
研究員
3D打印技術(shù)研究中心
核反應(yīng)堆熱工水力試驗(yàn)研究與安全分析
汽液兩相流動(dòng)與沸騰傳熱
關(guān)鍵結(jié)構(gòu)件增材制造創(chuàng)新優(yōu)化設(shè)計(jì)
金屬材料激光加工、增減材復(fù)合制造以及加工成型
巖土3D打印及其材料
1. 2019,中廣核研究院發(fā)展獎(jiǎng),院級(jí),1
2. 2017,廣東省電機(jī)工程學(xué)會(huì)優(yōu)秀論文獎(jiǎng),省級(jí),1
3. 2016,中廣核研究院優(yōu)秀論文獎(jiǎng),院級(jí),1
4. 2015,GenIV International Forum: The 7th International Symposium on Supercritical Water-Cooled Reactors Best Paper Award,國(guó)際學(xué)術(shù)會(huì)議論文獎(jiǎng),2
5. 2013,中廣核研究院科技成果獎(jiǎng),院級(jí),1
6. 2007,中國(guó)核工業(yè)集團(tuán)優(yōu)秀國(guó)防科技報(bào)告獎(jiǎng),部級(jí),11. 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
10. Experimental study on the density wave oscillation in parallel rectangular channels with narrow gap, Annals of Nuclear Energy, 2011, 21. 2022,核燃料組件結(jié)構(gòu)件增材制造與性能評(píng)定,1
2. 2021,增材制造工藝研究,1
3. 2020,雙金屬表面結(jié)合層性能研究,1