| Number |
Name |
Graduation Date |
Research topic |
| 1 |
Liangzhi Cao |
2005/6/1 |
Study on Solution of Neutron Transport Equation with Unstructured Grid Spherical Harmonic Function and Space-Time Dynamics Calculation |
| 2 |
Haitao Ju |
2007/3/1 |
Research on the Discrete Ordinates Method and New Acceleration Arithmetic of Neutron Transport Equation Using Least-Squares Finite-Element Method |
| 3 |
Haoliang Lu |
2007/7/1 |
Nodal Methods for the Neutron Diffusion and Transport Equations in Triangular Meshes |
| 4 |
Guoming Liu |
2009/12/1 |
Transmission Probability Method and Discrete Direction Probability Method for Solving the Neutron Integral Transport Equations in Unstured-Geometry |
| 5 |
Qichang Chen |
2010/9/1 |
Method of Characteristics for Arbitrary Geometry and App;ied Research on Assembly Calculation of Direct Cycle Reactor |
| 6 |
Qingjie Liu |
2011/3/1 |
Sub-group Resonance Calculation Method and its Application in the Dimensional Arbitrary Geometry |
| 7 |
Youqi Zheng |
2011/3/1 |
The Wavelet Expansion Method for Solving Neutron Transport Equation and its Application Analysis |
| 8 |
Weiyan Yang |
2011/6/1 |
Wavelet Scaling Function Expansion Method for Continuous-Energy Variable in Resonance Calculation |
| 9 |
Changhui Wang |
2011/9/1 |
Harmonics Expansion Method and Its Application in On-line Monitoring the In-core Power Distribution |
| 10 |
Yongqiang Zhou |
2012/3/1 |
Study on Fuel Management and Loading Optimization of Small Nuclear Reactor |
| 11 |
Hongbo Zhang |
2012/12/1 |
Matrix Method of Characteristics Based on Domain Decomposition and Research on 2D/1D Neutronics Numerical Method |
| 12 |
Yunzhao Li |
2013/3/1 |
Advanced Reactor Core Neutronics Computational Algorithms based on the Variational Nodal and Nodal SP3 Methods |
| 13 |
Kunpeng Wang |
2013/6/1 |
Analytic Basis Function Expansion Method in Arbitrary Triangular-z Node for Neutron Diffusion Equation and Its Application to Kinetics Analysis |
| 14 |
Tiejun Zu |
2013/12/1 |
Neutronics Computation Method and Conceptual Design of Fusion Driven Subcritical Reactor for Energy Production |
| 15 |
Zheng Zheng |
2014/3/1 |
Calculational Methods for Fast Neutron Fluence of Pressurized Water Reactor Pressure Vessel and Cavity Radiation Streaming |
| 16 |
Zhouyu Liu |
2014/3/1 |
Three-Dimensional Modular Characteristic Method for Neutron Transport Equation |
| 17 |
Guangchun Zhang |
2015/3/1 |
Three-Dimensional Deterministic Neutronics Calculation Methods for ITER Test Blanket Module |
| 18 |
Chuanqi Zhao |
2015/3/1 |
Neutronics/Thermal-Hydraulics Coupling Method and Pre-conceptual Design of Supercritical Water Reactor with Annular Fuel |
| 19 |
Kun Liu |
2015/6/1 |
Research on Neutronics Analyses of Long Lived Fission Products Transmutation in Thermal Reactors |
| 20 |
Ammar Ahmad |
2015/6/1 |
Study on the Core Design for Pressure Tube scWRs based on 3D Coupled Neutronics and Thermal Hydraulics Calculations |
| 21 |
yuxiong cheng |
2015/6/1 |
Research on Numerical Methods for High Energy Photon Inverse Tomography Transport Problems |
| 22 |
lei he |
2015/6/1 |
Research on Subgroup and Wavelet Expansion Coupling Resonant Method for Complex Lattice |
| 23 |
qian zhang |
2016/6/1 |
Research on Advanced Resonance Self-Shielding Calculation Method Based on Equivalence Theory |
| 24 |
chao yang |
2016/9/1 |
Research on Uncertainty Quantification for Burnup Calculation and its Application to High-Level Waste Transmutation Analysis |
| 25 |
kai huang |
2017/3/1 |
High Fidelity Depletion Calculation Methods Development for Numerical Reactors |
| 26 |
yunlong xiao |
2017/3/1 |
Fast Reactor Core Analysis Method and its Application to Preliminary Core Design for the Flexible Fast Breeder Reator |
| 27 |
mingtao he |
2017/3/1 |
Transport-based Transient Methods of Liquid-Metal Cooled Fast Reactors and Transient Characteristics of Minor Actinides Transmutation |
| 28 |
tengfei zhang |
2017/3/1 |
Research on Heterogeneous Variational Nodal Method and its Application to 3D Whole-Core Neutronics Computations |
| 29 |
shengcheng zhou |
2017/3/1 |
Neutronics Calculation and Fuel Cycle Analyses of Accelerator Driven Subcritical Transmuters |
| 30 |
xunzhao li |
2017/6/1 |
Neutronics Analysis of Accelerator-Driven Sub-critical System for MA transmutation |
| 31 |
zhifeng li |
2017/6/1 |
Study on the Neutronics Characteristics of the Pebble Bed Fluoride Salt Cooled High Tmperature Reactor |
| 32 |
kun zhuang |
2017/6/1 |
Steady-State and Transient Analysis of Channel-Type Molten Salt Reactor with Coupled Neutronics/Thermal Hydraulics |
| 33 |
baolin liu |
2017/6/1 |
Core Design and Transient Analysis of Supercritical CO2 Cooled Small Reactor Core with Coupled 3-D Neutronics/Thermal Hydraulicse |
| 34 |
yong liu |
2017/9/1 |
Research on Perturbation-theory-based Reactor-physics Sensitivity and Uncertainty Analysis and its Application |
| 35 |
liang liang |
2017/11/8 |
2D/1D and 2D/3D Coupling Neutron Transport Calculation Method Based on the Method of Characteristics |
| 36 |
qingming he |
2017/12/1 |
Three-Dimensional Whole-Core High-Fidelity Resonance Self-Shielding Calculation Method of Numerical Reactor |
| 37 |
bin zhang |
2017/12/1 |
Pin-Cell Homogenization Methods for PWR Whole-Core Pin-by-pin Calculation |
| 38 |
chenhui wan |
2018/3/1 |
Researches on Sensitivity and Uncertainty Analysis for Reactor Physics Computation and Its Application in Code Validation |
| 39 |
xianan du |
2018/6/1 |
Few-Group Cross Section Generation Method for Fast Reactor Analysis and its Verification and Validation |
| 40 |
Qasim Awan |
2018/6/1 |
Design and evaluation of all-ceramic coated pellet fuel components and small modular core cores |
| 41 |
Zhuo Li |
2018/9/1 |
PWR Three-Dimensional Online Power-Distribution Monitorimg Method and Its Sensitivity and Uncertainty Analysis |
| 42 |
Wen Yang |
2018/9/2 |
Study on PWR Three-dimensional Whole-core Pin-by-pin Physical Calculation Method |
| 43 |
Zhipeng Li |
2018/9/3 |
Hexagonal Variable Nodal Method based on Group Theory |
| 44 |
Longfei Xu |
2019/1/1 |
Massively Parallel SN Method and its application for PWR Physical and Shielding Calculation |
| 45 |
Jun Chen |
2019/3/1 |
High-fidelity Coupled Thermal-hydraulics Calculation Method Based on Three-Dimensional Neutron Transport and Subchannel Analysis |
| 46 |
Yongping Wang |
2019/3/2 |
Improved Three-Dimensional Heterogeneous Variational Nodal Method and Its Hybrid Parallelization |
| 47 |
Boning Liang |
2019/3/3 |
Improvements and Application Analysis of Neutron Diffusion Variational Nodal Method |
| 48 |
Tianliang Hu |
2019/3/4 |
Steady-State And Transient Analyses For Fast-Spectrum Molten Salt Reactor Based On Coupled Neutronics And Thermal-Hydraulics |
| 49 |
YIjun Zhang |
2019/6/1 |
PWR Core Transient Multiphysics Simulations Based on Newton- Iterative Method |
| 50 |
Zhitao Xu |
2019/6/2 |
Research on Neutron Transport Discrete Ordinates Nodal Method for Fast-Spectrum Reactor |
| 51 |
Jialong Xu |
2019/9/1 |
Research On New Methods of Nuclear Data Processing for Reactors and Development of Independent Nuclear-Data Processing Code NECP-Atlas |
| 52 |
Chen Zhao |
2019/12/1 |
Research for The Improvement of 2D/1D Transport Method and Application in the Numerical Reactors Physical Calculation |
| 53 |
Jikui Li |
2020/12/1 |
Research Advanced Resonance Calculation and Anisotropic Scattering Treatment Methods for Fuel Assemblies Loaded with Strong Absorbers in Pressurized Water Reactors |
| 54 |
Xingjian Wen |
2020/12/1 |
Numerical Reactor High-Fidelity Cycle Depletion And Source Term Calculation Method Development And Application |
| 55 |
Qi Zheng |
2020/12/1 |
Research on The Hybrid Stochastic Method And Code Development and Application in Neutron Shielding Calculation |
| 56 |
Chao Fang |
2021/3/1 |
Spherical Harmonic-Stabilized Finite Element Method for The First-Order Neutron Transport Equation and Its Application in the Fusion Reactor Blanket |
| 57 |
Bo Wang |
2021/6/1 |
Research and Application of Transient Analysis Methods with High-Fidelity Neutronics and Thermal-Hydraulics Coupling |
| 58 |
Fan Xia |
2021/6/1 |
Neutronics Calculation Method for Plate-Type Fuel Reactor-Core by Using Fine-Mesh Homogenization and Nodal-SP3 Method |
