| Number |
Name |
Graduation date |
Research topic |
| 1 |
Xueming Shi |
2002/6/1 |
Optimization of fuel management in high throughput engineering test Reactor |
| 2 |
Lihua Wang |
2003/6/1 |
Methodology Research of Coupled Particle Transport，Depletion，Activation and Source- |
| 3 |
Bo Yang |
2004/6/1 |
Optimization study on the loading of combustible poisons in pressurized water reactor nuclear power plant core |
| 4 |
Haifeng Liu |
2004/6/1 |
Study on calculation of reflector homogenization parameters of pressurized water reactor |
| 5 |
Pingping Liu |
2005/6/1 |
Research on penetration probability method based on triangular mesh |
| 6 |
Junjun Xiang |
2006/6/1 |
Nonuniform calculation of reactor fuel assembly parameters based on MC method |
| 7 |
Qiwei Liu |
2006/3/1 |
Steady state and transient dynamics calculation of three-dimensional discrete longitudinal neutron transport equation |
| 8 |
Feng Xiao |
2006/6/1 |
Calculation of first order neutron transport equation by discrete ordinate finite element method and Krylov subspace |
| 9 |
Yuhua Liu |
2006/6/1 |
Study on multi-cycle fuel management and optimization in Qinshan Nuclear Power Plant |
| 10 |
Jun Zhang |
2007/6/1 |
Parallel SN calculation of neutron transport in two-dimensional unstructured grids |
| 11 |
Qing Ye |
2007/6/1 |
Spherical harmonic function method for neutron transport equation in two-dimensional cylindrical coordinate system |
| 12 |
Xingguang Sun |
2007/6/1 |
Study on acceleration method for numerical calculation of neutron transport equation |
| 13 |
WeiBing Huang |
2008/6/1 |
Resonance Self-Shielding Calculation in Arbitrary Geometries |
| 14 |
Xiaoyan Xu |
2008/6/1 |
A Time-Dependent 3D Neutron Transport Methodology and Its Application in Solution |
| 15 |
Sitao Peng |
2008/6/1 |
Study on calculation method of small group cross section parameters for aqueous medical isotope production reactor |
| 16 |
Ping Yang |
2011/3/1 |
Core design of pressurized tube supercritical water cooled reactor based on 3D physical thermo-mechanical coupling |
| 17 |
Shizhuang Jia |
2011/6/1 |
Core Design Study on Pressure Tube SCWR with 3-D Neutronics and Thermal-Hydraulics |
| 18 |
Yulong Qin |
2011/6/1 |
Ultra-fine Group Resonance Calculation Method of Multi-group Neutron Calculation and |
| 19 |
Zhiyan liu |
2011/6/1 |
Development of Continuous Energy Nuclear Data Library and Multi-group Nuclear Data Library for Neutronics Calculation |
| 20 |
Lei Lou |
2012/6/1 |
Study on the Conceptual Core Design of Traveling Wave Reactors with Radial Fuel Shuffling Scheme |
| 21 |
Chenlin Wang |
2012/6/1 |
Study on the Fuel Management and Economical Analysis of Utilizating PWR Recycled Uranium in CANDU Reactors |
| 22 |
Mengqi Wang |
2012/6/1 |
Study on Scattering Correction and Image Reconstruction Based on 3D Cone-Beam Flash Radiography |
| 23 |
Bing Du |
2012/6/1 |
Fast Calculation Method for Three-Dimensional Space-Time Neutron Diffusion Kinetics Equations and Study of Neutron Kinetics for Source-Driven Subcritical System |
| 24 |
Halei Dang |
2012/6/1 |
Study on the Verification and Validation Methods of PWR Fuel Assembly Calculation Programs |
| 25 |
Yunli Xie |
2013/6/1 |
Conceptual Design of a Hybrid Reactor for Tritium Production and its Thorium-Uranium United Joint Fuel Cycle with PWR |
| 26 |
Hongyue Zhang |
2013/6/1 |
Development and Analysis of a PWR Lattice Calculation Code |
| 27 |
Shengnan Gao |
2015/6/1 |
PWR Few-Group Constant Parameterization Methodology Study and Code Development |
| 28 |
Yunfan Ma |
2016/6/1 |
The Study of Transient Safety Analysis of Pressurized Water Reactor for Long-lived Fission Products Transmutation |
| 29 |
Dingyong Chen |
2016/6/1 |
Fuel Management and Core Analysis for PWR Core with MOX Fuel |
| 30 |
Chao Tian |
2016/6/1 |
Research on PWR Lattice Calculation Methods and Development of the NECP-CACTI Code |
| 31 |
Xiong Zhang |
2017/6/1 |
Design Analysis and Experimental Investigation of a New Neutron Ambient Dose Equivalent Rate Meter |
| 32 |
Yin Jin |
2017/6/2 |
Methods Investigation and Code Development for Advanced PWR Control Rod Cusping Effect and History Effect Treatments |
| 33 |
Yaodong He |
2017/6/3 |
Analysis of PWR Pin-by-pin Few-Group ConstantsParameterization |
| 34 |
Tao He |
2018/6/1 |
Methodology Investigation and Bamboo-Transient CodeDevelopment for Three-Dimensional PWR-core TransientAnalysis |
| 35 |
Shen Qu |
2018/6/1 |
Steady and Transient Neutronic Analysis of Heat Pipe CooledSpace Reactor |
| 36 |
Dangwei Ma |
2018/6/1 |
Research on Multiple Parallel Algorithm Based on 2D/D Fusion Neutron Transport Calculation |
| 37 |
Dongyong Wang |
2018/6/1 |
Improvement and Application of the PWR Lattice Calculation Code Bamboo-Lattice |
| 38 |
Weihua Xie |
2018/6/1 |
Three-DimensionalPWR-core Pin-by-pin Neutron KineticsCalculation Method |
| 39 |
Yang Liu |
2019/9/1 |
Three Dimensional Long Characteristics Method and ItsAcceleration Method Based on CSG Modeling |
| 40 |
Pei Zhao |
2019/9/2 |
Development and Verification for Reconstruction and ReactoCore Nuclear Data Library Generation Modules in the Nuclea Data Processing Code NECP-Aflas |
| 41 |
Zian Zhai |
2019/9/3 |
Improvements of Sodium-cooled Fast Reactor Reactivity andBurnup Calculation Methods and the Core Code Verification andValidation |
| 42 |
Chi Lei |
2019/9/4 |
Conceptual Design Study of a Small Mobile Long-lifeLead-bismuth Cooled Reactor Core |
| 43 |
Hang Zhou |
2019/9/5 |
Validation of the Fast Reactor Neutronics Code NECP-SARAXand its Application in ADS |
| 44 |
Huchao Bi |
2019/9/6 |
Probability Table Generation Method Study and Module Development for Unresolved Resonance Region |
| 45 |
Nimra |
2019/9/5 |
Study on core design scheme of small modular pressurized water reactor loaded with all ceramic coated particles (FCM) accident tolerant fuel |
| 46 |
Yifan Zhang |
2020/3/1 |
Shielding Design and Core Safety Analysis of Megawatt ScaleVehicle-Mounted Fast Reacto |
| 47 |
Ce Zhang |
2020/6/1 |
|
| 48 |
Zhuojie Sui |
2020/6/1 |
Uncertainty Quanfificafion Method for High Fidelity Reacto Physics Transient Analysis |
| 49 |
Bin Sun |
2020/6/1 |
Ex-Core Detector Response Simulation Analysis for the First AP1000 |
| 50 |
Yu Liu |
2021/6/1 |
Homogenization and Parameterization of the Microscopic CrossSections and Reflector for the Commercial PWRS |
| 51 |
Qishen Teng |
2021/6/1 |
Calculation Method and Code Development for Multigroup Coyariance Data |
| 52 |
Fenglin Han |
2021/6/1 |
Generation Method and Code Development for NeutronActivation and Radiation Source Term Data Library |
| 53 |
Xuewen Wu |
2021/6/1 |
Research on Generation Method of Few-group Cross SectionsBased on High-order Flux and its Code Development Verification and Validation |
| 54 |
Jianda Chen |
2021/6/1 |
Research on Fine Power Calculation Method and Code Development and Application for the Core with HexagonalAssembly |
| 55 |
Jianxin Miao |
2021/6/1 |
Functional development and parallel optimization of deterministic neutronics analysis program for fusion reactor cladding |
| 56 |
Xing Huang |
2021/6/1 |
Research on the Refined Modeling Method for the Fuel-assemblyGrid and Reflector Assembly of fhe Commercial PWRS |
| 57 |
Junji Chen |
2021/6/1 |
Function Development and Acceleration and Parallel Research ofHexagonal Reactor Transport Calculation for High-fidelityReactor Physics Code NECP-X |
| 58 |
Minwan Zhang |
2021/6/1 |
Neutronics and Thermal-hydraulics Coupling AnalysisMethod Based on Fine Model and its Application in AdvancedPressurized Water Reactors |
