| A new high-fidelity neutronics code NECP-X J Chen, Z Liu, C Zhao, Q He, T Zu, L Cao, H Wu Annals of Nuclear Energy 116, 417-428, 2018 | 150 | 2018 |
| A new three-dimensional method of characteristics for the neutron transport calculation Z Liu, H Wu, L Cao, Q Chen, Y Li Annals of Nuclear Energy 38 (2-3), 447-454, 2011 | 88 | 2011 |
| Fuel, core design and subchannel analysis of a superfast reactor L Cao, Y Oka, Y Ishiwatari, Z Shang Journal of Nuclear Science and Technology 45 (2), 138-148, 2008 | 71 | 2008 |
| NECP-Atlas: A new nuclear data processing code T Zu, J Xu, Y Tang, H Bi, F Zhao, L Cao, H Wu Annals of Nuclear Energy 123, 153-161, 2019 | 67 | 2019 |
| The pseudo-resonant-nuclide subgroup method based global–local self-shielding calculation scheme Z Liu, Q He, T Zu, L Cao, H Wu, Q Zhang Journal of Nuclear Science and Technology 55 (2), 217-228, 2018 | 65 | 2018 |
| Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD Q Chen, H Wu, L Cao Nuclear Engineering and Design 238 (10), 2828-2833, 2008 | 60 | 2008 |
| NECP-MCX: a hybrid Monte-Carlo-deterministic particle-transport code for the simulation of deep-penetration problems Q He, Q Zheng, J Li, H Wu, W Shen, L Cao, Z Liu, J Xu Annals of Nuclear Energy 151, 107978, 2021 | 55 | 2021 |
| Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice Y Li, B Zhang, Q He, D Wang, H Wu, L Cao, W Shen Nuclear Engineering and Design 335, 432-440, 2018 | 42 | 2018 |
| Transient methods for pin-resolved whole core transport using the 2D-1D methodology in MPACT A Zhu, Y Xu, A Graham, M Young, T Downar, L Cao Proc. M&C, 19-23, 2015 | 41 | 2015 |
| Improved leakage splitting method for the 2D/1D transport calculation C Zhao, Z Liu, L Liang, J Chen, L Cao, H Wu Progress in Nuclear Energy 105, 202-210, 2018 | 38 | 2018 |
| An improved resonance self-shielding calculation method based on equivalence theory Q Zhang, H Wu, L Cao, Y Zheng Nuclear Science and Engineering 179 (3), 233-252, 2015 | 37 | 2015 |
| Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry L Xu, L Cao, Y Zheng, H Wu Progress in Nuclear Energy 94, 1-21, 2017 | 36 | 2017 |
| LAVENDER: a steady-state core analysis code for design studies of accelerator driven subcritical reactors S Zhou, H Wu, L Cao, Y Zheng, K Huang, M He, X Li Nuclear Engineering and Design 278, 434-444, 2014 | 34 | 2014 |
| Improvements to the Transmutation Trajectory Analysis of depletion evaluation K Huang, H Wu, L Cao, Y Li, W Shen Annals of Nuclear Energy 87, 637-647, 2016 | 32 | 2016 |
| Code development for eigenvalue total sensitivity analysis and total uncertainty analysis C Wan, L Cao, H Wu, T Zu, W Shen Annals of Nuclear Energy 85, 788-797, 2015 | 32 | 2015 |
| An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methods H Zhang, H Wu, L Cao Annals of Nuclear Energy 38 (12), 2742-2751, 2011 | 31 | 2011 |
| Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core W Yang, H Wu, Y Li, J Yang, L Cao Nuclear Engineering and Design 337, 279-290, 2018 | 30 | 2018 |
| Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY T Hu, L Cao, H Wu, X Du, M He Annals of Nuclear Energy 109, 260-276, 2017 | 30 | 2017 |
| Spherical harmonics method for neutron transport equation based on unstructured-meshes LZ Cao, HC Wu Nucl. Sci. Tech 15 (6), 335-339, 2004 | 29 | 2004 |
| A modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method B Wang, Z Liu, J Chen, C Zhao, L Cao, H Wu Progress in Nuclear Energy 108, 122-135, 2018 | 28 | 2018 |
