已发表成果:
WOK 论文 40 篇;中文核心 26 篇;其它论文 3 篇;专利发明 9 个;图书及章节 1 本;
The impact of coal to nuclear on regional energy system
Experimental study of supercritical carbon dioxide heat transfer deterioration in a vertical tube under high heat flux
Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies
Technological Frontiers in Gen4 nuclear energy systems and small reactors
Experimental Study on S-CO2 Forced Convection Heat Transfer in Tubes under High-temperature Condition
Experimental study on convective heat transfer of S-CO2 under high heat flux
Research on Suppressant Characteristic in Pressure Suppression Pool of Small Pressurized Water Reactor
Influence of compressor inlet correction on simulation of supercritical carbon dioxide Brayton cycle
<i>In situ</i> studies on the evolution of damage microstructures in tungsten under heavy ion irradiation and post annealing
Numerical simulation of Rayleigh-Benard convection with supercritical carbon dioxide in a shallow cavity
Development of transient thermal-hydraulic analysis code for SCO2-cooled reactor coupled with Brayton cycle and its application
Numerical analysis of Poiseuille-Rayleigh-Benard convection in supercritical carbon dioxide
Experimental study on surface reaction during water injection on molten Zr/Fe pool
<p>In-situ TEM investigation of dislocation loop evolution in Al-forming austenitic stainless steels during Fe+ irradiation: Effects of irradiation dose and pre-existing dislocations</p>
Experimental study on heat transfer characteristics of supercritical carbon dioxide natural circulation
Repowering Coal Power in China by Nuclear Energy-Implementation Strategy and Potential
Comparative study of the supercritical carbon-dioxide recompression Brayton cycle with different control strategies
Experimental Study on Friction Coefficient of Supercritical Carbon Dioxide
The optimization for the straight-channel PCHE size for supercritical CO2 Brayton cycle
Multi-objective optimization based on economic analysis for a printed circuit heat exchanger with application to Brayton cycle
A thermal-hydraulic analysis model of printed circuit heat exchangers for system simulation using Modelica
Mobile charging: A novel charging system for electric vehicles in urban areas?
Analysis of Natural Cycle Characteristics of Supercritical Carbon Dioxide in Rectangular Loop
Measurement and analysis of specific heat capacity of lead-bismuth eutectic
Seesaw structured triboelectric nanogenerator with enhanced output performance and its applications in self-powered motion sensing
Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel
Modeling convective heat transfer of supercritical carbon dioxide using an artificial neural network
Development of a model for thermal-hydraulic analysis of helically coiled tube once-through steam generator based on Modelica
Analysis of variability in supercritical carbon dioxide recompression brayton cycle
Numerical analysis of the flow behavior in a helically coiled once through steam generator
Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment
The excess reactivity management in small pressurized water reactor utilizing fully ceramic microencapsulated fuel
Development of a computer code for thermalehydraulic design and analysis of helically coiled tube once-through steam generator
The safety analysis of a small pressurized water reactor utilizing fully ceramic microencapsulated fuel
Modeling and simulating supercritical CO2 Brayton cycle in SMR using Modelica
CFD analysis of the primary side in a helical-coil once-through steam generator
Microstructural evolution, thermodynamics, and kinetics of Mo-Tm2O3powder mixtures during ball milling
Analysis of levelized cost of electricity for travelling wave reactor
Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
Effect of platform motion on the safety performance of an offshore floating nuclear power plant
物理信息神经网络对圆管内层流流动和换热的数值模拟验证与求解效率研究
厦门大学学报(自然科学版),0438-0479,2024-11-19.亚临界和超临界CO2在竖直加热圆管内的流动传热特性
厦门大学学报(自然科学版),0438-0479,2024-09-13.铅铋堆燃料组件子通道计算方法优化
核技术,0253-3219,2024-07-15.弥散流工况下矩形窄缝通道鼓包对流动传热的影响
厦门大学学报(自然科学版),0438-0479,2024-05-23.高温工况下管内S-CO2强迫对流换热实验研究
原子能科学技术,1000-6931,2023-06-30.高温工况下管内S-CO2强迫对流换热实验研究
原子能科学技术,1000-6931,2023-06-30.小型压水堆抑压水池抑压特性研究
原子能科学技术,1000-6931,2023-06-20.氦氙反应堆子通道湍流交混系数研究
厦门大学学报(自然科学版),0438-0479,2022-4-25.氦氙反应堆子通道交混系数研究
厦门大学学报(自然科学版),0438-0479,2022-04-25.超临界二氧化碳摩擦系数实验研究
核动力工程,0258-0926,2021-06-30.超临界二氧化碳的自然循环流动特性
厦门大学学报(自然科学版),0438-0479,2021-06-28.基于新型在线水处理技术的节能减排效果研究
全球能源互联网,2096-5125,2021-03-25.不同几何和换热条件下转子风阻变化规律
厦门大学学报(自然科学版),0438-0479,2021-03-12.不同几何和换热条件下转子风阻的变化规律
厦门大学学报(自然科学版),0438-0479,2021-03-12.超临界二氧化碳在矩形回路中的自然循环特性分析
核动力工程,0258-0926,2020-08-20.基于OpenFOAM的超临界CO2流动与传热求解器的开发与验证
厦门大学学报(自然科学版),0438-0479,2020-04-09.涡轮机械转子在二氧化碳工质中风摩损耗的数值分析
厦门大学学报(自然科学版),0438-0479,2019-10-30.超临界二氧化碳再压缩布雷顿循环变工况特性分析
原子能科学技术,1000-6931,2018.压力对超临界二氧化碳布雷顿循环系统的影响
哈尔滨工程大学学报,1006-7043,2017-04-25.过冷沸腾通道内截面汽泡平均直径预测模型研究
核动力工程,0258-0926,2017-04-15.自然循环工况下倒U型管蒸汽发生器管内倒流的数值计算分析
厦门大学学报. 自然科学版,0438-0479,2017.自然循环工况下倒U型管蒸汽发生器的一次侧流量反转机理
厦门大学学报. 自然科学版,0438-0479,2017.行波堆平准化发电成本分析
原子能科学技术,1000-6931,2016-02-20.基于TRISO燃料的小型压水堆研究
厦门大学学报(自然科学版),0438-0479,2015-09-28.核反应堆系统中以超临界二氧化碳为工质的热力循环过程的建模与分析
厦门大学学报(自然科学版),0438-0479,2015-09-28.不同材料对行波堆有效增殖因数的影响因素分析
厦门大学学报(自然科学版),0438-0479,2015-09-28.薄板烘丝机筒内结垢程度对设备工艺性能的影响
轻工学报,2096-1553,2025-02-15.煤电改核电的经济性分析
厦门大学学报(自然科学版),0438-0479,2025-01-28.中英双语教学背景下学期大作业对本科生学习的提升作用
教育观察,2095-3712,2019-05-10.点亮蜡烛:一种创新性核反应堆燃耗策略. (译著). 中国原子能出版社, 2014年12月.