Publications 

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. Conceptual Design of Subcritical Reactor for China Initiative Accelerator Driven System[J]. Atomic Energy Science and Technology, 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. Study on Response Characteristic of CiADS Sub-critical Reactor Fuel Cladding under Beam Transient [J]. Atomic Energy Science and Technology, 2018, 52(5):931-936. (EI) 

22. Safety Analysis of CiADS Sub-Critical Reactor Fuel Cladding under Beam Transients [J]. Nuclear Power Engineering, 2018, 39(5):51-57. (EI) 

23. Experiment and Simulation Study for Fuel Rod Worth of Venus-Ⅱ Light Water Reactor[J]. Atomic Energy Science and Technology, 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. Application of Continuum Modeling of Dense Granular Flow[J]. Atomic Energy Science and Technology, 2019. (EI) 

Patents 

1. Locking or lifting mechanism and mothods of reactor fuel assembly[P]. 201711323628.5 

2. A refractive index matching fluid[P]. 201910247620.8 

3. A kind of positioning device and its making and use method with external helicoid groove[P]. 201811472853.X 

4. A kind of positioning device and its application method with internal helicoid groove[P]. 201811599315.7 

5. A kind of visualization fuel rod[P]. 201811616507.4 

6. A locking, unlocking and grabbing lifting device for lead-based reactor fuel assembly[P]. 201910958005.8 

7. A refueling grab mechanism for lead based reactor fuel assemblies[P]. 201910958022.1 

8. A upper pipe base self-locking mechanism for lead-based reactor fuel assembly[P]. 201910925021.7 

9. A lower tube seat buoyancy locking mechanism for lead-based reactor fuel assembly[P]. 201910957810.9 

10. An inner heater and its reactor[P]. 201910411195.1