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核反應堆熱工水力試驗研究與安全分析 

汽液兩相流動(dòng)與沸騰傳熱 

關(guān)鍵結構件增材制造創(chuàng )新優(yōu)化設計 

金屬材料激光加工、增減材復合制造以及加工成型 

1. 2019，中廣核研究院發(fā)展獎，院級，1 

2. 2017，廣東省電機工程學(xué)會(huì )優(yōu)秀論文獎，省級，1 

3. 2016，中廣核研究院優(yōu)秀論文獎，院級，1 

4. 2015，GenIV International Forum: The 7th International Symposium on Supercritical Water-Cooled Reactors Best Paper Award，國際學(xué)術(shù)會(huì )議論文獎，2 

5. 2013，中廣核研究院科技成果獎，院級，1 

1.  Experimental Study of Supercritical Water Heat Transfer Deteriorations in Different Channels, Annals of Nuclear Energy, 2018, 1 

2.  Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure, Journal of Nuclear Engineering and Radiation Science, 2018, 2 

3.  Experimental study on heat transfer of supercritical water flowing upward and downward in 2 2 rod bundle with wrapped wire, Annals of Nuclear Energy, 2018, 2 

4.  Experimental Investigation on Heat Transfer and Pressure Drop of Supercritical Water Flows In 2 2 Bundle With Wire Wraps, The 25th International Conference on Nuclear Engineering (ICONE25), 2017, 1 

5.  Experimental investigation on transient heat transfer in 2 2 bundle during depressurization from supercritical pressure, Annals of Nuclear Energy, 2017, 1 

6.  Experimental study on transient heat transfer across critical pressure in 2 2 rod bundle with wire wraps, International Journal of Heat and Mass Transfer, 2017, 1 

7.  Heat transfer to supercritical water in a 2 2 rod bundle, Annals of Nuclear Energy, 2015, 2 

8.  Experimental Research of Supercritical Water Heat Transfer in Different Channels, The 21st International Conference on Nuclear Engineering (ICONE21), 2013, 1 

9.  Heat Transfer Research on Supercritical Water Flow Upward in Tube, The 2012 International Congress on the Advances in Nuclear Power Plants (ICAPP’12), 2012, 1 

1. 2022，核燃料組件結構件增材制造與性能評定，1 

2. 2021，增材制造工藝研究，1