论文 

　　1. Thermal-hydraulic Modeling and Transient Analysis of Helium-cooled Tungsten Target Coupled with ADS Core[J]. Annals of Nuclear Energy, 2016, 87:612-620. (SCI) 

　　2. Accident analysis of tungsten target coupled with ADS core[J]. International Journal of Hydrogen Energy, 2016, 41:7059-7068. (SCI) 

　　3. Preliminary physics study of the lead–bismuth eutectic spallation target for China initiative accelerator-driven system[J]. Nuclear Science and Techniques, 2016, 27(5): 120. (SCI) 

　　4. Development and validation of burnup-transport code system OMCB for accelerator driven system. Nuclear Engineering and Design, 2017, 324: 360-371. (SCI) 

　　5. FreeCAD based modeling study on MCNPX for accelerator driven system[J]. Progress in Nuclear Energy, 2018, 107:100-109. (SCI) 

　　6. CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation[J]. Annals of Nuclear Energy, 2018, 114: 329-341. (SCI) 

　　7. Measurement of tungsten reactivity worth on VENUS-II light water reactor and validation of evaluated nuclear data[J]. Progress in Nuclear Energy, 2018, 108:81-88. (SCI) 

　　8. Development and validation of the code COUPLE3. 0 for the coupled analysis of neutron transport and burnup in ADS[J]. Nuclear Science and Techniques, 2018, 29(9): 124. (SCI) 

　　9. Modification on the contact model of LiPb and noncondensable gas in RELAP/SCDAPSIM/MOD4.0 and application to LOCA of China DFLL-TBM[J]. Fusion Engineering and Design, 2018, 134:35-42. (SCI) 

　　10. CFD simulation of pressure wave propagation in the helium coolant tube break accident of DFLL-TBM[J]. Fusion Engineering and Design, 2018, 136:950-957. (SCI) 

　　11. Evaluation of displacement cross-section for neutron-irradiated 15-15Ti steel and its swelling behavior in CiADS radiation environment[J]. Annals of Nuclear Energy, 2019, 133:937-949. (SCI) 

　　12. Deterministic simulation of the static neutronic characteristics for the lead core of VENUS-II facility[J]. Nuclear Engineering and Design, 2019, 133:353-368. (SCI) 

　　13. HLMIF, a facility for investigating the synergistic effect of ion-irradiation and LBE corrosion[J]. Journal of Nuclear Materials, 2019, 523:260-267. (SCI) 

　　14. Physical studies of minor actinide transmutation in the accelerator-driven subcritical system[J]. Nuclear Science and Techniques, 2019, 30(6). (SCI) 

　　15. Numerical model and program development of TWH salt cavern construction for UGS[J]. Journal of Petroleum Science and Engineering, 2019, 179:930-940. (SCI) 

　　16. The influence of the water injection method on two-well-horizontal salt cavern construction[J]. Journal of Petroleum Science and Engineering, 2020, 184:106560. (SCI) 

　　17. Thermal-hydraulic Design and Transient Analysis of Helium-cooled Solid Target for ADS[C]. 22nd International Conference on Nuclear Engineering, 2014. (EI) 

　　18. Concept Design and Thermal-hydraulic Analysis for Helium-cooled ADS[C]. 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015. (EI) 

　　19. 中国加速器驱动嬗变研究装置次临界反应堆概念设计[J]. 原子能科学技术, 2017, 51(12):2235-2241. (EI) 

　　20. Neutronic study on a new concept of accelerator driven subcritical system in China[C]. ICONE26, 2018, ICONE26-81329, V005T05A007. (EI) 

　　21. 束流瞬变下CiADS次临界反应堆燃料包壳响应特性研究[J]. 原子能科学技术, 2018, 52(5):931-936. (EI) 

　　22. 束流瞬变下CiADS次临界反应堆燃料包壳安全分析[J]. 核动力工程, 2018, 39(5):51-57. (EI) 

　　23. 启明星II号轻水堆燃料棒价值实验和模拟研究[J].原子能科学技术, 2018, 52(9): 1665-1670. (EI) 

　　24. Modification of RELAP/SCDAPSIM/MOD4.0 for Liquid Metal in Contact with Noncondensable Gas[C]. 26th International Conference on Nuclear Engineering. 2018, London, England. (EI) 

　　25. Investigation on Thermal-hydraulic Parameters and Instability Under Two Different Heating Conditions Based On RELAP5 Code[C]. 26th International Conference on Nuclear Engineering. 2018, London, England. (EI) 

　　26. 密集颗粒流动的连续性方法应用研究[J]. 原子能科学技术, 2019. (EI) 

　　专利 

　　1.反应堆燃料组件的锁紧与提升机构以及锁紧与提升方法[P]. 201711323628.5 

　　2.一种折射率匹配液[P]. 201910247620.8 

　　3.一种具有外部螺旋槽纹的定位装置及其制作和使用方法[P]. 201811472853.X 

　　4.一种具有内部螺旋槽纹的定位装置及其使用方法[P]. 201811599315.7 

　　5.一种可视化燃料棒[P]. 201811616507.4 

　　6.一种铅基反应堆燃料组件的锁紧、解锁及抓取提升装置[P]. 201910958005.8 

　　7.一种用于铅基反应堆燃料组件的换料抓头机构[P]. 201910958022.1 

　　8.一种铅基反应堆燃料组件的上管座自锁机构[P]. 201910925021.7 

　　9.一种铅基反应堆燃料组件的下管座浮力锁紧机构[P]. 201910957810.9 

　　10.用于核反应堆的加热器及核反应堆[P]. 201910411195.1