Shaochun, Chen Bowen, Wang Bo*, Li Ru**. Numerical calculation method of the corrugated plate dryer based on the discrete phase model and the Euler Water film model: A short communication. Annals of Nuclear Energy, 2023, 186, 109752.（SCI:000944402300001，中科院小类1区，JCR 2区，影响因子1.81，被引0次，学院“小核创新班”本科生一作）
[6]Wang Mengyao, Wang Bo*, Guo Xin, Zhang Jiayi, Chao Zhiyang, Wang Yang, Lu Chuan, Wu Yang, Tian Ruifeng**. Review on the steam-liquid separation in the steam generator of nuclear power plants. Annals of Nuclear Energy, 2022, 175, 109207.（SCI:000814221400005，中科院小类1区，JCR 2区，影响因子1.81，被引2次，学院“小核创新班”本科生一作，被上海交通大学电子信息与电气工程学院 生物过程模型化与控制实验室主任袁景淇教授团队、清华核研院zhanghuang团队引用）
[7]Wang W.-B., Wang, S.-N., Zhu, J.-H., Wang, B.*, Liang, B., Cheng, K. Hou, H.-G.**, Zhang, M., Tian, R.-F. Prediction of Corrosion Defect Critical Size and Corrosion Failure Assessment Study of SGTs. Journal of Nuclear Materials, 2023, 578, 154350. （SCI:000948929700001，中国核学会T1级期刊，中科院top期刊，中科院小类1区，JCR 1区，影响因子3.555，被引3次）
[8]Li Ru, Mao Feng, Chen Bowen, Wang Bo*, Tian Ruifeng**. Influence of the structure of drainage tank on the separation performance of corrugated plate dryer in NPPs: A short communication. Annals of Nuclear Energy, 2022, 169, 108930.（SCI:000806351800002，中科院小类1区，JCR 2区，影响因子1.81，被引1次）
[9]Li Ru, Chen Bowen, Wang Weibing, Wang Bo*, Tian Ruifeng**. Experimental analysis of droplet impacting on inclined wall of the corrugated plate dryer in steam generator of nuclear power plants. Annals of Nuclear Energy, 2022, 172, 109062.（SCI:000793300600006，中科院小类1区，JCR 2区，影响因子1.81，被引7次，被重庆大学低品位能源利用技术与系统教育部重点实验室中国能源研究会热力学及其工程应用专业委员会委员吴双应引用）
[10]Li Ru, Zhan Chunyuan, Wang Bo*, Wen Jiming, Tian Ruifeng**, Ke Zhiwu***. Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR. Annals of Nuclear Energy, 2022, 177, 109292.（SCI:尚未检索，中科院小类1区，JCR 2区，影响因子1.81，被引1次）
[11] Wang Weibing, Wang Bo*, Zhou Ying, Wang Shengnan, Zhang Meng. Study on the mass and heat transfer characteristics of the drying process of spent nuclear fuel cladding with nitrogen assisted. Nuclear Engineering and Design, 2022, 391, 111672.（SCI:000782569900001，中科院小类2区，JCR 2区，影响因子1.9，被引7次）
[12] 梁彪，黄涛，袁鹏，刘永超，王博*，谭思超. 核动力系统运行工况预判的深度学习方法研究[J].核科学与工程,2023,43(04):944-951. (CSCD)
https://kns.cnki.net/kcms2/article/abstract?v=axnrJTP8flyEUiQakuGOFqDtMpZrASlaXyHmF1FVzKu6jNXLcpWM1RWFlEhDTwsmvMiAaRrR9Ks18wJpif8eIaMaO5Nbotea-k5LLpIP46NOwHmUoaP0yrzBragQAXFVsApus1lxLokoQ2mEFlmrww==&uniplatform=NZKPT&language=CHS
[13] Wang Weibing, Zhou Ying, Liang Bo, Wang Bo*, Zhang Meng**, Tan Sichao***. Electrochemical behavior and corrosion rate prediction study of alloy 690 [J]. International Journal of Advanced Nuclear Reactor Design and Technology, 2022.（西交主办国际期刊，被引7次，被南非约翰内斯堡大学机械工程科学系—南非国家科学院Tien-ChienJen(任天健)院士在IEEE会议论文引用，被东北大学沈阳材料科学国家实验室—中国腐蚀与防护学会第九届理事会理事长—王福会教授引用）
[14] Liu Yongchao, Li Xiangyu, Liang Biao, Wang Bo*, Tan Sichao**, Gao Puzhen. Research on Accident Diagnosis Method of Reactor System Based on XGBoost Using Bayesian Optimization[C]//International Conference on Nuclear Engineering29 (ICONE29). American Society of Mechanical Engineers, 2022, 86472: V012T12A015. （EI检索）
其他代表性论文：
[1]Wang, G.-Q., Wang, B., Wen, J.M.，et al. Investigation on the hydraulic process of inertia tank in the case of pump trips. Nuclear Engineering and Design, 2021,379, 111195.（中科院小类2区，核能 SCI 期刊）
[2]Wang, G.-Q., Wang, B., Wen, J.M., et al., 2020. Scaling analysis for inertia tank based on the cold state of deep pool-type nuclear heating reactor. Annals of Nuclear Energy, 2020, 151, 107905.（中科院小类1区，核能 SCI 期刊）
[3]Wang, G.-Q., Wang, B., Wen, J.M., et al., 2020. Experimental study on the hydraulic characteristics of inertia tank after the failure of pump power. Annals of Nuclear Energy, 2020, 151, 107885.（中科院小类1区，核能 SCI 期刊）
[4]Chen, B.-W., Wang, B., Tian, R.-F., 2020. Experimental study of droplet impacting on inclined wetted wall in corrugated plate separator. Annals of Nuclear Energy, 137, 107155.（中科院小类1区，核能 SCI 期刊，被引21次）
[5]Chen, B.-W., Wang, B., Mao, F., et al., 2020. Analysis of liquid droplet impacting on liquid film by CLSVOF. Annals of Nuclear Energy, 143, 107468.（中科院小类1区，核能 SCI 期刊，被引19次）
[6]Chen, B.-W., Wang, B., Mao, F., et al., 2020. Review on separation mechanism of corrugated plate separator. Annals of Nuclear Energy, 144(1), 107548.（中科院小类1区，核能 SCI 期刊，被引9次）
[7]Ke, B.-Z., Gao, P.-Z., Wang, B., et al., Study on thermal hydraulic characteristics of a simulated pressurizer during the blowdown process. Annals of Nuclear Energy, 2021,153, 108063.（中科院小类1区，核能 SCI 期刊）
[8]Wang, W.-B., Cheng, K., Wang, B., Zhang, M., Tian, R.-F. Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator. Nuclear Engineering and Design, 2023, 402(3), 112081.（中科院小类2区，核能 SCI 期刊，被引1次）
[9]陈博文, 王博, 田瑞峰, 等, 2020. 液滴撞击干燥倾斜壁面铺展实验研究. 核动力工程, 41(4), 64-69.（核能 EI 期刊）
[10]柯炳正, 高璞珍, 王博, 等, 2020. 不同喷射条件下闪蒸喷雾液滴尺寸特性数值分析. 哈尔滨工程大学学报, 41(8), 1170-1175.（核能 EI 期刊）
[11]柯炳正, 高璞珍, 王博, 等, 2020. LOCA 下喷放参数对冷却剂喷放特性影响数值研究. 原子能科学技术, 54(10), 1858-1865.（核能 EI 期刊）
[12]Chen, B.-W., Wang, B., Mao, F., et al., 2020. Numerical study on characteristics of single droplet impacting on wetted surface. Experimental and Computational Multiphase Flow, 3(1), 59-67.
[13]Zhu,J.-H., Lin, Y.-S., Wang, B., Wen, J.-M.*, Tian, R.-F., 2023. Study on ultrasonic attenuation characteristics in air-droplet two-phase flow. Annals of Nuclear Energy, 185,109742.（中科院小类1区，核能 SCI 期刊：000947854100001，被引1次）
[14] Mohamed Moustafa, Tian Ruifeng, Wang Bo, Jiming Wen, Asmat Ullah, Hagar Alm ElDin Mohamad. A detailed experimental evaluation of gas –Liquid film attributes in a horizontal rectangular duct by Planar Laser-Induced fluorescence (PLIF) approach. Nuclear Engineering and Design, Volume 408, July 2023, 112331.（国际合作论文）
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