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Zhou-Yu Liu, Xiaobei Xu, Hongchun Wu, Liang-Zhi Cao (2021). Multidimensional multiphysics simulations of the supercritical water-cooled fuel rod behaviors based on a new fuel performance code developed on the MOOSE platform. Nuclear Engineering and Design.DOI
Bin Sun, Yunzhao Li, Liang-Zhi Cao, Xuesong Li, Hongchun Wu, W. Shen, Tengfei Hao, Chenghui Wan (2021). Simulations of the source-range detector response for the fuel-loading process of the AP1000 cores.DOI
Tiejun Zu, Yongqiang Tang, Lipeng Wang, Liang-Zhi Cao, Hongchun Wu (2021). Thermal scattering law data generation for hydrogen bound in zirconium hydride based on the phonon density of states from first-principles calculations. Annals of Nuclear Energy.DOI
Yongqiang Tang, Tiejun Zu, Siyu Yi, Liang-Zhi Cao, Hongchun Wu (2021). Development and verification of thermal neutron scattering law data calculation module in nuclear data processing code NECP-Atlas. Annals of Nuclear Energy.DOI
Lu Cao, Zhou-Yu Liu, Xingjian Wen, Liang-Zhi Cao, Hongchun Wu, Shuai Qin (2021). Resonance calculation based on the deep learning method for treating the non-uniform fuel temperature distribution in PWRs.DOI
Qing-Ming He, Qi Zheng, Jie Li, Hongchun Wu, W. Shen, Liang-Zhi Cao, Zhou-Yu Liu, Jialong Xu (2021). NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems.DOI
Bingbing Ji, Zhiping Chen, Jia Liu, Liang-Zhi Cao, Zhuojie Sui, Hongchun Wu (2021). Moment Matching: A New Optimization-Based Sampling Scheme for Uncertainty Quantification of Reactor-Physics Analysis. Nuclear science and engineering.DOI
Tiejun Zu, Yihan Huang, Qichen Teng, Feng Han, Xing Huang, Chenghui Wan, Liang-Zhi Cao, Hongchun Wu (2021). Application of CENDL-3.2 and ENDF/B-VIII.0 on the reactor physics simulation of PWR.DOI
W. Shu, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu (2021). Performance of CENDL-3.2 evaluated nuclear data library for the shielding benchmarks.DOI
Shuai Qin, Qian Zhang, Liang Liang, Qing-Ming He, Hongchun Wu (2021). THE TWO-STEP APPROACH FOR WHOLE-CORE RESONANCE SELF-SHIELDING CALCULATION. EPJ Web of Conferences.DOI
Jiewei Yang, Hongchun Wu, Ling Guo, Yunzhao Li, Xuesong Li, Sicheng Wang, Tengfei Hao, Wenhao Ji (2021). Validation of NECP-Bamboo with BEAVRS and AP1000 measurements.DOI
Jie Li, Hongchun Wu, Qing-Ming He, W. Shen, Qi Zheng, Liang-Zhi Cao, Qi-Xiang Cao, Q. Shen (2021). The neutron-photon-coupling analysis of the tritium-breeding blanket in CFETR by NECP-MCX.DOI
Xinyu Zhou, Zhou-Yu Liu, Liang-Zhi Cao, Hongchun Wu, Zi'an Zhai (2021). A new online energy group condensation method for the high-fidelity neutronics code NECP-X.DOI
Xinyu Zhou, Zhou-Yu Liu, Lu Cao, L. Cao, Hongchun Wu, Yu Han, Chun-Tao Tang (2020). Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X.DOI
Qing-Ming He, Yijun Zhang, Zhou-Yu Liu, Liang-Zhi Cao, Hongchun Wu (2020). The JFNK method for the PWR's transient simulation considering neutronics, thermal hydraulics and mechanics.DOI
Tianliang Hu, Liang-Zhi Cao, Shou-Hai Yang, M. Fratoni, Hongchun Wu (2020). Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors. International Journal of Energy Research.DOI
Zhou-Yu Liu, Bo Wang, Minwan Zhang, Xinyu Zhou, Liang-Zhi Cao, Hongchun Wu (2020). An internal parallel coupling method based on NECP-X and CTF and analysis of the impact of thermal-hydraulic model to the high-fidelity calculations.DOI
Yunzhao Li, Wen Yang, Sicheng Wang, Hongchun Wu, Liang-Zhi Cao (2020). A three-dimensional PWR-core pin-by-pin analysis code NECP-Bamboo2.0.DOI
Chenghui Wan, Yihan Huang, Youqi Zheng, Liang-Zhi Cao, Hongchun Wu (2020). Nuclear-data adjustment based on the continue-energy cross-section library for the fast reactor.DOI
Shuai Qin, Qian Zhang, Liang Liang, Qiang Zhao, Zhi-Jian Zhang, Hongchun Wu, Liang-Zhi Cao (2020). Fitting-based resonance database method for resonance self-shielding calculations of large-scale task considering depletion and intra-pin distribution.DOI
Wen Yin, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu (2020). Development and verification of heat production and radiation damage energy production cross section module in the nuclear data processing code NECP-Atlas. Annals of Nuclear Energy.DOI
Jie Li, Yunzhao Li, W. Shen, Qi Zheng, Hongchun Wu (2020). Monte Carlo neutron-kinetics analysis in continuous time and energy. Annals of Nuclear Energy.DOI
Zhuo Li, Yu Ma, Qian Zhang, Liang-Zhi Cao, Hongchun Wu, Yunzhao Li (2020). Assembly pin factor parameterization method based on the proper orthogonal decomposition.DOI
Liang-Zhi Cao, Chao Fang, Hongchun Wu (2020). A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation. Transactions of the American Nuclear Society.DOI
T. Dai, Liang-Zhi Cao, Qing-Ming He, Hongchun Wu, W. Shen (2020). A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR.DOI
Bowen Xiao, Linfang Wei, Youqi Zheng, Bin Zhang, Hongchun Wu (2020). On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX.DOI
Yongping Wang, Chen Zhao, Hongchun Wu, Liang-Zhi Cao (2020). Comparison of the performance of heterogeneous variational nodal method and 2D/1D-MOC on pin-resolved neutron transport calculations of PWR.DOI
Qing-Ming He, Jun Chen, Zhou-Yu Liu, Liang-Zhi Cao, Hongchun Wu (2020). The on-the-fly subgroup method capable of treating spatial self-shielding, resonance interference and temperature distribution effects.DOI
Guangchun Zhang, Jie Liu, Liang-Zhi Cao, Hongchun Wu, Xianbao Yuan (2020). Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code Hydra. Nuclear Science and Techniques.DOI
Shuai Qin, Qian Zhang, Jinchao Zhang, Liang Liang, Qiang Zhao, Hongchun Wu, Liang-Zhi Cao (2020). Application of deep neural network for generating resonance self-shielded cross-section.DOI
Linfang Wei, Youqi Zheng, Xia-Nan Du, Hongchun Wu (2020). Extension of SARAX code system for reactors with intermediate spectrum.DOI
Yunzhao Li, T. He, Boning Liang, Hongchun Wu, Jiahe Bai, Jiewei Yang (2020). Development and verification of PWR-core nuclear design code system NECP-Bamboo: Part III: Bamboo-Transient.DOI
Chao Fang, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li, Jianxin Miao (2020). Modified least-squares finite element method for solving the Boltzmann transport equation with spherical harmonic angular approximation. Annals of Nuclear Energy.DOI
Chenghui Wan, Jialong Xu, Liang-Zhi Cao, Hongchun Wu (2020). Study on the linearization workflow for the generation of point-wise cross sections in nuclear data processing.DOI
Zhuo Li, Yu Ma, Liang-Zhi Cao, Hongchun Wu (2020). Uncertainty quantification of proper orthogonal decomposition based online power-distribution reconstruction.DOI
Chenghui Wan, Xiao-Yang Zou, Liang-Zhi Cao, Hongchun Wu (2020). Covariance comparisons between ENDF/B-VII.1 and ENDF/B-VIII.0 with application for the UAM-LWR exercises. Annals of Nuclear Energy.DOI
Yongping Wang, Zhitao Xu, Youqi Zheng, Hongchun Wu (2020). A new hexagonal-Z nodal SN method in SARAX code system.DOI
Qian Zhang, Qin Shuai, Qiang Zhao, Liang Liang, Hongchun Wu, Liang-Zhi Cao (2020). Improvements on the method of ultra-fine-group slowing-down solution coupled with method of characteristics on irregular geometries.DOI
Zhou-Yu Liu, Xinyu Zhou, Liang-Zhi Cao, Hongchun Wu (2020). A new three-level CMFD method based on the loosely coupled parallel strategy.DOI
Zhuo Li, Mingtao He, Liang-Zhi Cao, Hongchun Wu, W. Shen, Yong Liu (2020). Implementation and comparison of least-square method and thin-plate spline method for PWR online power-distribution monitoring based on NECP-ONION system.DOI
Lipeng Wang, Liang-Zhi Cao, Hongchun Wu, Lingti Kong, Yongqiang Tang (2020). Thermal neutron scattering properties of Bismuth crystal filter. Journal of Nuclear Science and Technology.DOI
Qing-Ming He, Wen Yin, Zhou-Yu Liu, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu (2020). Extension of the subgroup method for self-shielding calculation of fully ceramic micro-encapsulated fuel. Annals of Nuclear Energy.DOI
Qian Zhang, Liang Liang, Qiang Zhao, Zhi-Jian Zhang, Hongchun Wu, Liang-Zhi Cao (2020). A Comparison Between the Embedded Self-Shielding Method and the Enhanced Neutron Current Method Based on the Equivalent Pin Cell Model on the Irregular Fuel Lattice Problem. Nuclear science and engineering.DOI
Liang Liang, Qian Zhang, Ying Chen, Peitao Song, Zhi-Jian Zhang, Qiang Zhao, Hongchun Wu, Liang-Zhi Cao (2020). Least squares linear source approach in method of characteristics.DOI
Zhitao Xu, Youqi Zheng, Yongping Wang, Hongchun Wu (2020). IFDF acceleration method with adaptive diffusion coefficients for SN nodal calculation in SARAX code system.DOI
Liang Liang, Qian Zhang, Peitao Song, Zhi-Jian Zhang, Qiang Zhao, Hongchun Wu, Liang-Zhi Cao (2020). Overlapping communication and computation of GPU/CPU heterogeneous parallel spatial domain decomposition MOC method. Annals of Nuclear Energy.DOI
Liang-Zhi Cao, C. Lei, Hongchun Wu, Sheng-Cheng Zhou (2019). CONCEPTUAL CORE DESIGN OF A TRANSPORTABLE LEAD-BISMUTH COOLED FAST REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Chenghui Wan, Liang Qiao, Youqi Zheng, Liang-Zhi Cao, Hongchun Wu (2019). Validation of SARAX for the China Fast Reactor with the extrapolated experimental data. Annals of Nuclear Energy.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu (2019). Uncertainty quantification for the first-cycle modeling and simulations of the BEAVRS benchmark problem. Annals of Nuclear Energy.DOI
Liang-Zhi Cao, Zhuo Li, Hongchun Wu (2019). Numerical Simulation and Sensitivity Study of the Rhodium Self-Powered Neutron Detector Used in PWR. IEEE Transactions on Nuclear Science.DOI
Yongping Wang, Tengfei Zhang, E. Lewis, W.-S. Yang, Micheal A. Smith, Hongchun Wu (2019). Three-dimensional variational nodal method parallelization for pin resolved neutron transport calculations. Progress in nuclear energy (New series).DOI
Zhou-Yu Liu, Chen Zhao, Lu Cao, Hongchun Wu, Liang-Zhi Cao (2019). The material-region-based 2D/1D transport method. Annals of Nuclear Energy.DOI
Shuai Qin, Qian Zhang, Qiang Zhao, Liang Liang, Hongchun Wu, Lu Cao (2019). RESEARCH ON ACCELERATION OF ULTRA-FINE-GROUP CALCULATION BASED ON METHOD OF CHARACTERISTIC. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Kunpeng Wang, Chao Xu, Cong-Xin Li, Yu-Sheng Liu, Jian-Ping Jing, Hongchun Wu (2019). Rod Ejection and Drop Accident Analysis of Aqueous Homogeneous Solution Reactor. Frontiers in Energy Research.DOI
Sheng-Cheng Zhou, Liang-Zhi Cao, Hongchun Wu, B. Bai, C. Lei, Yi-Fan Zhang (2019). SPARK-LS: A novel design of a compact liquid chloride salt cooled fast reactor based on tube-in-duct fuel concept. Annals of Nuclear Energy.DOI
Qing-Ming He, Zhou-Yu Liu, Liang-Zhi Cao, Hongchun Wu (2019). Error analysis of approximations and treatments commonly made in multi-group library and self-shielding calculation based on NECP-X. Annals of Nuclear Energy.DOI
Linfang Wei, Youqi Zheng, Hongchun Wu (2019). Improvement of few-group cross-section generation in fast reactor analysis system SARAX. Annals of Nuclear Energy.DOI
Lipeng Wang, Du Jiang, Xinbiao Jiang, Liang-Zhi Cao, Hongchun Wu (2019). Investigation on the impact of thermal-kernel effect of lithium hydride on the reactivity of nuclear propulsion particle bed reactor. Annals of Nuclear Energy.DOI
Qi Zheng, W. Shen, Yunzhao Li, Hongchun Wu, Liang-Zhi Cao (2019). A deterministic-stochastic energy-hybrid method for neutron-transport calculation. Annals of Nuclear Energy.DOI
Yongping Wang, Yunzhao Li, Tengfei Zhang, E. Lewis, M. Smith, W.-S. Yang, Hongchun Wu (2019). Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method. Nuclear science and engineering.DOI
Jialong Xu, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu (2018). Development and Verification of a New Nuclear Data Processing System NECP-Atlas. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory.DOI
Qian Zhang, Qiang Zhao, Hongchun Wu, Liang-Zhi Cao, Zheng Zheng (2018). Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory.DOI
Sheng-Cheng Zhou, Hongchun Wu, Youqi Zheng (2018). Flexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios.DOI
Fan Xia, Tiejun Zu, Hongchun Wu (2018). Effect and treatment of angular dependency of multi-group total cross section and anisotropic scattering in fine-mesh transport calculation.DOI
Boning Liang, Hongchun Wu, Yunzhao Li (2018). Adaptive expansion order for diffusion Variational Nodal Method. Annals of Nuclear Energy.DOI
Chao Fang, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li (2018). Fast Sub-Grid Scale Finite Element Method for the First Order Neutron Transport Equation. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory.DOI
Zhou-Yu Liu, Liang Liang, Jun Chen, Chen Zhao, Hongchun Wu (2018). Accuracy and analysis of the iteratively coupling 2D/3D method for the three-dimensional transport calculations.DOI
Zhitao Xu, Hongchun Wu, Youqi Zheng, Mingtao He (2018). Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis. Volume 9: Student Paper Competition.DOI
M. Q. Awan, Liang-Zhi Cao, Hongchun Wu, Chuan-Qi Zhao (2018). Neutronic Study of Burnable Poison Materials and Their Alternative configurations in FCM loaded PWR Fuel Assembly.DOI
Tengfei Zhang, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li (2018). Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method.DOI
Yunzhao Li, Zhi-Peng Li, Hongchun Wu, Youqi Zheng (2018). Improved Variational Nodal Method Based on Symmetry Group Theory.DOI
Yijun Zhang, Liang-Zhi Cao, Zhou-Yu Liu, Hongchun Wu (2018). Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis. Annals of Nuclear Energy.DOI
Sheng-Cheng Zhou, W. Yang, Tongkyu Park, Hongchun Wu (2018). Fuel cycle analysis of molten salt reactors based on coupled neutronics and thermal-hydraulics calculations.DOI
Jun Chen, Zhou-Yu Liu, Chen Zhao, Qing-Ming He, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu (2018). A new high-fidelity neutronics code NECP-X.DOI
Xia-Nan Du, Liang-Zhi Cao, Youqi Zheng, Hongchun Wu (2018). A hybrid method to generate few-group cross sections for fast reactor analysis.DOI
Zhuo Li, Liang-Zhi Cao, Hongchun Wu, W. Shen, Yong Liu, Chenghui Wan (2018). Sensitivity and uncertainty analysis for the PWR online power-distribution monitoring with NECP-ONION system. Annals of Nuclear Energy.DOI
Tengfei Zhang, E. Lewis, Micheal A. Smith, W. Yang, Yongping Wang, Hongchun Wu (2018). Acceleration of within group iteration for pin-by-pin calculations.DOI
Li Jikui, Liang-Zhi Cao, Tiejun Zu, Hongchun Wu (2018). Resonance self-shielding treatment and analysis of resonance integral tables for Fully Ceramic Micro-encapsulated fuels with the Embedded Self-Shielding Method.DOI
Sheng-Cheng Zhou, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2018). Unstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations. Annals of Nuclear Energy.DOI
Qian Zhang, Qiang Zhao, Zhi-Jian Zhang, Liang Liang, W. Yang, Hongchun Wu, Liang-Zhi Cao (2018). Improvements of the Embedded Self-Shielding Method with Pseudo-Resonant Isotope Model on the Multifuel Lattice System. Nuclear science and engineering.DOI
Qing-Ming He, Liang-Zhi Cao, Hongchun Wu, B. Forget, Kord Smith (2018). Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method.DOI
Yunzhao Li, Bin Zhang, Qing-Ming He, Dongyong Wang, Hongchun Wu, Liang-Zhi Cao, W. Shen (2018). Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice. Nuclear Engineering and Design.DOI
Qian Zhang, Qiang Zhao, W. Yang, Hongchun Wu (2018). Modeling of Resonance-Interference Effect in Depleted Fuel Compositions by Pseudo Resonant Isotopes.DOI
Bo Wang, Zhou-Yu Liu, Jun Chen, Chen Zhao, Liang-Zhi Cao, Hongchun Wu (2018). A modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method. Progress in nuclear energy (New series).DOI
Xia-Nan Du, Youqi Zheng, Liang-Zhi Cao, Hongchun Wu (2018). Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system. Annals of Nuclear Energy.DOI
Qian Zhang, Qiang Zhao, Zhi-Jian Zhang, Liang Liang, Liang-Zhi Cao, Hongchun Wu (2018). Investigation on the heterogeneous resonance integral in the embedded self-shielding method. Annals of Nuclear Energy.DOI
M. Q. Awan, Liang-Zhi Cao, Hongchun Wu, W. Shen, Zhifeng Li (2018). Neutronic design study of a small modular IPWR loaded with accident tolerant-fully ceramic micro-encapsulated (AT-FCM) fuel. Nuclear Engineering and Design.DOI
Qian Zhang, Rongling Jiang, Qiang Zhao, Liang-Zhi Cao, Hongchun Wu (2018). Accurate resonance absorption calculation for fuel pins with non-uniform intra-pellet temperature profile based on ultra-fine-group slowing-down calculations. Annals of Nuclear Energy.DOI
Tengfei Zhang, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li (2018). An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation. Nuclear Engineering and Design.DOI
Wen Yang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao, Sicheng Wang (2018). Acceleration of the exponential function expansion nodal SP3 method by multi-group GMRES algorithm for PWR pin-by-pin calculation. Annals of Nuclear Energy.DOI
Liang-Zhi Cao, Kun Zhuang, Youqi Zheng, Tianliang Hu, Hongchun Wu (2018). Transient analysis for liquid‐fuel molten salt reactor based on MOREL2.0 code.DOI
Sheng-Cheng Zhou, Liang-Zhi Cao, Hongchun Wu (2018). Preliminary Design of a Small Transportable Liquid Chloride Salt Cooled Fast Reactor.
Sheng-Cheng Zhou, Renzong Chen, Yiqiong Shao, Liang-Zhi Cao, B. Bai, Hongchun Wu (2018). Conceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply. International Journal of Energy Research.DOI
Wen Yang, Hongchun Wu, Yunzhao Li, Jiewei Yang, Liang-Zhi Cao (2018). Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core. Nuclear Engineering and Design.DOI
Hongchun Wu, Qi Zheng, Yunzhao Li (2018). Monte Carlo Resonance Calculation for the Method of Characteristics.
Zhou-Yu Liu, Qing-Ming He, Xingjian Wen, Tiejun Zu, Li Cao, Hongchun Wu (2018). Improvement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X.DOI
Ji-Kui Li, Tiejun Zu, Liang-Zhi Cao, Hongchun Wu, Qing-Ming He (2018). Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory.DOI
Chen Zhao, Zhou-Yu Liu, Liang Liang, Jun Chen, Liang-Zhi Cao, Hongchun Wu (2018). Improved leakage splitting method for the 2D/1D transport calculation.DOI
Zhou-Yu Liu, Jun Chen, Liang-Zhi Cao, Chen Zhao, Qing-Ming He, Hongchun Wu (2018). Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC.DOI
Liang Liang, Zhou-Yu Liu, Hongchun Wu, Sheng Wang, Qian Zhang, Qiang Zhao (2018). Development and Application of a 2D/1D Fusion Code With Leakage Reconstruction Method. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory.DOI
Longfei Xu, Liang-Zhi Cao, Youqi Zheng, Hongchun Wu (2018). Hybrid MPI-communication for the multi-angular S N parallel sweep on 3-D regular grids. Annals of Nuclear Energy.DOI
Tiejun Zu, Fan Xia, Hongchun Wu (2018). An improved fitting method for subgroup parameters based on the heterogeneous cells. Journal of Nuclear Science and Technology.DOI
Yongping Wang, Hongchun Wu, Yunzhao Li (2017). Comparison of two three-dimensional heterogeneous variational nodal methods for PWR control rod cusping effect and pin-by-pin calculation.DOI
Xia-Nan Du, Liang-Zhi Cao, Youqi Zheng, Hongchun Wu (2017). Developments of the sodium fast reactor analysis code SARAX: methods and verification.
Tengfei Zhang, E. Lewis, M. Smith, W.-S. Yang, Hongchun Wu (2017). A Variational Nodal Approach to 2D/1D Pin Resolved Neutron Transport for Pressurized Water Reactors.DOI
Zhitao Xu, Hongchun Wu, Yunzhao Li, Youqi Zheng (2017). Improved discrete nodal transport method for treating void regions.DOI
Zhi-Peng Li, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao (2017). Block-diagonalization of the variational nodal response matrix using the symmetry group theory. Journal of Computational Physics.DOI
Tianliang Hu, Hongchun Wu, Liang-Zhi Cao, Zhifeng Li (2017). Finite volume method based neutronics solvers for steady and transient-state analysis of nuclear reactors.DOI
Youqi Zheng, Mingtao He, Liang-Zhi Cao, Hongchun Wu, Xunzhao Li, Sheng-Cheng Zhou (2017). Reactor core transient analysis of an innovative high‐level nuclear waste transmuter with metal fuel.DOI
Youqi Zheng, Xunzhao Li, Hongchun Wu (2017). Effect of high-energy neutron source on predicting the proton beam current in the ADS design.DOI
Tianliang Hu, Liang-Zhi Cao, Hongchun Wu, Kun Zhuang (2017). Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, W. Shen (2017). Uncertainty analysis for the assembly and core simulation of BEAVRS at the HZP conditions.DOI
Liang Liang, Zhou-Yu Liu, Youqi Zheng, Liang-Zhi Cao, Hongchun Wu (2017). Leakage reconstruction method for 2D/1D fusion transport calculations.DOI
Tengfei Zhang, Yongping Wang, E. Lewis, Micheal A. Smith, W. Yang, Hongchun Wu (2017). A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors.DOI
Zhuo Li, Liang-Zhi Cao, Hongchun Wu, W. Shen (2017). Sensitivity analysis for the weighting factor in the least-square method for the PWR on-line power-distribution monitoring.DOI
Yunzhao Li, Bin Zhang, Hongchun Wu, W. Shen (2017). Heterogeneous neutron-leakage model for PWR pin-by-pin calculation.DOI
Mingtao He, Youqi Zheng, Hongchun Wu, Zhuo Li, Xia-Nan Du (2017). Assessment of transient characteristics of fast reactors and influences of minor actinides using neutron transport method.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu (2017). Sensitivity and uncertainty analysis for eigenvalue and few-group constants of reactor-physics calculations.DOI
Tianliang Hu, Liang-Zhi Cao, Hongchun Wu, Xia-Nan Du, Mingtao He (2017). Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, W. Shen (2017). Total sensitivity and uncertainty analysis for LWR pin-cells with improved UNICORN code.DOI
Zhuo Li, Liang-Zhi Cao, Hongchun Wu, Yunzhao Li, Zhou-Yu Liu, W. Shen, Wen Yang (2017). Development and validation of a PWR on-line power-distribution monitoring system NECP-ONION.DOI
Bin Zhang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao, Wei Shen (2017). Evaluation of Pin-Cell Homogenization Techniques for PWR Pin-by-Pin Calculation.DOI
Hongchun Wu, Qian Zhang, Tiejun Zu, Qing-Ming He, W. Shen (2017). The Pseudo-Resonant-Isotope-Model for Predicting the Resonance-Interference Effect in the Self-Shielding Calculation.
Kun Zhuang, Youqi Zheng, Liang-Zhi Cao, Tianliang Hu, Hongchun Wu (2017). Improvements and validation of the transient analysis code MOREL for molten salt reactors.DOI
Li Jikui, Liang-Zhi Cao, Tiejun Zu, Hongchun Wu, Qing-Ming He (2017). Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method.DOI
M. Q. Awan, Liang-Zhi Cao, Hongchun Wu (2017). Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu (2017). Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations.DOI
Longfei Xu, Liang-Zhi Cao, Youqi Zheng, Hongchun Wu (2017). Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry.DOI
Zhou-Yu Liu, Hongchun Wu, Liang-Zhi Cao (2017). Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD.DOI
Kai Huang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao (2017). Depletion system compression method with treatment of decay heat.DOI
Youqi Zheng, Hongchun Wu, Xia-Nan Du, Yun-Long Xiao, Mingtao He (2017). Improvement and verification of the fast reactor neutronics code NECP-SARAX.DOI
Tianliang Hu, Liang-Zhi Cao, Hongchun Wu (2017). A coupled neutronics and thermal-hydraulics modeling approach to the steady-state and dynamic behavior of MSRs.
Zhifeng Li, Liang-Zhi Cao, Hongchun Wu (2017). The impacts of random effect and scattering effects on the neutronics analysis of the PB-FHR.DOI
Yongping Wang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao, W. Shen (2017). Investigation on generalized Variational Nodal Methods for heterogeneous nodes.DOI
Yunzhao Li, Kai Huang, Hongchun Wu, Liang-Zhi Cao (2017). A Depletion System Compression Method Based on Quantitative Significance Analysis.DOI
Jun Chen, Liang-Zhi Cao, Zhou-Yu Liu, Hongchun Wu, Yijun Zhang (2017). Preliminary Verification of the High-Fidelity Neutronics and Thermal-Hydraulics Coupling System NECP-X/SUBSC.DOI
M. Q. Awan, Liang-Zhi Cao, Hongchun Wu (2017). Neutronic design and evaluation of a PWR fuel assembly with accident tolerant-Fully Ceramic Micro-Encapsulated (AT-FCM) fuel.DOI
Bin Zhang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao (2017). Analysis of Pressurized Water Reactor Pin-by-pin Homogenization.
Youqi Zheng, Yun-Long Xiao, Hongchun Wu (2017). Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, W. Shen (2017). Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly.DOI
Tengfei Zhang, Yongping Wang, E. Lewis, M. Smith, W.-S. Yang, Hongchun Wu (2017). Assessment of 2 D-Transport / 1 D-Diffusion Approximations in a Pin Resolved Variational Nodal Method for PWR Calculations.
Baolin Liu, Liang-Zhi Cao, Hongchun Wu, Xianbao Yuan, Kunpeng Wang (2016). Pre-conceptual core design of a small modular fast reactor cooled by supercritical CO2.DOI
Zhifeng Li, Liang-Zhi Cao, Hongchun Wu, Qing-Ming He, W. Shen (2016). On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor.DOI
Zhifeng Li, Hongchun Wu, Chenghui Wan, Tianliang Hu (2016). The Fast Three-Dimensional Space-Time Neutron Kinetic Model for Cartesian Geometry and Cylindrical Geometry.DOI
Tiejun Zu, Qian Zhang, Hongchun Wu, Liang-Zhi Cao, Qing-Ming He, W. Yang (2016). Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation.DOI
Liang-Zhi Cao, Zhi-Peng Li, Hongchun Wu, Yunzhao Li (2016). Improved variable-transformation algorithm for the hexagonal Variational Nodal Method.
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu, W. Shen (2016). Propagation of Nuclear Data Uncertainties for PWR Burnup Calculation.DOI
Yunzhao Li, Qing-Ming He, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu (2016). Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method.DOI
Kai Huang, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li, W. Shen (2016). Improvements to the Transmutation Trajectory Analysis of depletion evaluation.DOI
Yong Liu, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu, Qing-Ming He (2016). Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation.DOI
Yun-Long Xiao, Hongchun Wu, Youqi Zheng, Kunpeng Wang (2016). Neutronics studies on the feasibility of developing fast breeder reactor with flexible breeding ratio.DOI
Zhuo Li, Hongchun Wu, Liang-Zhi Cao, Chao Tian, Dingyong Chen (2016). On-line monitoring analysis of BEAVRS benchmark using NECP-ONION.
Chuan-Qi Zhao, Kunpeng Wang, Liang-Zhi Cao, Hongchun Wu, Youqi Zheng (2016). Coupled Neutronics and Thermal–Hydraulics Analysis of Annular Fuel Assembly for SCWR.DOI
Kai Huang, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao (2016). GENERALIZED DEPLETION CHAIN SIMPLIFICATION BASED ON SIG- NIFICANCE ANALYSIS.
Tiejun Zu, Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, W. Shen (2016). Total Uncertainty Analysis for PWR Assembly Based on the Statistical Sampling Method.DOI
Liang-Zhi Cao, Boning Liang, Hongchun Wu, Yunzhao Li (2016). Variational Nodal Method fission-source iteration acceleration using the partitioned-matrix technique.
Zhifeng Li, Liang-Zhi Cao, Hongchun Wu, Qing-Ming He (2016). The impacts of thermal neutron scattering effect and resonance elastic scattering effect on FHRs.DOI
Qing-Ming He, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu (2016). Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method.DOI
Hongchun Wu, Yunzhao Li, Bin Zhang, Zhitao Xu, Youqi Zheng (2016). NECP-RIVER: A 3-D nodal SN code for small critical facilities.
Zhifeng Li, Liang-Zhi Cao, Hongchun Wu, Chenghui Wan, Tianliang Hu (2016). Effects of Applying the Implicit Particle Fuel Model for Pebble-Bed Reactors.DOI
Tengfei Zhang, Elmer E. Lewis, Micheal A. Smith, Wu Yang, Hongchun Wu (2016). Variational nodal 2D/1D transport/diffusion solutions of the C5G7 benchmark problems. Transactions of the American Nuclear Society.
Tiejun Zu, Chao Yang, Liang-Zhi Cao, Hongchun Wu (2016). Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells.DOI
Qing-Ming He, Hongchun Wu, Yunzhao Li, Liang-Zhi Cao, Tiejun Zu (2016). Neutron Up-Scattering Effect in Refined Energy Group Structure.DOI
Jun Chen, Liang-Zhi Cao, Chuan-Qi Zhao, Hongchun Wu, Zhou-Yu Liu (2016). Development and Validation of Subchannel Code SUBSC.DOI
Shengnan Gao, Hongchun Wu, Yunzhao Li (2015). Comparison of cross-section models for functionalization and history effect.
Longfei Xu, Liang-Zhi Cao, Hongchun Wu, Youqi Zheng (2015). Three-Dimensional Discrete Ordinate Transport Code Based on KBA Method.
Qing-Ming He, Liang-Zhi Cao, Hongchun Wu (2015). The Improved Subgroup Method Considering Resonance Elastic Scattering Effect and Resonance Interference Effect.
Tiejun Zu, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao (2015). Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycle strategies.DOI
Xianbao Yuan, Liang-Zhi Cao, Hongchun Wu (2015). Pre-conceptual study of small modular PbBi-cooled nitride fuel reactor core characteristics.DOI
Yunzhao Li, E. Lewis, Micheal A. Smith, Hongchun Wu, Liang-Zhi Cao (2015). Preconditioned Multigroup GMRES Algorithms for the Variational Nodal Method.DOI
Liang-Zhi Cao, Yongping Wang, Hongchun Wu, Yunzhao Li (2015). Heterogeneous Variational Nodal Methods forEliminating the Control Rod Cusping Effect.
Kun Zhuang, Liang-Zhi Cao, Youqi Zheng, Hongchun Wu (2015). Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design.DOI
Zhou-Yu Liu, B. Kochunas, B. Collins, T. Downar, Yun-Lin Xu, Hongchun Wu (2015). Model and analysis of performance for the method of characteristics direction probabilities with boundary averaging.DOI
Zhuo Li, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Yunzhao Li, Kunpeng Wang (2015). ICONE23-1692 3D PWR POWER DISTRIBUTION ON-LINE MONITORING BASED ON HARMONICS EXPANSION.DOI
Chenghui Wan, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu, W. Shen (2015). Code development for eigenvalue total sensitivity analysis and total uncertainty analysis.DOI
Zhou-Yu Liu, B. Collins, B. Kochunas, T. Downar, Yun-Lin Xu, Hongchun Wu (2015). Theory and analysis of accuracy for the method of characteristics direction probabilities with boundary averaging.DOI
Xunzhao Li, Sheng-Cheng Zhou, Youqi Zheng, Kunpeng Wang, Hongchun Wu (2015). Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale.DOI
Yong Liu, Liang-Zhi Cao, Hongchun Wu, Tiejun Zu, W. Shen (2015). Eigenvalue implicit sensitivity and uncertainty analysis with the subgroup resonance-calculation method.DOI
Mingtao He, Hongchun Wu, Youqi Zheng, Kunpeng Wang, Xunzhao Li, Sheng-Cheng Zhou (2015). Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method.DOI
Qian Zhang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2015). An Improved Resonance Self-Shielding Calculation Method Based on Equivalence Theory.DOI
Tiejun Zu, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao (2014). Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor.DOI
Zhou-Yu Liu, Hongchun Wu, B. Kochunas, B. Collins, Yun-Lin Xu, T. Downar (2014). Method of characteristics direction probabilities and its accuracy and performance models.DOI
Ammar Ahmad, Liang-Zhi Cao, Hongchun Wu, Chuan-Qi Zhao (2014). Conceptual design of pressure-tube super critical water reactor with inverted geometry.DOI
Baolin Liu, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao, Xianbao Yuan (2014). Preliminary Core Design of the Long Life S-CO2 Cooled Fast Reactor With 300WMth.DOI
Ammar Ahmad, Liang-Zhi Cao, Hongchun Wu (2014). Coupled analysis and improvements for Canadian-SCWR core design.DOI
Sheng-Cheng Zhou, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Kai Huang, Mingtao He, Xunzhao Li (2014). LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors. Nuclear Engineering and Design.DOI
Chuan-Qi Zhao, Liang-Zhi Cao, Hongchun Wu, Youqi Zheng (2014). Pre-conceptual core design of SCWR with annular fuel rods.DOI
Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao, Yunzhao Li (2014). Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors.DOI
Yongping Wang, Hongchun Wu, Yunzhao Li (2014). Heterogeneous variational nodal method with continuous cross section distribution in space.
Zheng Zheng, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Hongbo Zhang (2014). A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation. Annals of Nuclear Energy.DOI
Lei He, Hongchun Wu, Liang-Zhi Cao, Yunzhao Li (2014). Improvements of the subgroup resonance calculation code SUGAR.DOI
Mingtao He, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Sheng-Cheng Zhou (2014). Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh.DOI
Yuxiong Cheng, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Three-Dimensional Inverse Transport Solver Based on Compressive Sensing Technique.DOI
Kai Huang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Study on Improvement of Analytic Depletion Calculation Method.DOI
Kun Liu, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Changhui Wang (2013). A code development for LLFP transmutation analysis based on the whole pin-wise calculation in PWRs.DOI
Kun Liu, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Optimization Study on LLFPs Transmutation in PWRs.DOI
Kun Liu, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Studies on LLFP transmutation in a pressurized water reactor.DOI
Liang Liang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation.DOI
Chuan-Qi Zhao, Liang-Zhi Cao, Hongchun Wu, Jue Yang, Yong Zhang (2013). Conceptual design of a supercritical water reactor with double-row-rod assembly.DOI
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao (2013). Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equation. Nuclear Engineering and Design.DOI
Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao, Yunzhao Li (2013). A 3D transport-based core analysis code for research reactors with unstructured geometry.DOI
Guangchun Zhang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Yunzhao Li, Zhou-Yu Liu (2013). Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method.DOI
Xunzhao Li, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). A Neutronics Concept Design of Lead-Bismuth Cooled Accelerator-Driven System for Minor Actinide Transmutation.DOI
Yunzhao Li, Hongchun Wu, Liang-Zhi Cao (2013). Unstructured Triangular Nodal-SP3 Method Based on an Exponential Function Expansion.DOI
Qian Zhang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2013). Spatially Dependent Resonance Cross Sections in a Fuel Plate.DOI
Chao Yang, Liang-Zhi Cao, Hongchun Wu, Youqi Zheng, Tiejun Zu (2013). Neutronics analysis of minor actinides transmutation in a fusion-driven subcritical system.DOI
Zhou-Yu Liu, B. Kochunas, B. Collins, T. Downar, Hongchun Wu (2013). The method of modular characteristic direction probabilities in MPACT.
Kunpeng Wang, A. Rineiski, W. Maschek, Hongchun Wu, Liang-Zhi Cao (2013). Neutron transport model based on the transmission probability method.DOI
Xinli Gao, Tiejun Zu, W. Tian, S. Qiu, G. Su, Hongchun Wu (2013). Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor.DOI
Tiejun Zu, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao, Chao Yang (2013). NAPTH: Neutronics analysis code system for the fusion-fission hybrid reactor with pressure tube type blanket.DOI
Hongchun Wu, Tiejun Zu, S. Qiu, Xinli Gao, Youqi Zheng, Liang-Zhi Cao, W. Tian (2013). A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production.DOI
Lei He, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Hongbo Zhang (2012). Research on the Subgroup Method and 2D Arbitrary Geometry Resonance Calculation Code.DOI
Youqi Zheng, Hongchun Wu, Tiejun Zu, Chao Yang, Liang-Zhi Cao (2012). The neutronics studies of fusion fission hybrid power reactor.DOI
Tiejun Zu, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao (2012). Neutronics Performance of a Fusion-Fission Hybrid Reactor With Pressure Tube Assemblies.DOI
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao (2012). Application of the wavelet expansion method in spatial-angular discretization of the neutron transport equation.DOI
Kun Liu, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng, Changhui Wang (2012). Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs.DOI
Youqi Zheng, Tiejun Zu, Hongchun Wu, Liang-Zhi Cao, Chao Yang (2012). The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets.DOI
Xinli Gao, Tiejun Zu, Hongchun Wu, S. Qiu, G. Su, W. Tian (2012). Thermal-Hydraulics Design of Water-Cooled Pressure Tube Blanket for a Fusion Driven Subcritical Reactor.DOI
Guangchun Zhang, Hongchun Wu, Liang-Zhi Cao, Youqi Zheng (2012). Calculations of the Dual Functional Lithium Lead-Test Blanket Module for ITER With Three-Dimensional Deterministic Method.DOI
Youqi Zheng, Hongchun Wu, Liangzhi Cao, Shizhuang Jia (2012). Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle. Science and Technology of Nuclear Installations.DOI
Yunzhao Li, Hongchun Wu, Liang-Zhi Cao (2011). A POLYGONAL NODAL-SP3 METHOD FOR WHOLE CORE PIN-BY-PIN NEUTRONICS CALCULATION.
Liang-Zhi Cao, Hongchun Wu, Qingjie Liu, Qichang Chen (2011). ARBITRARY GEOMETRY RESONANCE CALCULATION USING SUBGROUP METHOD AND METHOD OF CHARACTERISTICS.
Hongbo Zhang, Hongchun Wu, Liang-Zhi Cao (2011). An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methods.DOI
Zhou-Yu Liu, Hongchun Wu, Liang-Zhi Cao, Qichang Chen, Yunzhao Li (2011). A new three-dimensional method of characteristics for the neutron transport calculation.DOI
Changhui Wang, Hongchun Wu, Liang-Zhi Cao, Ping Yang (2011). On-line reconstruction of in-core power distribution by harmonics expansion method.DOI
Ping Yang, Liang-Zhi Cao, Hongchun Wu, Changhui Wang (2011). Core design study on CANDU-SCWR with 3D neutronics/thermal-hydraulics coupling.DOI
Qingjie Liu, Hongchun Wu, Liang-Zhi Cao (2010). Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel.DOI
Weiyan Yang, Hongchun Wu, Liang-Zhi Cao (2010). Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method.DOI
Z. Liu, Hongchun Wu, Liang-Zhi Cao, Qingjie Liu (2010). The Consistency of WIMS-D Library and ACE Format Library.DOI
Hongbo Zhang, Hongchun Wu, Liang-Zhi Cao, Xing-Guang Sun (2010). Angular Multigrid Acceleration Method and Lyusternik-Wagner Extrapolation Acceleration Technique for Numerical Calculation of Neutron Transport Equation.
Kunpeng Wang, Hongchun Wu, Liang-Zhi Cao, Changhui Wang (2010). Analytic Basis Function Expansion Nodal Method for Neutron Diffusion Equations in Triangular Geometry.DOI
Weiyan Yang, Hongchun Wu, Youqi Zheng, Liang-Zhi Cao (2010). Application of wavelets scaling function expansion method in resonance self-shielding calculation.DOI
Tiejun Zu, Hongchun Wu, Liang-Zhi Cao, Qingjie Liu, Weiyan Yang (2010). Wavelets Scaling Function Expansion Resonance Self-Shielding Calculation Based on the DDPM.DOI
Zhou-Yu Liu, Hongchun Wu, Liang-Zhi Cao, Qichang Chen, Yunzhao Li (2010). Direct 3D MOC for Whole-Core Transport Calculation.DOI
Hongchun Wu, Guo-Ming Liu, Liang-Zhi Cao, Qichang Chen (2010). Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry.DOI
Qingjie Liu, Hongchun Wu, Liang-Zhi Cao (2010). Solution of the multiplying binary stochastic media based on L–P equation in 1D spherical geometry.DOI
Yulong Qin, Hongchun Wu, Liang-Zhi Cao, Qingjie Liu (2010). Resonance Calculation Code UFOP Based on the Hyper-Fine Group Neutron Resonance Calculation Method.DOI
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao (2010). Neutron Transport Solution Using the Daubechies’ Wavelets in the Spatial Discretization.DOI
Yunzhao Li, Hongchun Wu, Liang-Zhi Cao, Qichang Chen, Hao-Liang Lu, Si-Tao Peng, Xiaoming Song, Dong Yao (2010). FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor.DOI
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao, N. Cho (2010). Daubechies’ Wavelet Method for Angular Solution of the Neutron Transport Equation.DOI
Hongbo Zhang, Hongchun Wu, Liang-Zhi Cao (2010). Acceleration Technique Using Krylov Subspace Methods for 2D Arbitrary Geometry Characteristics Solver.DOI
Lei He, Hongchun Wu, Liang-Zhi Cao, Qingjie Liu, Z. Liu (2010). Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor.DOI
Ping Yang, Liang-Zhi Cao, Hongchun Wu, Changhui Wang (2010). Conceptual Design of CANDU-SCWR With Thermal-Hydraulics Coupling.DOI
Changhui Wang, Hongchun Wu, Liang-Zhi Cao (2010). On Line Monitoring the Reactor Power Distribution Based on the Data Library of the Eigenfunctions.DOI
Shizhuang Jia, Liangzhi Cao, Hongchun Wu (2010). Economic Analysis on MOX Fuels. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Hongchun Wu (2009). Parallel S_n Algorithm for 2-D Transport Equations Based on Unstructured Grid.
Hai-tao Ju, Hongchun Wu (2009). Additive angular dependent rebalance acceleration arithmetic for neutron transport equation in optically thick diffusive region.
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao (2009). An improved three-dimensional wavelet-based method for solving the first-order Boltzmann transport equation.DOI
Weiyan Yang, Hongchun Wu, Liang-Zhi Cao (2009). Application of Wavelet Scaling Function Expansion to Continuous-Energy Resonance Calculation.DOI
Changhui Wang, Hongchun Wu, Liang-Zhi Cao (2009). On-Line Monitoring the In-Core Flux Distribution Using the Eigenfunctions.DOI
O. Zheng, Hongchun Wu, Liang-Zhi Cao (2009). Nuclear Engineering and Design.
Youqi Zheng, Hongchun Wu, Liang-Zhi Cao (2009). Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel lattice.DOI
Qichang Chen, Hongchun Wu, Liang-Zhi Cao (2008). The Method of Characteristics for Arbitrary Geometry Based on the Customization of Autocad.DOI
Liang-Zhi Cao, Hongchun Wu, Youqi Zheng (2008). Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization.DOI
Guo-Ming Liu, Hongchun Wu, Liang-Zhi Cao (2008). Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometry.DOI
Hai-tao Ju, Hongchun Wu, Dong Yao, Chunyu Xian (2008). Discrete ordinates method for three-dimensional neutron transport equation based on unstructured-meshes.DOI
Guo-Ming Liu, Hongchun Wu (2008). Transmission Probability Method Based on Triangular-Z Mesh for Solving Neutron Transport Equation in Three-Dimensional Geometry.DOI
Qichang Chen, Hongchun Wu, Liang-Zhi Cao (2008). Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD.DOI
Qing Ye, Hongchun Wu (2008). Spherical Harmonics Method for Neutron Transport Equation in Two-Dimensional Cylindrical (R-Z) Geometry. Hedongli gongcheng.
Wei-bing Huang, Hongchun Wu (2008). Resonance self-shielding calculation for complicated fuel assembly. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
Hai-tao Ju, Hongchun Wu, Y. K. Zhou, Liang-Zhi Cao, Dong Yao, Chunyu Xian (2007). A least-squares finite-element Sn method for solving first-order neutron transport equation.DOI
Hao-Liang Lu, Hongchun Wu, Liang-Zhi Cao, Y. K. Zhou, Chunyu Xian, Dong Yao (2007). Two-dimensional nodal transport method for triangular geometry.DOI
Hai-tao Ju, Hongchun Wu, Dong Yao, Chunyu Xian (2007). Least-squares finite-element SN method for solving three-dimensional transport equation.DOI
Hongchun Wu, Ping-Ping Liu, Yong-Qiang Zhou, Liang-Zhi Cao (2007). Transmission probability method based on triangle meshes for solving the unstructured geometry neutron transport problem.DOI
Liang-Zhi Cao, Hongchun Wu (2007). A spherical harmonics—Finite element discretization of the self-adjoint angular flux neutron transport equation.DOI
Hao-Liang Lu, Hongchun Wu (2007). A nodal SN transport method for three-dimensional triangular-z geometry.DOI
Hongchun Wu, Liu Pingping, Zhou Yongqiang, Cao Liangzhi (2006). Transmission probability method based on triangle meshes for solving unstructured geometry neutron transport problem. Nuclear Engineering and Design.DOI
T. Takeda, D. Sato, Toshihisa Yamamoto, Hongchun Wu (2000). Minor Actinides Incineration by Loading Moderated Targets in Fast Reactor. Journal of Nuclear Science and Technology.DOI
Zhu Xuehua, Xie Zhongsheng, Hongchun Wu (1994). Application of the diffusion synthetic acceleration technique to the discrete nodal transport method. Hedongli gongcheng.
Zhu Xuehua, Xie Zhongsheng, Hongchun Wu (1994). A discrete nodal method for two-dimensional neutron transport numerical calculation in cylindrical geometry. Chinese Journal of Nuclear Science and Engineering.