赵鹏程简介

【个人简介】

赵鹏程，男，博士，教授，湖南省“青年芙蓉学者”、湖南省普通高校青年骨干教师、衡阳首届青年科技托举人才、中国核学会核反应堆热工流体力学分会副秘书长、中国核学会研究堆与新堆分会理事、中国核学会数字化与人工智能分会理事、中国核学会快堆分会理事，中国科技期刊卓越行动-梯队期刊《原子能科学技术》青年编委、EI期刊《核技术》《核动力工程》青年编委。2011年毕业于南华大学核工程与核技术专业，获工学学士学位。2014年12月至2015年12月在国家留学基金委资助下赴德国卡尔斯鲁厄理工学院博士联培，2017年毕业于中国科学技术大学核科学与技术专业，获工学博士学位。2018年~2023年，在中国核动力研究设计院核科学与技术学科（领域）从事博士后研究工作，并考核优秀出站。

主要从事先进核能概念设计与热工安全分析、人工智能技术在核能工程中的应用、反应堆热工流体实验等研究工作。近年来，主持国家自然科学基金、教育部联合基金青年人才项目、核能开发科研项目子课题、横向企业委托项目等20余项。近年来出版学术专著2部、发表学术论文60余篇，申请国家发明专利20余项，申请软件著作权10余项。获湖南省高等教育教学成果一等奖1项、三等奖1项，2019年获南华大学“十佳优秀班主任”荣誉称号、2020年获南华大学“十佳优秀教师”荣誉称号。

【近年科研项目】

[1] 装备预研教育部联合基金（青年人才项目），8091B032243，XXX小型化与轻量化设计优化方法研究，2022/12-2024/12，50万，主持；

[2] 国家自然科学基金青年项目，11905101，非对称热负荷下铅基快堆冷/热铅池热分层耦合响应机理及其对自然循环能力影响研究，2020/01-2022/12，27万，主持；

[3] 核能开发项目子课题，126001JX0120230500，典型事故的不确定性分析，2021/01-2023/12，113.7万，主持；

[4] 中国核动力研究设计院技术开发项目，11203002053-FW-HT-2022001，环形燃料有效温度计算与验证，2022/07-2023/10，86万，主持；

[5] 上海核工程研究设计院有限公司技术开发项目，铅铋堆实验数据库构建及子通道程序开发应用，2022/12-2023/12，78万，主持；

[6] 湖南省自然科学基金面上项目，2019JJ40239，驱动循环铅冷快堆非对称运行工况下复杂三维热工水力现象及其影响研究，2019/01-2021/12，10万，主持；

[7] 核反应堆系统设计技术国家重点实验室基金，HT-KFKT-01-2018001，小型长寿命自然循环铅铋快堆关键技术概念研究，2018/01-2019/12，28万，主持；

[8] 核反应堆系统设计技术国家重点实验室基金，KFKT-05-FW-HT-20220014，窄矩形通道内铅铋合金流动传热特性研究，2022/07-2024/07，34万，主持；

[9] 中国核动力研究设计院技术开发项目，HT-QBJS-05-FW-JT-20190220，铅铋堆热工水力与安全分析准则及标准规范研究，2019/10-2021/06，38.5万，主持.

【发表论著】

[1] 赵鹏程,刘紫静,于涛,等. 小型铅基快堆热工流体特性研究[M]. 中国原子能出版社, 2019.

[2] Zeng F, Zhang X, Zhao P*, Liu Z. Application Research of a Hybrid Data- and Knowledge-Driven Artificial Intelligence Scientific Computing Model in Neutron Diffusion Calculation for Nuclear Reactors[J]. Nuclear Science and Techniques, 2025.

[3] Zeng F, Zeng Y, Zhao P*, et al. Nonlinear reduced-order analysis of three-dimensional thermal stratification phenomenon in the upper plenum of a lead-bismuth cooled fast reactor based on a graph neural network[J]. Progress in Nuclear Energy, 2025, 188: 105874.

[4] Liu Z, Zhao P*, Florin B A, et al. Thermal stratification prediction in reactor system based on CFD simulations accelerated by a data-driven coarse-grid turbulence model[J]. Nuclear Engineering and Technology, 2025, 57(4): 103288.  

[5] Zhang X, Zeng F, Zhao P*. Study on non-uniform circumferential temperature distribution of annular fuel in the tight lattice configuration of a lead-bismuth cooled fast reactor[J]. Progress in Nuclear Energy, 2024, 176: 105383.

[6] Xiang Z, Chen Q, Zhao P*. Application of data-driven model reduction techniques in reactor neutron field calculations[J]. Nuclear Engineering and Technology, 2024, 56(8): 2948-2957.

[7] Zhang A, Chun S, Cheng Z, Zhao P*. Predicting the core thermal hydraulic parameters with a gated recurrent unit model based on the soft attention mechanism [J]. Nuclear Engineering and Technology, 2024, 56(6): 2343-2351.

[8] Tang M, Yang J, Zhao P*, et al. Research on design requirements for passive residual heat removal system of lead cooled fast reactor via model-based system engineering[J]. Nuclear Engineering and Technology, 2024.

[9] Qi J, Ai Q, Zhao P*, et al. Design and optimization analysis of a new double-layer tube type heat exchanger for lead-bismuth reactors[J]. Frontiers in Energy Research, 2024, 12: 1379747

[10] Yang T, Zhao P*, Zhao Y, et al. Development of reduced-order thermal stratification model for upper plenum of a lead–bismuth fast reactor based on CFD[J]. Nuclear Engineering and Technology, 2023.

[11] Xiao Y, Peng L, Zhao P*, et al. A novel method for calculating annular fuel cell resonance effective temperature[J]. Annals of Nuclear Energy, 2023, 192: 109950.

[12] Peng L, Zhao P*, Yu T. Study on anti-disturbance capacity of LBE cooled double loop natural circulation system under asymmetric conditions[J]. Annals of Nuclear Energy, 2023, 182: 109584.

[13] Zhao P, Wang T, Zhu E, et al. Research on proportional method for experimental facility of lead-based fast reactor with natural circulation[J]. Annals of Nuclear Energy, 2022, 172: 109096.

[14] Zhu E, Chen Q, Zhao P*, et al. Research on multi-objective optimization method for flow distribution of natural circulation reactor during its life-cycle[J]. Annals of Nuclear Energy, 2022, 176: 109266.

[15] Wang T, Wang Y, Zhao P*, et al. Study on the key influencing factors of reverse flow in U-tube steam generator under natural circulation[J]. Annals of Nuclear Energy, 2022, 171: 109035.

[16] Xiao Y, Yang J, Zhao P*, et al. Research on core power maximization method of natural circulation lead-bismuth cooled fast reactor[J]. Frontiers in Energy Research, 2022, 10: 961547.

[17] Yu Q, Dai S, Zhao P*, et al. Intelligent Optimization Method for Core Flow Zoning of Long-Cycle Lead-Bismuth-Cooled Reactor[J]. Frontiers in Energy Research, 2022, 10: 849874.  

[18] Yi J, Ji N, Zhao P*, et al. Research on the method of predicting CEFR core thermal hydraulic parameters based on adaptive radial basis function neural network[J]. Frontiers in Energy Research, 2022, 10: 961901.  

[19] Shi W, Yi F, Zhao P*, et al. Flow distribution investigation and sensitive analyses on reverse flow in U-tubes of steam generator under natural circulation[J]. Annals of Nuclear Energy, 2021, 154: 108112.  

[20] Zhao P, Lei Z, Yu T, et al. Uncertainty analysis in coupled neutronic/thermal-hydraulic calculations based on computational fluid dynamics[J]. Annals of Nuclear Energy, 2021, 156: 108215.

[21] Zhu E, Wang T, Zhao P*, et al. Stability analysis of a parallel channel-loop system with single-phase natural circulation under asymmetric conditions[J]. Annals of Nuclear Energy, 2021, 163: 108552.

[22] Guo C, Zhao P*, Deng J, et al. Safety analysis of small modular natural circulation lead-cooled fast reactor SNCLFR-100 under unprotected transient[J]. Frontiers in Energy Research, 2021, 9: 678939.

[23] Yang T, Zhao P*, Li Q, et al. Study on Thermophysical Properties of a Lead–Bismuth-Based Graphene Nanofluid[J]. Frontiers in Energy Research, 2021, 9: 727447.

[24] Zhao P, Liu Z, Yu T, et al. Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor[J]. Nuclear Engineering and Technology, 2020, 52(12): 2789-2802.

[25] Zhao P, Shi K, Li S, et al. CFD analysis of the primary cooling system for the small modular natural circulation lead cooled fast reactor SNRLFR-100[J]. Science and Technology of Nuclear Installations, 2016, 2016.

[26] Zhao P, Li S, Chen Z, et al. Natural circulation characteristics analysis of a small modular natural circulation lead–bismuth eutectic cooled fast reactor[J]. Progress in Nuclear Energy, 2015, 83: 220-228.

【招生要求】

（1）良好的英语阅读、写作能力；

（2）数学和物理方面基本功扎实；

（3）能够熟练应用计算机语言编程、人工智能算法；

（4）勤于思考，善于交流，有上进心。

【联系方式】

邮箱：pengcheng.zhao@usc.edu.cn