朱隆祥，工学博士，助理研究员。2021年6月获得西安交通大学核科学与技术专业博士学位，2021年6月进入太阳成集团tyc4633任助理研究员/弘深青年教师。目前从事包括多相流流动与传热、两相流相态及相界面输运行为、反应堆热工水力分析程序、复杂两相流系统机器学习方法等研究。担任核能领域国际会议International Conference on Nuclear Engineering(ICONE)和Pacific Basin Nuclear Conference(PBNC)主席助理，在International Journal of Heat and Mass Transfer、Progress in Nuclear Energy等国际知名SCI期刊上发表文章。
2016/09-2021/06 西安交通大学 核科学与技术 博士学位
2018/09-2020/11 美国伊利诺伊大学 核能工程 联合培养
2012/09-2016/06 太阳成集团 核工程与核技术 学士学位
[1] 多相流流动与传热
[2] 两相流相态及相界面输运行为
[3] 反应堆热工水力分析程序
[4] 复杂两相流系统机器学习方法
[1] 横向课题，系统程序饱和蒸汽相间换热模型研究，2021/10/08-2023/04/08，92万，主持；
[2] 国家自然科学基金青年科学基金项目，基于物理认知-神经网络耦合方法的高参数相界面演变机制研究，2023/01/01-2025/12/31，30万，主持；
[3] 中国博士后科学基金面上项目，2023/01/01-2024/12/31，8万，主持。
[1] Longxiang Zhu*, Zhiee Jhia Ooi, Taiyang Zhang, Caleb S. Brooks, and Liangming Pan. “Identification of flow regimes in boiling flow with clustering algorithms: An interpretable machine-learning perspective.” Applied Thermal Engineering, 228 (2023): 120493. (SCI,EI)
[2] Longxiang Zhu*, Taiyang Zhang, Joseph L. Bottini, and Caleb S. Brooks. “Two-dimensional quantitative study of boiling flow evolution in vertical inner-heated annulus channel.” International Journal of Heat and Mass Transfer, 183 (2022): 122190.（SCI,EI）
[3] Longxiang Zhu*, Joseph L. Bottini, Caleb S. Brooks, and Luteng Zhang. “Comparison of Intergroup Mass Transfer Coefficient Correlations in Two-Group IATE for Subcooled Boiling Flow”. Front. Energy Res. 10(2022):890795.
[4] Zhiee Jhia Ooi*, Longxiang Zhu, Joseph L. Bottini, and Caleb S. Brooks. “Identification of flow regimes in boiling flows in a vertical annulus channel with machine learning techniques.” International Journal of Heat and Mass Transfer, 185 (2022): 122439.（SCI,EI）
[5] Longxiang Zhu, Zhiee Jhia Ooi, Joseph L. Bottini, Caleb S. Brooks*, and Jianqiang Shan. “Bubble diameter distribution and intergroup mass transfer in the multigroup two-fluid model.” International Journal of Heat and Mass Transfer, 163 (2020): 120456.（SCI,EI）
[6] Longxiang Zhu, Zhiee Jhia Ooi, Caleb S. Brooks*, and Jianqiang Shan. “Modeling sensitivity in prediction of interfacial area concentration in boiling flow.” Progress in Nuclear Energy, Vol. 133, 103638. DOI: 10.1016/j.pnucene.2021.103638.（SCI,EI）
[7] Joseph L. Bottini, Longxiang Zhu, Zhiee Jhia Ooi, Taiyang Zhang, and Caleb S. Brooks*. "Experimental study of boiling flow in a vertical heated annulus with local two-phase measurements and visualization." International Journal of Heat and Mass Transfer 155 (2020): 119712.（SCI,EI）
[8] Longxiang Zhu*, Zhiee Jhia Ooi, Taiyang Zhang, Caleb S. Brooks, and Liangming Pan. "Flow regime identification for boiling flow and study of feed-in information in unsupervised machine learning." In 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH -19. 2022.
[9] Longxiang Zhu*, Taiyang Zhang, Zhiee Jhia Ooi, Caleb S. Brooks, and Liangming Pan. "Validation of interfacial mass transfer closures in drift flux model for condensation flow." In 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH -19. 2022.
[10] Longxiang Zhu, Joseph L. Bottini, and Caleb S. Brooks*. “Sensitivity of intergroup mass transfer in two-group IATE for subcooled boiling flow.” In 2020 ANS Winter Meeting and Nuclear Technology Expo, Chicago, 2020.
[11] Longxiang Zhu, Zhiee Jhia Ooi, and Caleb S. Brooks*. "Current Intergroup mass transfer limitations in the multi-group two-fluid model." In 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH -2019. 2019.（EI）
[12] Longxiang Zhu, Zhiee Jhia Ooi, and Caleb S. Brooks*. "Current capability of interfacial area transport approaches in subcooled boiling." In 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-2019. 2019.（EI）
[13] Longxiang Zhu and Jianqiang Shan*. "Interfacial Drag Force Improvement in Two-Fluid Model." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers Digital Collection, 2018.（EI）
[14] Bottini, Joseph L., Longxiang Zhu, Zhiee Jhia Ooi, Taiyang Zhang, and Caleb S. Brooks*. "A new dataset with local measurement and visualization of subcooled boiling in an internally heated annulus channel." In 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH- 2019. 2019.（EI）
