曹良志

期刊论文

1. 黄展鹏，曹良志，贺清明，吴宏春（2026）. GPU事件并行算法在NECP-MCX的初步实现. 《强激光与粒子束》.
2. 杜思芃，李云召，周克峰，张航萁，邵睿智，曹良志（2026）. 基于SPND响应电流精准计算的压水堆堆芯功率分布验证实验分析. 《核技术》.
3. 汪曙岚，曹良志，贺清明，郑琪，吴宏春（2026）. 光子输运中原子级联弛豫与轫致光子对中低能辐射能谱的影响. 《核技术》.
4. 郑岩，贺清明，舒瀚林，曹良志（2026）. 共轭驱动的贝叶斯-蒙特卡罗耦合辐射场重建方法研究. 《核动力工程》.DOI
5. 申靖文，曹良志，贺清明，尹苗，曹启祥（2026）. 基于图神经网络的蒙特卡罗CSG模型重用方法及应用研究. 《核技术》.
6. 陈佳达，刘宙宇，黄紫皇，曹良志，吴宏春（2026）. 基于NECP-X的控制棒尖齿效应修正方法研究. 《核动力工程》.
7. 彭贺宇，郑琪，汪威，贺清明，曹良志，祖铁军，王永平（2026）. 基于蒙特卡罗方法的BNCT头部肿瘤案例的剂量学研究. 《强激光与粒子束》.
8. 吴宏春，曹良志，郑友琦，李云召，祖铁军，刘宙宇，贺清明，万承辉，王永平，杜夏楠（2026）. 先进核反应堆高保真中子学计算方法与应用研究进展. 《科学通报》.
9. Muhammad Kamran Butt, S. Nasir, Muhammad Ahmad, Muhammad Bin Humayun, Ahmer Riaz, Chenghui Wan, Liangzhi Cao (2026). Appropriate selection of objective functions with constraints for successive multicycle optimization of the HPR1000 reactor core using deep learning enhanced multi-objective genetic algorithm. Annals of Nuclear Energy.DOI
10. Liying Zhang, De-Feng Yang, Xiao-Xiao Wang, Aijun Mi, Guo-Ming Liu, Liangzhi Cao, Jin-Kai Liu, Shi-Yu Liu, Peng-Pei Xie, Qing-Min Zhang (2026). Development and validation of CFDT code for fission product release analysis of spherical and cylindrical TRISO-based fuel element in HTGRs. Annals of Nuclear Energy.DOI
11. Junwei Qin, Yuancheng Zhou, Yunzhao Li, Liangzhi Cao, Hongchun Wu (2026). A deep generative model and Bayesian optimization scheme for PWR first-cycle loading-pattern optimization. Nuclear Engineering and Technology.DOI
12. Shihao Shao, Zhouyu Liu, Jiawang Liu, Ziyuan Liu, Ziyuan Liu, Ziyuan Liu, Ke Wang, Zhu Qiyu, Liangzhi Cao, Hongchun Wu (2026). A neutron transport calculation method based on Monte Carlo–Deep learning–interface current coupling and its validation in assembly problems. Annals of Nuclear Energy.DOI
13. Junwei Qin, Yunzhao Li, Liangzhi Cao, Hongchun Wu (2026). Central-Difference method based on consistent Half-Node linear approximation for the neutron diffusion equation. Annals of Nuclear Energy.DOI
14. Songzhe Wang, Yunzhao Li, Yunzhao Li, Yilin Liang, Yisong Li, Yisong Li, Hongchun Wu, Liangzhi Cao (2026). Precise location of failed fuel assembly in operating PWR-core based on fine nuclide evolution and deep metric learning. Annals of Nuclear Energy.DOI
15. Xuran Yang, Liangzhi Cao, Zheng Qi, Qingming He, Hongchun Wu, Qiang Yang, Baoxin Yuan (2026). Direct and IKS Monte Carlo Methods in Flight-Based and Collision-Based Frameworks for Frequency-Domain Neutron Noise Calculation. Nuclear Science and Engineering.DOI
16. Junwei Qin, Yunzhao Li, Yisong Li, Yisong Li, Yisong Li, Liangzhi Cao, Hongchun Wu (2026). Anisotropic diffusion coefficient for pin-by-pin two-step method. Nuclear Engineering and Technology.DOI
17. Tiejun Zu, Zerun Lu, ZG Liu, Zhewen Xiao, Liangzhi Cao, Hongchun Wu (2026). Evaluation of neutron-induced independent fission yields for 37 fissioning systems. Journal of Nuclear Science and Technology.DOI
18. Yunzhao Li, Yunzhao Li, Yuwen Fan, Songzhe Wang, Hongchun Wu, Liangzhi Cao (2026). A nodal P1 two-step method for PWR-core neutronics calculation. Annals of Nuclear Energy.DOI
19. Jingwen Shen, Liangzhi Cao, Qingming He, Jiandi Guo, Yuetong Luo, Kaihui Lei, Miao Yin (2026). BRepNet-based BRep-to-CSG conversion for complex geometry modelling in Monte Carlo particle transport calculation. Annals of Nuclear Energy.DOI
20. Shuaizheng Li, Zhouyu Liu, Rui Zhang, Ning Xu, Liangzhi Cao, Hongchun Wu (2026). The neutron-photon two-way coupling transport calculation based on the 2D/1D method. Annals of Nuclear Energy.DOI
21. Tiejun Zu, Rui Zhang, Hongchun Wu, Liangzhi Cao (2026). Development of a module to generate delayed photon data in ACE format within nuclear data processing code NECP-Atlas. Annals of Nuclear Energy.DOI
22. Bing Zhao, Zheng Qi, Qiong He, Liangzhi Cao, Tiejun Zu, Yongping Wang (2026). Research on hybrid methods for variance reduction in Monte Carlo dose calculation of BNCT. Nuclear Engineering and Technology.DOI
23. Xuran Yang, Qi Zheng, Liangzhi Cao, Qingming He, Hongchun Wu (2026). Study on Monte Carlo iterative K-source (IKS) method for frequency domain neutron noise calculation. Annals of Nuclear Energy.DOI
24. Runze Liu, Zhouyu Liu, Zhouyu Liu, Xiaoqing Liang, Liangzhi Cao, Hongchun Wu (2026). Development and improvement of the quadratic depletion method. Annals of Nuclear Energy.DOI
25. Sipeng Du, Yunzhao Li, Hangqi Zhang, Ruizhi Shao, Liangzhi Cao (2026). Corrigendum to "Verification of PWR-Core power distribution based on precisely calculated SPND response currents" <[ Nuclear Engineering and Design 448 (2026) 114726]>. Nuclear Engineering and Design.DOI
26. Xiang Li, Zhouyu Liu, W.T. Chen, Liangzhi Cao, Hongchun Wu (2026). Calculation and analysis of self-shielded cross sections for the high-fidelity neutronics calculation of fast reactors. Annals of Nuclear Energy.DOI
27. Hangqi Zhang, Yunzhao Li, Liangzhi Cao (2026). Response Current Delay-Effect Elimination for SPND in PWR-Core. Springer proceedings in physics.DOI
28. Meng Zhang, Chunfeng Shi, Yaping Zhang, Liangzhi Cao, Donghui Wang (2026). Development and Application of Ex-Vessel Neutron Dosimetry System on Tianwan VVER-1000 Unit 2. Springer proceedings in physics.DOI
29. Zhongming Fu, Hao Wang, Jun Qi, Tao Cui, Guojian Li, Liangzhi Cao, Yaping Zhang (2026). Analysis of the Impact on Iron Dosimeter Missing in a Reactor Vessel Surveillance Capsule. Springer proceedings in physics.DOI
30. Xiaoyu Wen, Yunzhao Li, Haopo Liu, Liangzhi Cao (2026). Continuous-Energy MOC for Neutron-Transport Calculation. Springer proceedings in physics.DOI
31. 吴宏春，郑友琦，曹良志，杜夏楠，王学松，祖铁军，刘宙宇，贺清明，陈荣华，葛莉，杨睿，高鑫钊，王事喜，阿热爱（2025）. 液态金属快堆分析方法与自主化软件的研发与验证. 《原子能科学技术》.
32. 黄义涵，祖铁军，刘铮鸣，曹良志，吴宏春（2025）. 基于评价核数据抽样的不确定度量化及同化方法研究. 《原子能科学技术》.
33. 卢泽润，祖铁军，曹良志，吴宏春（2025）. 基于实验数据与理论模型的链产额数据产生方法研究. 《原子能科学技术》.
34. 刘铮鸣，祖铁军，黄义涵，吴宏春，曹良志（2025）. 56Fe核数据对屏蔽计算不确定度的影响研究. 《原子能科学技术》.
35. 袁安民，吴宏春，李云召，朱彤，于宾跃，方思聪，曲鸣，曹良志（2025）. 基于Bamboo-Lattice的双类型弥散颗粒燃料计算方法. 《原子能科学技术》.
36. 张奥林，王永平，吴宇轩，徐东宇，曹良志，吴宏春，罗勇（2025）. 基于节块展开法的球床式高温气冷堆堆芯导热计算方法. 《原子能科学技术》.
37. 秦浚玮，李云召，曹良志，吴宏春（2025）. 基于P 1 理论的栅元尺度压水堆堆芯物理分析. 《中国核科学技术进展报告（第九卷）中国核学会2025年学术年会论文集 第3册》.DOI
38. 曹璐，刘宙宇，王立鹏，姜夺玉，胡田亮，郭树伟，黄海龙，曹良志（2025）. 多环燃料共振计算方法研究及验证. 《强激光与粒子束》.
39. 吴宇轩，王永平，秦帅，曹良志，吴宏春，罗勇（2025）. 球床式高温气冷堆物理热工计算程序NECP-Panda中子学计算模块研制. 《核技术》.
40. 邵睿智，曹良志，李云召，陈磊（2025）. 基于钒SPND瞬发电流的最佳指示功率估计方法. 《核动力工程》.DOI
41. 曹璐，李达，刘宙宇，王立鹏，姜夺玉，胡田亮，曹良志（2025）. NECP-X程序中环形燃料共振计算方法及其在西安脉冲堆中的应用. 《现代应用物理》.
42. 刘家旺，刘宙宇，邵世豪，曹良志，吴宏春（2025）. 基于深度学习的压水堆瞬态物理场预测方法研究. 《现代应用物理》.
43. 曹璐，李达，王立鹏，胡田亮，姜夺玉，李华琪，陈立新，刘宙宇，曹良志（2025）. 基于深度学习的共振计算方法研究及其在堆芯分析中的应用. 《现代应用物理》.
44. S. Raza, Yongping Wang, Liangzhi Cao, Yuxuan Wu (2025). Parametric study of the computational model on fuel and fission products characteristics analysis of HTR-PM equilibrium core. Annals of Nuclear Energy.DOI
45. S. Raza, M. Hashim, Liangzhi Cao, Xia-Nan Du, Longwen Jiang (2025). Investigation on radioisotopes evolution in the fuel of Lead-Bismuth eutectic (LBE) cooled SPARK-NC core. Annals of Nuclear Energy.DOI
46. Liangzhi Cao (2025). Editorial: A new chapter for Annals of Nuclear Energy. Annals of Nuclear Energy.DOI
47. Izat Khan, Liangzhi Cao, S. Raza, Muhammad Kamran Butt (2025). Development of a novel neutron-gamma spectrum-based composite material optimization process for the shielding design of a space reactor. Nuclear Engineering and Design.DOI
48. S. Raza, Liangzhi Cao, Yongping Wang, Yuxuan Wu, Haoyong Li, M. Hashim (2025). Development of radionuclide inventory and fission product release calculation model and its application to HTR-PM. Annals of Nuclear Energy.DOI
49. Sipeng Du, Yunzhao Li, Hangqi Zhang, Ruizhi Shao, Liangzhi Cao (2025). Verification of PWR-Core power distribution based on precisely calculated SPND response currents. Nuclear Engineering and Design.DOI
50. Yilin Liang, Yunzhao Li, Yunzhao Li, Yisong Li, Yisong Li, Liangzhi Cao (2025). A mechanism and data dual-driven digital-twin design for PWR-core. Annals of Nuclear Energy.DOI
51. Xiaoying Li, Xiaoying Li, Yunzhao Li, Ruizhi Shao, Ning Xu, Liangzhi Cao, Tiejun Zu (2025). Multigroup cross-section library generation for deterministic electron-transport calculation. Annals of Nuclear Energy.DOI
52. Miao Zhao, Xianan Du, Youqi Zheng, Mingyu Wu, Rui Yang, Li Xu, Liangzhi Cao, Hongchun Wu (2025). Feasibility study on the core design of high-flux fast neutron research reactors. Nuclear Engineering and Technology.DOI
53. Heyu Peng, Qi Zheng, Qingming He, Tiejun Zu, Yongping Wang, Liangzhi Cao, Hong‐Chun Wu, Sheng Wang, Xiaozhi Zhang (2025). Acceleration study of a BNCT dose calculation engine based on NECP-MCX. Journal of Nuclear Science and Technology.DOI
54. Yang Liu, Lei Xue, Hangyu Shi, Zhiyi Ni, Liangzhi Cao, Xiaoping Ouyang (2025). Application of the half-boundary method to solving the neutron transport equation in 1D cylindrical coordinate. Progress in Nuclear Energy.DOI
55. Yang Liu, Zhiyi Ni, Hangyu Shi, Lei Xue, Liangzhi Cao, Xiaoping Ouyang (2025). Solving the two-dimensional neutron transport equation in the right-angle coordinate system by the half-boundary method. Annals of Nuclear Energy.DOI
56. Xiang Li, Zhouyu Liu, Siyu Yi, Zhao Tian, Shunhong Wang, Longwen Jiang, Liangzhi Cao, Hongchun Wu (2025). Group condensation method for the transport calculation of PWR with dispersed-particle fuel. Annals of Nuclear Energy.DOI
57. Dongyu Xu, Yongping Wang, Yuxuan Wu, Aolin Zhang, Liangzhi Cao, Hongchun Wu, Yong Luo (2025). Development and verification of thermal hydraulic model of the pebble bed high-temperature gas-cooled reactor core analysis code NECP-Panda. Annals of Nuclear Energy.DOI
58. Haopo Liu, Yunzhao Li, Xiaoyu Wen, Hongchun Wu, Liangzhi Cao (2025). A deterministic continuous-energy neutron transport calculation method based on hybrid basis function expansion. Annals of Nuclear Energy.DOI
59. Jinlong Huang, Liangzhi Cao, Qingming He, Mohan Wang, Chenghui Wan, Hongchun Wu (2025). Improved XGPT method for uncertainty quantification of reactor physics analysis with continuous-energy covariance data. Annals of Nuclear Energy.DOI
60. Hanlin Shu, Liangzhi Cao, Qingming He, Tao Dai (2025). An Automatic Load-Balancing Domain Decomposition Scheme for Monte Carlo Simulation on Large-Scale Unstructured-Mesh Problems. Nuclear Science and Engineering.DOI
61. Rui Zhang, Tiejun Zu, Jiandi Guo, Qingming He, Hongchun Wu, Liangzhi Cao (2025). Implementation of inverse transform sampling method for photon transport in Monte Carlo code and nuclear data library preparation by NECP-Atlas. Annals of Nuclear Energy.DOI
62. Rui Nie, Jiong Guo, Ma Qian, Xi Chen, Yulin Zhang, Wenting Jia, Yu Wang, Feng Xie, Jianzhu Cao, Yaoquan Zhou, Emmanuel Boafo, Qingming He, Liangzhi Cao (2025). Ar-41 source term investigation in HTR-PM: Theory, calculations, and experiments. Nuclear Engineering and Design.DOI
63. Hongchun Wu, Shuaizheng Li, Jun Chen, Guangwen Bi, Zhouyu Liu, Sifan Zhang, Xinyu Zhou, Liangzhi Cao (2025). A neutron transport calculation approach via the coupling of 2D/1D and 3D SN nodal methods. Annals of Nuclear Energy.DOI
64. Tiejun Zu, Yutu Ma, Hongchun Wu, Liangzhi Cao, Ya'Nan Tang (2025). Evaluation of thermal neutron scattering law for light and heavy water based on molecular dynamics simulations. Annals of Nuclear Energy.DOI
65. Runze Liu, Fan Li, Zhouyu Liu, Changyou Zhao, Xianghui Lu, Liangzhi Cao, Hongchun Wu (2025). Simulation of the fuel-assembly bowing in PWR based on the coupling of pin-resolved neutronics and pin-by-pin subchannel. Annals of Nuclear Energy.DOI
66. Zhanpeng Huang, Yunki Jo, Qingming He, Liangzhi Cao, Hongchun Wu, Deokjung Lee (2025). Performance Improvement of Weight Window Method by Incorporating DXTRAN. Nuclear Science and Engineering.DOI
67. Muhammad Kamran Butt, Chenghui Wan, Luo Wei, Izat Khan, Liangzhi Cao (2025). Method research on equilibrium cycle reloading pattern optimization for the HPR1000 reactor core using deep learning-enhanced multi-objective genetic algorithm. Annals of Nuclear Energy.DOI
68. Hanlin Shu, Liangzhi Cao, Qingming He (2025). Efficient Monte Carlo Particle Transport Simulation for Hybrid Geometries Using an Intrusive Approach. Nuclear Technology.DOI
69. Zhouyu Liu, Jiawang Liu, Shihao Shao, Liangzhi Cao, Hongchun Wu (2025). Deep learning-based prediction of transient power variation in pressurized water reactors. Progress in Nuclear Energy.DOI
70. Yunzhao Li, Songzhe Wang, Yuancheng Zhou, Senhan Yang, Ruizhi Shao, Liangzhi Cao, Tian Chen, Miao Yu, Zeng Shao, Guoming Liu (2025). Bamboo-SFuel: A nuclide composition evaluation code for PWR spent fuel in NECP-Bamboo. Nuclear Engineering and Design.DOI
71. Junwei Qin, Yunzhao Li, Liangzhi Cao (2025). Development of Bamboo-Transient2.0 for three-dimensional PWR-core pin-by-pin Transient analysis. Nuclear Engineering and Technology.DOI
72. Jiandi Guo, Zhouyu Liu, Qingming He, Danbin Huang, Liangzhi Cao, Hongchun Wu (2025). A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework. Nuclear Engineering and Technology.DOI
73. Yilin Liang, Yunzhao Li, Yunzhao Li, Yuancheng Zhou, Yisong Li, Yisong Li, Shilong Zhou, Hengrui Zhang, Weiguo Wang, Yuxiang Ou, Songzhe Wang, Junwei Qin, Liangzhi Cao, Hongchun Wu (2025). Validation of the PWR-core physics analysis software NECP-Bamboo based on NPP measurements. Progress in Nuclear Energy.DOI
74. 刘浩泼，李云召，吴宏春，曹良志（2024）. 非共振能区连续能量确定论中子输运计算方法研究. 《原子能科学技术》.
75. 黄义涵，祖铁军，曹良志，吴宏春（2024）. NECP-Atlas中协方差数据制作模块的开发与验证. 《核技术》.
76. 周遥，曹良志，刘宙宇，王立鹏，邵睿智，贺清明，吴宏春（2024）. 基于电流组分分离模型的钒SPND伽玛效应计算方法和实验验证. 《核技术》.
77. 王伟国，李云召，秦浚玮，曹良志（2024）. 基于中子电报方程的均匀裸堆瞬态中子输运问题解析解研究. 《核动力工程》.
78. 徐宁，祖铁军，曹良志，吴宏春（2024）. 基于分子干涉函数的光子-原子相干散射截面计算方法研究. 《原子能科学技术》.
79. 黄金龙，曹良志，贺清明，秦帅，吴宏春（2024）. 函数展开计数在CLUTCH方法中的初步应用. 《原子能科学技术》.
80. 邵世豪，刘宙宇，许晓北，宗育凡，曹良志，吴宏春（2024）. 基于MOOSE平台液态金属冷却快堆燃料性能分析程序开发. 《原子能科学技术》.
81. 吴宏春，贺清明，曹良志，黄展鹏，郑琪，李捷，秦帅，黄金龙，包彦（2024）. 深穿透跨尺度辐射场分析软件NECP-MCX研发及应用. 《原子能科学技术》.
82. 吴宏春，杨红义，郑友琦，曹良志，杜夏楠，杨勇，刘一哲，胡赟（2024）. 快中子反应堆堆芯物理分析方法的研究现状与发展建议. 《原子能科学技术》.
83. 邹晓阳，万承辉，曹良志（2024）. 堆芯多物理耦合的不确定性分析方法研究及应用. 《哈尔滨工程大学学报》.
84. Junwei Qin, Yunzhao Li, Liangzhi Cao, Hongchun Wu (2024). P1 generalized equivalence theory for PWR-core pin-by-pin neutronics calculation. Annals of Nuclear Energy.DOI
85. Sicheng Wang, Yunzhao Li, Junwei Qin, Yilin Liang, Yuancheng Zhou, Liangzhi Cao, Hongchun Wu (2024). Verifications and applications of NECP-Bamboo2.0 for PWR whole-core multi-cycle pin-by-pin simulation. Progress in Nuclear Energy.DOI
86. Tiejun Zu, Chengyao Wu, Hao Feng, Yutu Ma, Liangzhi Cao, Hongchun Wu, Yongqiang Tang (2024). Implementation of one-phonon correction method to calculate inelastic scattering law data in nuclear data processing code NECP-Atlas. Progress in Nuclear Energy.DOI
87. Muhammad Kamran Butt, Liangzhi Cao, Chenghui Wan, Kaihui Lei, Izat Khan (2024). Integrating the deep learning and multi-objective genetic algorithm to the reloading pattern optimization of HPR1000 reactor core. Nuclear Engineering and Design.DOI
88. Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo (2024). Corrigendum to “NECP-Panda: A neutronics and thermal-hydraulic analysis code for pebble-bed high temperature gas-cooled reactor” [Ann. Nucl. Energy (2024) 110814]. Annals of Nuclear Energy.DOI
89. Muhammad Hashim, Liangzhi Cao, Hongchun Wu, Xiaoqian Jia, Jinshun Wang, Sohail Ahmad Raza, Haoyu Fan (2024). Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients. Annals of Nuclear Energy.DOI
90. Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo (2024). Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor.DOI
91. Wen Yin, Tiejun Zu, Liangzhi Cao (2024). Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation.DOI
92. Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo (2024). NECP-panda: A neutronics and thermal-hydraulic analysis code for pebble-bed high temperature gas-cooled reactor. Annals of Nuclear Energy.DOI
93. Sohail Ahmad Raza, Liangzhi Cao, Yongping Wang, Qingming He, Muhammad Hashim (2024). Automated modelling approach for neutronic analysis of high temperature gas-cooled pebble bed reactors. Nuclear Engineering and Design.DOI
94. Hongchun Wu, Shuai Qin, Yunzhao Li, Jinkang Shi, Qingming He, Liangzhi Cao (2024). Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX. Nuclear Engineering and Technology.DOI
95. Tiejun Zu, Yihan Huang, Liangzhi Cao, Hongchun Wu (2024). Development and Verification of Sampling Code NECP-SOUL for Evaluated Nuclear Data Files in ENDF-6 Format. Nuclear Science and Engineering.DOI
96. Sicheng Wang, Yunzhao Li, Liangzhi Cao, Lei Chen, Hongchun Wu (2024). Anderson acceleration for PWR whole-core pin-by-pin Nu-TH coupling calculation in NECP-Bamboo2.0. Nuclear Engineering and Design.DOI
97. Hongchun Wu, Ning Xu, Tiejun Zu, Rui Zhang, Liangzhi Cao (2024). Capability for processing photonuclear data in nuclear data processing code NECP-Atlas. Annals of Nuclear Energy.DOI
98. Siyu Yi, Zhouyu Liu, Kunpeng Wang, Wei Shen, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2024). Resonance Calculation of FCM Fuel Based on the Global-Local Method. Nuclear Science and Engineering.DOI
99. Qingming He, Zhanpeng Huang, Liangzhi Cao, Hongchun Wu (2024). The methods of CADIS-NEE and CADIS-DXTRAN in NECP-MCX and their applications. Nuclear Engineering and Technology.DOI
100. Hanlin Shu, Liangzhi Cao, Qingming He, Qi Zheng, Tao Dai (2024). Study on Unstructured Mesh–Based Monte Carlo/Deterministic Coupled Particle Transport Calculation Method. Nuclear Science and Engineering.DOI
101. Xiaoyang Zou, Chenghui Wan, Liangzhi Cao (2024). Evaluation of sampling methods for nuclear data uncertainty quantification. Annals of Nuclear Energy.DOI
102. Sicheng Wang, Yonghee Kim, Yunzhao Li, Liangzhi Cao (2024). An embedded coupling design and development of NECP-Bamboo2.0 and START for PWR whole-core pin-by-pin analysis. Annals of Nuclear Energy.DOI
103. Qingming He, Qi Zheng, Jie Li, Zhanpeng Huang, Jinlong Huang, Shuai Qin, Hanlin Shu, Heyu Peng, Xuran Yang, Jingwen Shen, Jiandi Guo, Liangzhi Cao, Hongchun Wu (2024). Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0. EPJ Nuclear Sciences & Technologies.DOI
104. Jinlong Huang, Liangzhi Cao, Qingming He, Hongchun Wu (2024). Development of sensitivity calculation capability of Legendre moments of scattering angular distributions in NECP-MCX. EPJ Web of Conferences.DOI
105. Jiandi Guo, Zhouyu Liu, Qingming He, Danbin Huang, Zi-Wei Lin, Liangzhi Cao, Hongchun Wu (2024). Count Rate Analysis of the Source-range Detector for M310. EPJ Web of Conferences.DOI
106. Zhanpeng Huang, Liangzhi Cao, Qingming He, Hongchun Wu (2024). The CADIS-DXTRAN method in NECP-MCX for Radiation Shielding Simulations. EPJ Web of Conferences.DOI
107. 舒瀚林，曹良志，贺清明，戴涛，黄展鹏（2023）. 基于非结构网格的蒙特卡罗重要性抽样方法研究. 《核动力工程》.
108. 杨寿海，曹南凤，刘杰，熊军，祖铁军，徐宁，曹良志（2023）. MATXS格式多群核截面数据加工平台研制与CMGC1.0数据库验证. 《核科学与工程》.
109. 周遥，曹良志，王立鹏，张好雨，吴宏春（2023）. 三代压水堆堆芯中子探测器响应计算方法验证和实验研究. 《中国核科学技术进展报告（第八卷）中国核学会2023年学术年会论文集 第6册 辐射研究与应用 核技术工业应用 原子能农学 核医学 核技术经济与管理现代化 核电子学与核探测技术 辐照效应》.DOI
110. 杨森涵，李云召，邵睿智，陈添，曹良志，邵增，刘国明（2023）. 基于NECP-Bamboo程序的商用压水堆乏燃料组件核素成分分析. 《原子能科学技术》.
111. 邵睿智，曹良志，李云召，司峰伟，杜超（2023）. 钒SPND中瞬发γ电流对堆芯测量的影响分析. 《原子能科学技术》.
112. 李帆，刘宙宇，王习宁，曹良志，吴宏春（2023）. 燃料组件弯曲的高保真全堆芯中子学计算方法及应用. 《核动力工程》.
113. 王立鹏，张信一，姜夺玉，胡田亮，曹良志，吴宏春，曹璐（2023）. 基于确定论的ZrHx中H热中子散射数据评价. 《核动力工程》.
114. 秦浚玮，李云召，王昆鹏，吴宏春，曹良志（2023）. 压水堆三维全堆芯Pin-by-pin瞬态分析. 《核动力工程》.
115. 李云召，秦浚玮，夏凡，吴宏春，曹良志（2023）. 含强吸收体堆芯的各向异性SP3两步法计算研究. 《核动力工程》.
116. 秦帅，李云召，贺清明，白家赫，董文昌，曹良志，吴宏春（2023）. 基于NECP-MCX的组件均匀化计算及其在HPR1000中的应用. 《核动力工程》.
117. 黄展鹏，曹良志，贺清明，吴宏春（2023）. 针对大空间伽马射线输运模拟的CADIS-环探测器耦合方法. 《原子能科学技术》.
118. 秦帅，李云召，贺清明，曹良志，吴宏春（2023）. 基于中子均方位移守恒的平均散射角余弦计算. 《哈尔滨工程大学学报》.
119. Shihao Shao, Zhouyu Liu, Xiaobei Xu, Yufan Zong, Liangzhi Cao, Hongchun Wu (2023). Development of Fuel Performance Analysis Code for Liquid Metal Coole Fast Reactor Based on MOOSE Platform. Springer proceedings in physics.DOI
120. Kaihui Lei, Hongchun Wu, Zhouyu Liu, Yi Qian Cao, Guoming Liu, Xiaojing Li, Qingming He, Liangzhi Cao (2023). SN-MscaleDNN: A coupling approach for rapid shielding-scheme evaluation of micro gas-cooled reactor in the large design-parameter space. Annals of Nuclear Energy.DOI
121. Yao Zhou, Liangzhi Cao, Liangzhi Cao, Lipeng Wang, Zhouyu Liu, Linyue Liu, Xinjie Sui, L. Cao, L. Cao, Chunlei Su, Hongchun Wu (2023). Monte Carlo analyses and experimental investigation of the vanadium self-powered neutron detector in 60Co source and research pulsed reactor. Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment.DOI
122. Miao Zhao, Tiejun Zu, Pingting Jiang, Yiyuan Gao, Chenghui Wan, Liangzhi Cao, Hongchun Wu (2023). Impact of the resonance elastic scattering on reactor-core physics calculation results based on the deterministic method. Annals of Nuclear Energy.DOI
123. Sicheng Wang, Yunzhao Li, Liangzhi Cao, Hongchun Wu (2023). A cross-section correction model for history effect treatment in pin-by-pin code NECP-Bamboo2.0. Annals of Nuclear Energy.DOI
124. Ruizhi Shao, Liangzhi Cao, Yunzhao Li, Yao Zhou (2023). Simulation and Analysis of the Space Charge Effect in a Self-Powered Neutron Detector. IEEE Transactions on Nuclear Science.DOI
125. Qingming He, Tao Dai, Hanlin Shu, Liangzhi Cao, Hongchun Wu, Qixiang Cao, Shen Qu (2023). Preliminary neutronics/thermal-hydraulics design and analyses of the helium-cooled mixed bed breeder blanket for CFETR under 1.5 GW fusion power. Fusion Engineering and Design.DOI
126. Shuai Qin, Yunzhao Li, Qingming He, Liangzhi Cao, Yongping Wang, Yuxuan Wu, Hongchun Wu (2023). Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX. Nuclear Engineering and Technology.DOI
127. Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao (2023). Double heterogeneity effect analysis for plate fuel with dispersed particles. Annals of Nuclear Energy.DOI
128. Jinlong Huang, Liangzhi Cao, Qingming He, Chenghui Wan, Hongchun Wu (2023). Improvement of the CLUTCH method for sensitivity analysis of k-eigenvalue to continuous-energy nuclear data in NECP-MCX. Progress in Nuclear Energy.DOI
129. Shuaizheng Li, Zhouyu Liu, Junji Chen, Minwan Zhang, Liangzhi Cao, Hongchun Wu (2023). Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF. Annals of Nuclear Energy.DOI
130. Bingbing Ji, Zhiping Chen, Jia Liu, Xiaoyang Zou, Chenghui Wan, Liangzhi Cao (2023). A new sampling scheme combining maximum entropy and moment matching techniques for reactor physics uncertainty quantification. Annals of Nuclear Energy.DOI
131. Wen Yin, A.Yu. Konobeyev, D. Leichtle, Liangzhi Cao (2023). General displacement function for displacement damage cross-section calculation. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.DOI
132. Xinyu Zhou, Zhouyu Liu, Liangzhi Cao, Hongchun Wu (2023). The improved odCMFD method based on the 2D/1D Fourier analysis. Annals of Nuclear Energy.DOI
133. Zerun Lu, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2023). Generation and analysis of independent fission yield covariances based on GEF model code. EPJ Web of Conferences.DOI
134. Hanlin Shu, Liangzhi Cao, Qingming He, Tao Dai, Zhangpeng Huang, Hongchun Wu (2023). Study on Unstructured-Mesh-Based Importance Sampling Method of Monte Carlo Simulation. Springer proceedings in physics.DOI
135. Tiejun Zu, Alain Hébert, Liangzhi Cao, Hongchun Wu (2023). Implementation of the RESKR module in NJOY. EPJ Web of Conferences.DOI
136. Shuai Qin, Qingming He, Jiahe Bai, Wenchang Dong, Liangzhi Cao, Hongchun Wu (2023). Group Constants Generation Based on NECP-MCX Monte Carlo Code. Springer proceedings in physics.DOI
137. Yihan Huang, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2023). Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas. EPJ Web of Conferences.DOI
138. 王思成，曹良志，李云召，吴宏春，杨杰伟（2022）. 强非均匀Pin-by-pin历史效应处理技术研究. 《原子能科学技术》.
139. 祖铁军，徐宁，尹文，曹良志，吴宏春（2022）. 核数据处理软件NECP-Atlas中的光子相关数据计算方法研究. 《原子能科学技术》.
140. 舒文玉，曹良志（2022）. 基于CENDL-3.2的宽群屏蔽数据库开发与验证. 《原子能科学技术》.
141. 曹良志，邓力，杨波，刘宙宇，刘鹏，汤春桃，史敦福，陈荣华，田文喜，彭良辉，万承辉，张旻婉，毕光文，费敬然，许晓北，李帆（2022）. CAP1400数值反应堆系统关键技术研究及示范应用. 《原子能科学技术》.
142. 刘宙宇，许晓北，温兴坚，王博，曹璐，周欣宇，张旻婉，陈俊辑，王习宁，李帆，李帅铮，马升泽，邵世豪，曹良志，吴宏春（2022）. 确定论数值反应堆程序NECP-X的开发及应用. 《原子能科学技术》.
143. 邹晓阳，曹良志，刘宙宇，吴宏春（2022）. 基于统计抽样的压水堆燃料组件性能分析不确定度量化研究. 《原子能科学技术》.
144. 曹璐，刘宙宇，贺清明，曹良志（2022）. 基于等效几何理论的复杂几何燃料共振计算方法研究. 《原子能科学技术》.
145. 黄金龙，曹良志，贺清明，李捷，沈炜（2022）. 连续能量核数据敏感性分析及其在AP1000中的应用. 《原子能科学技术》.
146. 祖铁军，汤勇强，曹良志，吴宏春（2022）. 基于第一性原理的氢化锆热散射律计算分析. 《原子能科学技术》.
147. 戴涛，曹良志，贺清明，吴宏春（2022）. 中国聚变工程试验堆包层的核热耦合效应研究. 《原子能科学技术》.
148. 吴宏春，刘宙宇，周欣宇，曹良志（2022）. 数值反应堆的研究现状与发展建议. 《原子能科学技术》.
149. 温兴坚，田超，唐松乾，翟梓安，苗建新，曹良志，刘宙宇（2022）. 基于反应率预测的预估校正方法研究. 《核动力工程》.
150. 祖铁军，徐宁，曹良志，吴宏春（2022）. NECP-Atlas中屏蔽数据库制作模块的开发与验证. 《核动力工程》.
151. 张思凡，袁媛，刘宙宇，周欣宇，曹良志（2022）. 一种通过边界注量率耦合的MOC和SN二维耦合中子输运方法. 《核动力工程》.
152. 陈俊辑，刘宙宇，曹璐，曹良志（2022）. 六角形布置反应堆高保真物理计算方法研究与验证. 《核动力工程》.
153. 张丽莹，曹良志，王晓霞，高桂玲（2022）. 用于乏燃料组件上下端部活化源项分析的截面库研究. 《辐射防护》.
154. 杜夏楠，王永平，郑友琦，曹良志，张延师，闫雪松，杨磊（2022）. 基于确定论的ADANES堆芯稳态中子学分析及瞬态事故模拟研究. 《核技术》.
155. Jiaqi Hu, Zhaopeng Qiao, Lunhe Fan, Yongqiang Tang, Liangzhi Cao, Tiejun Zu, Qingming He, Zhifeng Li, Sheng Wang (2022). Calculation of thermal neutron scattering data of MgF2 and its effect on beam shaping assembly for BNCT. Nuclear Engineering and Technology.DOI
156. Qingming He, Jie Li, Hanlin Shu, Liangzhi Cao, Hongchun Wu, Wei Shen (2022). Particle-transport/depletion/activation/source-term coupling analysis for CFETR with NECP-MCX. Fusion Engineering and Design.DOI
157. Sicheng Wang, Liangzhi Cao, Yunzhao Li, Hongchun Wu (2022). An energy-group structure optimization from seven to four for PWR-core pin-by-pin calculation. Nuclear Engineering and Design.DOI
158. Wen Yin, A.Yu. Konobeyev, D. Leichtle, Liangzhi Cao (2022). Calculation of displacement damage cross-section for charged particles at energies up to 100 GeV. Journal of Nuclear Materials.DOI
159. Yao Zhou, Liangzhi Cao, Qingming He, Zhelin Feng, Heyu Peng (2022). A Coupled Deterministic and Monte-Carlo Method for Modeling and Simulation of Self-Powered Neutron Detector. IEEE Transactions on Nuclear Science.DOI
160. Qingming He, Chao Fang, Liangzhi Cao, Haoyu Zhang (2022). A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation. Nuclear Science and Engineering.DOI
161. Zhouyu Liu, Junji Chen, Shuaizheng Li, Hongchun Wu, Liangzhi Cao (2022). Development and verification of the hexagonal core simulation capability of the NECP-X code. Annals of Nuclear Energy.DOI
162. Ruizhi Shao, Liangzhi Cao, Yunzhao Li, Lin Guo, Jiewei Yang, Fengwei Si, Chao‐Hai Du, Chenghui Wan, Hongchun Wu (2022). Numerical simulation of Delayed-SPND response current in NECP-Bamboo. Annals of Nuclear Energy.DOI
163. Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shengzhi Yu, Qianglong Wang, Jinrong Qiu (2022). Analysis of Double Heterogeneous Effect Under Double Dispersion of Fuel and Burnable Poison Particles.DOI
164. Yao Zhou, Liangzhi Cao, Changyou Zhao, Zhifeng Li, Yuxiang Zhu (2022). Layout Optimization of Self-Powered Neutron Detector for HPR1000. Volume 15: Student Paper Competition.DOI
165. Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shenzhi Yu, Yi Liao, Jinrong Qiu (2022). Research on Modeling Method and Eigenvalue Calculation of Single Dispersion of Fuel Particles.DOI
166. Kang Li, Liangzhi Cao, Jianxin Miao, Haoyu Zhang, Tao Dai (2022). Neutronics Analysis of Fusion Blanket Based on the Spherical Harmonic Function and Finite Element Method. Volume 15: Student Paper Competition.DOI
167. Yaodong Sang, Bangjie Deng, Qingmin Zhang, Shiyu Liu, Ruizhi Shao, Zhuang Shao, Liangzhi Cao, Yunzhao Li (2022). A numerical method for quantitatively analyzing the space charge effect of Self-Powered Neutron Detector. Annals of Nuclear Energy.DOI
168. Yucui Gao, Liangzhi Cao, Wenlian Ye, Xuesong Yan, Liangwen Chen, Yaling Zhang, Lei Yang, Sheng Wang (2022). Neutronics design optimization of a small modular fast reactor based on response surface methodology. Nuclear Engineering and Design.DOI
169. Zerun Lu, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2022). Burnup chain compression method preserving neutronics, decay photon source term and decay heat calculation results. Annals of Nuclear Energy.DOI
170. Yihan Huang, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2022). Capability of processing the GNDS format evaluated nuclear data in NECP-Atlas for neutronics calculations. Progress in Nuclear Energy.DOI
171. Wenyu Shu, Liangzhi Cao (2022). Design and validation of a broad-group shielding library for fast reactors by using particle swarm optimization. Annals of Nuclear Energy.DOI
172. Wenyu Shu, Liangzhi Cao, Hongchun Wu (2022). Application of particle swarm optimization to the reconstruction of the energy group structure for shielding library. Annals of Nuclear Energy.DOI
173. Qingming He, Siyu Yi, Zhouyu Liu, Hongchun Wu, Liangzhi Cao (2022). A one-dimensional model for multi-group equivalence parameters in subgroup method. Annals of Nuclear Energy.DOI
174. Zhouyu Liu, Sifan Zhang, Xinyu Zhou, Liangzhi Cao (2022). A new coupling method based on MOC and the SN nodal method for the neutron transport calculations. Annals of Nuclear Energy.DOI
175. Cheng Zhang, Chenghui Wan, Liangzhi Cao, Yunzhao Li, Ning Xu, Hongchun Wu (2022). Method research and engineering validation of the improved homogenization for the heavy reflector in VVER. Annals of Nuclear Energy.DOI
176. Ning Xu, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2022). Development of the capability for multi-group shielding library generation in the nuclear data processing code NECP-Atlas. Annals of Nuclear Energy.DOI
177. Zhanpeng Huang, Liangzhi Cao, Qingming He, Hongchun Wu (2022). New variance reduction techniques for Monte-Carlo calculation based on first-collision source method. Journal of Nuclear Science and Technology.DOI
178. Xinyu Zhou, Zhouyu Liu, Liangzhi Cao, Hongchun Wu (2022). Convergence analysis for the CMFD accelerated 2D/1D neutron transport calculation method based on Fourier analysis. Annals of Nuclear Energy.DOI
179. Chao Fang, Liangzhi Cao, Hongchun Wu, Kang Li (2022). A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation. Nuclear Science and Engineering.DOI
180. Xiaoyang Zou, Liangzhi Cao, Zhuojie Sui, Zeyun Wu (2022). Uncertainty Analysis of TMI-1 Mini-Core Neutron Kinetics Case. Transactions of the American Nuclear Society.DOI
181. 包彦，贺清明，曹良志，吴宏春（2021）. 基于NECP-MCX的点核积分方法研究与程序研发. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第6册（计算物理分卷、核物理分卷、核聚变与等离子体物理分卷、辐射物理分卷、核工程力学分卷）》.DOI
182. 祖铁军，汤勇强，尹文，徐宁，曹良志，吴宏春（2021）. 核数据处理程序NECP-Atlas研发进展. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第6册（计算物理分卷、核物理分卷、核聚变与等离子体物理分卷、辐射物理分卷、核工程力学分卷）》.DOI
183. 曹良志，邹晓阳，刘宙宇，万承辉，吴宏春（2021）. 高保真数值核反应堆不确定度量化方法研究进展. 《核动力工程》.DOI
184. 万承辉，李云召，郑友琦，刘宙宇，祖铁军，曹良志，吴宏春，沈炜（2021）. 压水堆燃料管理软件Bamboo-C研发及工业确认. 《核动力工程》.DOI
185. 苗建新，曹良志，方超，贺清明，曹启祥，尹苗（2021）. 球谐函数有限元程序NECP-FISH的开发及其在聚变堆包层中子学分析中的应用. 《原子能科学技术》.
186. 王思成，曹良志，李云召，吴宏春（2021）. 适用于压水堆全堆芯Pin-by-pin计算的历史效应复合修正方法研究. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第6册（计算物理分卷、核物理分卷、核聚变与等离子体物理分卷、辐射物理分卷、核工程力学分卷）》.DOI
187. 许晓北，刘宙宇，曹良志，吴宏春（2021）. 基于数值反应堆多物理耦合的U 3 Si 2 燃料堆内性能研究. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
188. 雷铠灰，曹良志，万承辉，曹泓（2021）. 基于深度卷积神经网络的堆芯换料方案性能评价研究. 《原子能科学技术》.
189. 张旻婉，刘宙宇，王博，曹璐，赵晨，曹良志（2021）. 基于统一几何建模的高保真物理-热工耦合方法研究及其在SPERT实验堆堆芯的计算应用. 《核动力工程》.
190. 曹璐，刘宙宇，张旻婉，贺清明，温兴坚，曹良志，吉文浩（2021）. NECP-X程序中基于全局-局部耦合策略的非棒状几何燃料共振计算方法研究. 《核动力工程》.DOI
191. 郑琪，沈炜，贺清明，李捷，曹良志（2021）. 基于NECP-MCX的蒙特卡罗-确定论耦合及权窗网格粗化方法研究. 《核动力工程》.DOI
192. 邵睿智，曹良志，李云召，桑耀东，李雪松，郝腾飞，司峰伟，杜超，张清民，万承辉（2021）. AP1000堆芯运行过程中SPND响应电流模拟分析. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
193. 周原成，李云召，刘裕，杨杰伟，黄星，邵睿智，曹良志（2021）. NECP-Bamboo程序自动化建模功能设计与开发. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
194. 徐宁，祖铁军，曹良志，吴宏春（2021）. NECP-Atlas中屏蔽数据库制作方法. 《哈尔滨工程大学学报》.
195. 曹良志（2021）. 专辑出版前言. 《现代应用物理》.
196. 吴宏春，杨红义，曹良志，郑友琦，刘宙宇，刘一哲，杜夏楠，王永平，杨军，张熙司（2021）. 金属冷却快堆关键分析软件的现状与展望. 《现代应用物理》.
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311. 李云召，杨文，王思成，张斌，吴宏春，曹良志（2018）. 压水堆堆芯Pin-by-pin燃料管理计算程序NECP-Bamboo2.0的设计与验证. 《核动力工程》.
312. 徐嘉隆，祖铁军，曹良志，吴宏春（2018）. NECP-Atlas中共振弹性散射核处理模块的开发与验证. 《核动力工程》.
313. 张乾，赵强，梁亮，吴宏春，曹良志（2018）. 压水堆相邻燃料棒间的高阶共振干涉现象研究. 《核动力工程》.
314. 曹璐，刘宙宇，曹良志，贺清明，吴宏春，韩宇，毕光文，汤春桃（2018）. 基于NECP-X程序的三维复杂几何小型压水堆全堆芯一步法计算. 《核动力工程》.
315. 屈伸，曹良志，周生诚，刘汉刚（2018）. 热管式空间反应堆燃耗计算研究. 《核动力工程》.
316. 张滕飞，吴宏春，曹良志，李云召，熊进标，刘晓晶（2018）. 中子扩散三维非均匀变分节块法及平源加速方法研究. 《核动力工程》.
317. Chenghui Wan, Liang Qiao, Youqi Zheng, Liangzhi Cao, Hongchun Wu (2018). Validation of SARAX for the China Fast Reactor with the extrapolated experimental data. Annals of Nuclear Energy.DOI
318. Youqi Zheng, Liang Qiao, Chenghui Wan, Liangzhi Cao, Yong Liu (2018). Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size. Annals of Nuclear Energy.DOI
319. Fiaz Mahmood, Huasi Hu, Liangzhi Cao, Guichi Lu, Si Ni, Jiaqi Yuan (2018). Evaluation of activated corrosion products in primary coolant circuit of AP-1000 under grid frequency stability mode. Annals of Nuclear Energy.DOI
320. Wen Yin, Tiejun Zu, Qingming He, Liangzhi Cao (2018). Multi-group effective cross section calculation method for Fully Ceramic Micro-encapsulated fuel. Annals of Nuclear Energy.DOI
321. Jialong Xu, Tiejun Zu, Liangzhi Cao (2018). Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas. Progress in Nuclear Energy.DOI
322. Kun Zhuang, Xiaobin Tang, Liangzhi Cao (2018). Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC. Annals of Nuclear Energy.DOI
323. Tiejun Zu, Jialong Xu, Yongqiang Tang, Huchao Bi, Fei Zhao, Liangzhi Cao, Hongchun Wu (2018). NECP-Atlas: A new nuclear data processing code. Annals of Nuclear Energy.DOI
324. Kun Zhuang, Liangzhi Cao (2018). A study of the impact of mixed mode of fuel salt in plenum on steady-state performance of channel-type molten salt reactor. Annals of Nuclear Energy.DOI
325. Qian Zhang, Qiang Zhao, Zhijian Zhang, Liang Liang, Won Sik Yang, Hongchun Wu, Liangzhi Cao (2018). Improvements of the Embedded Self-Shielding Method with Pseudo-Resonant Isotope Model on the Multifuel Lattice System. Nuclear Science and Engineering.DOI
326. Tengfei Zhang, Hongchun Wu, Liangzhi 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
327. Xianan Du, Youqi Zheng, Liangzhi 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
328. Jikui Li, Tiejun Zu, Liangzhi Cao, Hongchun Wu, Qingming He (2018). Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods.DOI
329. Fiaz Mahmood, Huasi Hu, Liangzhi Cao (2018). Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000.DOI
330. Jialong Xu, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2018). Development and Verification of a New Nuclear Data Processing System NECP-Atlas.DOI
331. Qian Zhang, Qiang Zhao, Hongchun Wu, Liangzhi Cao, Zheng Zheng (2018). Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices.DOI
332. Chao Fang, Hongchun Wu, Liangzhi Cao, Yunzhao Li (2018). Fast Sub-Grid Scale Finite Element Method for the First Order Neutron Transport Equation.DOI
333. Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu, Chuanqi Zhao (2018). Neutronic Study of Burnable Poison Materials and Their Alternative Configurations in Fully Ceramic Microencapsulated Loaded Pressurized Water Reactor Fuel Assembly. Journal of Nuclear Engineering and Radiation Science.DOI
334. Wen Yang, Hongchun Wu, Yunzhao Li, Liangzhi 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
335. Wen Yang, Hongchun Wu, Yunzhao Li, Jiewei Yang, Liangzhi Cao (2018). Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core. Nuclear Engineering and Design.DOI
336. Yunzhao Li, Bin Zhang, Qingming He, Dongyong Wang, Hongchun Wu, Liangzhi Cao, Wei Shen (2018). Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice. Nuclear Engineering and Design.DOI
337. Qian Zhang, Qiang Zhao, Zhijian Zhang, Liang Liang, Liangzhi Cao, Hongchun Wu (2018). Investigation on the heterogeneous resonance integral in the embedded self-shielding method. Annals of Nuclear Energy.DOI
338. Qian Zhang, Rong Jiang, Qiang Zhao, Liangzhi 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
339. Shengcheng Zhou, Hongchun Wu, Liangzhi 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
340. Shengcheng Zhou, Renzong Chen, Yunhao Shao, Liangzhi Cao, Bofeng 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
341. Tiejun Zu, Jikui Li, Wen Yin, Liangzhi Cao (2018). Accurate resonance calculation method coupling simplified embedded self-shielding method and ultra-fine group method. Annals of Nuclear Energy.DOI
342. Bo Wang, Zhouyu Liu, Jun Chen, Chen Zhao, Liangzhi 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.DOI
343. M. Qasim Awan, Liangzhi Cao, Hongchun Wu, Wei 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
344. Yijun Zhang, Liangzhi Cao, Zhouyu 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
345. Xianan Du, Liangzhi Cao, Youqi Zheng, Hongchun Wu (2018). A hybrid method to generate few-group cross sections for fast reactor analysis. Journal of Nuclear Science and Technology.DOI
346. Jun Chen, Zhouyu Liu, Chen Zhao, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun Wu (2018). A new high-fidelity neutronics code NECP-X. Annals of Nuclear Energy.DOI
347. Longfei Xu, Liangzhi 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
348. Kun Zhuang, Liangzhi Cao (2018). Numerical analysis on the dynamic behaviors of a graphite-moderated molten salt reactor based on MOREL2.0 code. Annals of Nuclear Energy.DOI
349. Chen Zhao, Zhouyu Liu, Liang Liang, Jun Chen, Liangzhi Cao, Hongchun Wu (2018). Improved leakage splitting method for the 2D/1D transport calculation. Progress in Nuclear Energy.DOI
350. Fiaz Mahmood, Huasi Hu, Liangzhi Cao (2018). Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based power-maneuvering transients in AP-1000. Annals of Nuclear Energy.DOI
351. 李茁，吴宏春，曹良志，李云召，刘宙宇（2017）. 压水堆堆芯功率分布在线监测计算中的探测器失效诊断与处理方法. 《强激光与粒子束》.
352. 贺清明，曹良志，吴宏春，李云召（2017）. 能精确处理空间自屏效应的共振伪核素子群方法. 《强激光与粒子束》.
353. 杜夏楠，曹良志，郑友琦（2017）. 基于点截面的快堆组件均匀化参数计算方法. 《强激光与粒子束》.
354. 黄凯，吴宏春，李云召，曹良志（2017）. 基于定量重要性分析的燃耗链压缩方法. 《强激光与粒子束》.
355. 祖铁军，张乾，吴宏春，曹良志（2017）. 基于广义等价理论的高保真共振计算方法. 《强激光与粒子束》.
356. 胡田亮，曹良志，吴宏春，庄坤（2017）. 熔盐堆有效缓发中子份额βeff的计算及分析. 《核动力工程》.
357. 袁显宝，曹良志，吴宏春（2017）. 铅铋冷却氮化物燃料小型模块化快中子反应堆堆芯物理特性分析. 《核技术》.
358. 马云帆，吴宏春，曹良志（2017）. 压水堆嬗变长寿命裂变产物的弹棒事故安全性研究. 《原子能科学技术》.
359. 陈军，曹良志，赵传奇，叶鑫，刘宙宇，吴宏春（2017）. 子通道程序SUBSC的开发及稳态验证. 《原子能科学技术》.
360. 杜夏楠，曹良志，郑友琦（2017）. SARAX-FXS程序针对非均匀快堆堆芯计算中的改进及应用. 《原子能科学技术》.
361. 屈伸，曹良志，郑琪，刘汉刚，赵小林（2017）. 热管堆高温数据库的制作及堆芯初步物理计算. 《现代应用物理》.
362. Zhuo Li, Liangzhi Cao, Hongchun Wu, Wei Shen, Yong Liu, Chenghui Wan (2017). Sensitivity and uncertainty analysis for the PWR online power-distribution monitoring with NECP-ONION system. Annals of Nuclear Energy.DOI
363. Qingmin Zhang, Xinxin Liu, Bangjie Deng, Liangzhi Cao, Chuntao Tang (2017). Numerical optimization of Rhodium Self-Powered Neutron Detector. Annals of Nuclear Energy.DOI
364. Tengfei Zhang, Hongchun Wu, Liangzhi Cao, Yunzhao Li (2017). Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method. Annals of Nuclear Energy.DOI
365. Zhouyu Liu, Jun Chen, Liangzhi Cao, Chen Zhao, Qingming He, Hongchun Wu (2017). Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC. Progress in Nuclear Energy.DOI
366. Qingmin Zhang, Bangjie Deng, Xinxin Liu, Chengyuan Li, Yaodong Sang, Liangzhi Cao, Guangwen Bi, Chuntao Tang, Peng Zhang, Dayin Tong, Yang Li (2017). Deconvolution-based real-time neutron flux reconstruction for Self-Powered Neutron Detector. Nuclear Engineering and Design.DOI
367. Jikui Li, Liangzhi Cao, Tiejun Zu, Hongchun Wu (2017). Resonance self-shielding treatment and analysis of resonance integral tables for Fully Ceramic Micro-encapsulated fuels with the Embedded Self-Shielding Method. Annals of Nuclear Energy.DOI
368. Zhouyu Liu, Qingming He, Tiejun Zu, Liangzhi Cao, Hongchun Wu, Qian Zhang (2017). The pseudo-resonant-nuclide subgroup method based global–local self-shielding calculation scheme. Journal of Nuclear Science and Technology.DOI
369. Zhipeng Li, Hongchun Wu, Yunzhao Li, Liangzhi Cao (2017). Block-diagonalization of the variational nodal response matrix using the symmetry group theory. Journal of Computational Physics.DOI
370. Qingming He, Liangzhi Cao, Hongchun Wu, Benoit Forget, Kord S. Smith (2017). Predicting spatially dependent reaction rate for problem with nonuniform temperature distribution by subgroup method. Annals of Nuclear Energy.DOI
371. Tianliang Hu, Hongchun Wu, Liangzhi Cao, Zhifeng Li (2017). Finite volume method based neutronics solvers for steady and transient-state analysis of nuclear reactors. Energy Procedia.DOI
372. Chenghui Wan, Liangzhi Cao, Hongchun Wu (2017). Sensitivity and uncertainty analysis for eigenvalue and few-group constants of reactor-physics calculations. Energy Procedia.DOI
373. Jun Chen, Liangzhi Cao, Chuanqi Zhao, Zhouyu Liu (2017). Development of Subchannel Code SUBSC for high-fidelity multi-physics coupling application. Energy Procedia.DOI
374. Luca Capriotti, Liangzhi Cao, Gonzalo Jimenez (2017). Editorial. Energy Procedia.DOI
375. Liangzhi Cao, Kun Zhuang, Youqi Zheng, Tianliang Hu, Hongchun Wu (2017). Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code. International Journal of Energy Research.DOI
376. Zhuo Li, Liangzhi Cao, Hongchun Wu, Yunzhao Li, Zhouyu Liu, Wei Shen, Wen Yang (2017). Development and validation of a PWR on-line power-distribution monitoring system NECP-ONION. Nuclear Engineering and Design.DOI
377. Tianliang Hu, Liangzhi Cao, Hongchun Wu, Kun Zhuang (2017). Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors.DOI
378. Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu (2017). Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly.DOI
379. Jikui Li, Liangzhi Cao, Tiejun Zu, Hongchun Wu, Qingming He (2017). Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method.DOI
380. Jun Chen, Liangzhi Cao, Zhouyu Liu, Hongchun Wu, Yijun Zhang (2017). Preliminary Verification of the High-Fidelity Neutronics and Thermal-Hydraulics Coupling System NECP-X/SUBSC.DOI
381. Chenghui Wan, Liangzhi Cao, Hongchun Wu (2017). Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations.DOI
382. Zhuo Li, Liangzhi Cao, Hongchun Wu, Wei Shen (2017). Sensitivity analysis for the weighting factor in the least-square method for the PWR on-line power-distribution monitoring. Annals of Nuclear Energy.DOI
383. Zhouyu Liu, Hongchun Wu, Liangzhi Cao (2017). Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD. Annals of Nuclear Energy.DOI
384. Tianliang Hu, Liangzhi Cao, Hongchun Wu, Xianan Du, Mingtao He (2017). Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY. Annals of Nuclear Energy.DOI
385. Yunzhao Li, Kai Huang, Hongchun Wu, Liangzhi Cao (2017). A Depletion System Compression Method Based on Quantitative Significance Analysis. Nuclear Science and Engineering.DOI
386. Zhifeng Li, Liangzhi Cao, Hongchun Wu (2017). The impacts of random effect and scattering effects on the neutronics analysis of the PB-FHR. Annals of Nuclear Energy.DOI
387. Kun Zhuang, Youqi Zheng, Liangzhi Cao, Tianliang Hu, Hongchun Wu (2017). Improvements and validation of the transient analysis code MOREL for molten salt reactors. Journal of Nuclear Science and Technology.DOI
388. Liangzhi Cao, Yong Liu, Wei Shen, Qingming He (2017). Development of a hybrid method to improve the sensitivity and uncertainty analysis for homogenized few-group cross sections. Journal of Nuclear Science and Technology.DOI
389. Bin Zhang, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Wei Shen (2017). Evaluation of Pin-Cell Homogenization Techniques for PWR Pin-by-Pin Calculation. Nuclear Science and Engineering.DOI
390. Kai Huang, Hongchun Wu, Yunzhao Li, Liangzhi Cao (2017). Depletion system compression method with treatment of decay heat. Progress in Nuclear Energy.DOI
391. Huang Kai, Wu Hongchun, Yunzhao Li, Liangzhi Cao (2017). Depletion chain compression method via quantitative significance analysis. High Power Laser and Particle Beams.DOI
392. Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen (2017). Uncertainty analysis for the assembly and core simulation of BEAVRS at the HZP conditions. Nuclear Engineering and Design.DOI
393. Youqi Zheng, Mingtao He, Liangzhi Cao, Hongchun Wu, Xunzhao Li, Shengcheng Zhou (2017). Reactor core transient analysis of an innovative high-level nuclear waste transmuter with metal fuel. International Journal of Energy Research.DOI
394. Liang Liang, Zhouyu Liu, Youqi Zheng, Liangzhi Cao, Hongchun Wu (2017). Leakage reconstruction method for 2D/1D fusion transport calculations. Progress in Nuclear Energy.DOI
395. Chenghui Wan, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen (2017). Propagation of Nuclear Data Uncertainties for PWR Burnup Calculation. Springer eBooks.DOI
396. Chuanqi Zhao, Kunpeng Wang, Liangzhi Cao, Hongchun Wu, Youqi Zheng (2017). Coupled Neutronics and Thermal–Hydraulics Analysis of Annular Fuel Assembly for SCWR. Springer eBooks.DOI
397. Jun Chen, Liangzhi Cao, Chuanqi Zhao, Hongchun Wu, Zhouyu Liu (2017). Development and Validation of Subchannel Code SUBSC. Springer eBooks.DOI
398. 胡田亮，吴宏春，曹良志，郑友琦，庄坤（2016）. 熔盐堆稳态物理-热工耦合计算研究. 《原子能科学技术》.
399. 赵传奇，曹良志，吴宏春，郑友琦（2016）. 超临界水冷堆可燃毒物设计与分析. 《原子能科学技术》.
400. 赵传奇，曹良志，吴宏春，高新力（2016）. 环形燃料超临界水冷堆中子学计算方法研究. 《原子能科学技术》.
401. 王永平，吴宏春，曹良志，李云召（2016）. 非均匀变分节块法. 《原子能科学技术》.
402. 陈军，曹良志，郑友琦，吴宏春，王昆鹏（2016）. 基于蒙特卡罗方法和CFD方法的物理-热工耦合计算. 《原子能科学技术》.
403. 赵传奇，王昆鹏，曹良志，吴宏春，郑友琦（2016）. 超临界水冷堆环形燃料组件核热耦合分析. 《原子能科学技术》.
404. Yongping Wang, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Wei Shen (2016). Investigation on generalized Variational Nodal Methods for heterogeneous nodes. Annals of Nuclear Energy.DOI
405. Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen (2016). Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly. Annals of Nuclear Energy.DOI
406. Tiejun Zu, Qian Zhang, Hongchun Wu, Liangzhi Cao, Qingming He, Won Sik Yang (2016). Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation. Nuclear Science and Engineering.DOI
407. Longfei Xu, Liangzhi Cao, Youqi Zheng, Hongchun Wu (2016). Development of a new parallel S N code for neutron-photon transport calculation in 3-D cylindrical geometry. Progress in Nuclear Energy.DOI
408. Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen (2016). Total sensitivity and uncertainty analysis for LWR pin-cells with improved UNICORN code. Annals of Nuclear Energy.DOI
409. Zhifeng Li, Liangzhi Cao, Hongchun Wu, Qingming He, Wei Shen (2016). On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor. Progress in Nuclear Energy.DOI
410. Zhifeng Li, Liangzhi Cao, Hongchun Wu, Qingming He (2016). The impacts of thermal neutron scattering effect and resonance elastic scattering effect on FHRs. Annals of Nuclear Energy.DOI
411. Xianan Du, Liangzhi Cao, Youqi Zheng (2016). The Generation of Few-Group Constants for Fast Reactor Analysis.DOI
412. Qingming He, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Tiejun Zu (2016). Neutron Up-Scattering Effect in Refined Energy Group Structure.DOI
413. Zhifeng Li, Liangzhi Cao, Hongchun Wu, Chenghui Wan, Tianliang Hu (2016). Effects of Applying the Implicit Particle Fuel Model for Pebble-Bed Reactors.DOI
414. Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Qingming He (2016). Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation.DOI
415. Tiejun Zu, Chao Yang, Liangzhi Cao, Hongchun Wu (2016). Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells. Annals of Nuclear Energy.DOI
416. Yunzhao Li, Qingming He, Liangzhi Cao, Hongchun Wu, Tiejun Zu (2016). Resonance Elastic Scattering and Interference Effects Treatments in Subgroup Method. Nuclear Engineering and Technology.DOI
417. Baolin Liu, Liangzhi Cao, Hongchun Wu, Xianbao Yuan, Kunpeng Wang (2016). Pre-conceptual core design of a small modular fast reactor cooled by supercritical CO2. Nuclear Engineering and Design.DOI
418. Yunzhao Li, Shengnan Gao, Hongchun Wu, Liangzhi Cao, Wei Shen (2016). PWR few-group constants parameterization analysis. Progress in Nuclear Energy.DOI
419. Liangzhi Cao, Zhipeng Li, Hongchun Wu, Yunzhao Li (2016). Improved variable-transformation algorithm for the hexagonal Variational Nodal Method. Transactions of the American Nuclear Society.
420. 庄坤，郑友琦，曹良志，吴宏春，黄凯，王昆鹏（2015）. 熔盐堆燃料管理程序开发. 《原子能科学技术》.
421. 万承辉，曹良志，吴宏春，祖铁军，沈炜（2015）. 基于抽样方法的特征值不确定度分析. 《原子能科学技术》.
422. 刘勇，曹良志，吴宏春，祖铁军（2015）. 基于经典微扰理论的特征值灵敏度和不确定度分析. 《原子能科学技术》.
423. 李茁，吴宏春，曹良志，李云召（2015）. 基于谐波展开法的压水堆堆芯功率分布在线监测. 《核动力工程》.
424. Liangzhi Cao (2015). Global R&D Status of Generation Ⅳ Nuclear Energy Systems. 《2015欧亚经济论坛-2015第五届国际新能源产业大会》.
425. Qingming He, Liangzhi Cao, Hongchun Wu, Tiejun Zu (2015). Improved resonance calculation of fluoride salt-cooled high-temperature reactor based on subgroup method. Annals of Nuclear Energy.DOI
426. Kai Huang, Hongchun Wu, Liangzhi Cao, Yunzhao Li, Wei Shen (2015). Improvements to the Transmutation Trajectory Analysis of depletion evaluation. Annals of Nuclear Energy.DOI
427. Chenghui Wan, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen (2015). Code development for eigenvalue total sensitivity analysis and total uncertainty analysis. Annals of Nuclear Energy.DOI
428. Liangzhi Cao, Andrew Gerlach, Yunlin Xu, Thomas J. Downar, John C. Lee (2015). Neutronics modeling of the SPERT III E-Core critical experiments with MPACT and KENO. Annals of Nuclear Energy.DOI
429. Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen (2015). Eigenvalue implicit sensitivity and uncertainty analysis with the subgroup resonance-calculation method. Annals of Nuclear Energy.DOI
430. Xianbao Yuan, Liangzhi Cao, Hongchun Wu (2015). Pre-conceptual study of small modular PbBi-cooled nitride fuel reactor core characteristics. Nuclear Engineering and Design.DOI
431. Qian Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2015). An Improved Resonance Self-Shielding Calculation Method Based on Equivalence Theory. Nuclear Science and Engineering.DOI
432. Zhuo Li, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Yunzhao Li, Kunpeng Wang (2015). ICONE23-1692 3D PWR POWER DISTRIBUTION ON-LINE MONITORING BASED ON HARMONICS EXPANSION. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
433. Tiejun Zu, Hongchun Wu, Youqi Zheng, Liangzhi Cao (2015). Economics analysis of fuel cycle cost of fusion–fission hybrid reactors based on different fuel cycle strategies. Fusion Engineering and Design.DOI
434. 贺清明，曹良志，吴宏春，郑友琦（2014）. 在MCNP中考虑共振弹性散射的修正方法. 《原子能科学技术》.
435. 杨文，郑友琦，吴宏春，曹良志，李云召（2014）. 基于EFEN-SP3方法的高性能全堆芯Pin-by-pin计算研究. 《核动力工程》.
436. 贺雷，吴宏春，曹良志（2014）. 二维任意几何耦合共振计算方法研究. 《核动力工程》.
437. 庄坤，曹良志，郑友琦，吴宏春（2014）. 熔盐堆动力学软件开发. 《核动力工程》.
438. 贺清明，曹良志，吴宏春，祖铁军（2014）. 确定论方法中共振弹性散射的修正方法研究. 《核动力工程》.
439. 杨超，曹良志，吴宏春，祖铁军（2014）. 基于一阶广义微扰理论的燃耗灵敏度系数计算. 《核动力工程》.
440. 刘勇，曹良志，吴宏春，祖铁军（2014）. 基于子群共振自屏方法的特征值隐式敏感性分析. 《核动力工程》.
441. 郑征，吴宏春，曹良志，梅其良，黎辉（2014）. 三维离散纵标-蒙特卡罗耦合方法在快中子注量率计算中的应用. 《核动力工程》.
442. 李志鹏，郑友琦，曹良志（2014）. 径向倒料式长寿期钠冷快堆方案研究. 《核动力工程》.
443. 袁显宝，曹良志（2014）. 铅铋冷却氮化物燃料小型模块化反应堆堆芯中子学特性分析. 《核动力工程》.
444. 祖铁军，吴宏春，郑友琦，曹良志（2014）. 聚变裂变混合堆燃耗计算及燃料成本分析. 《核动力工程》.
445. 娄磊，曹良志，吴宏春，郑友琦（2014）. 径向倒料式驻波堆堆芯概念设计. 《原子能科学技术》.
446. 张乾，吴宏春，曹良志，郑友琦（2014）. 嵌入式自屏方法研究. 《现代应用物理》.
447. Yunzhao Li, Elmer E. Lewis, Micheal A. Smith, Hongchun Wu, Liangzhi Cao (2014). Preconditioned Multigroup GMRES Algorithms for the Variational Nodal Method. Nuclear Science and Engineering.DOI
448. Ammar Ahmad, Liangzhi Cao, Hongchun Wu, Chuanqi Zhao (2014). Conceptual design of pressure-tube super critical water reactor with inverted geometry. Nuclear Engineering and Design.DOI
449. Shengcheng Zhou, Hongchun Wu, Liangzhi 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
450. Kun Zhuang, Liangzhi Cao, Youqi Zheng, Hongchun Wu (2014). Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design. Journal of Nuclear Science and Technology.DOI
451. Mingtao He, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Shengcheng Zhou (2014). Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh.DOI
452. Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Yunzhao Li (2014). Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors.DOI
453. Baolin Liu, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Xianbao Yuan (2014). Preliminary Core Design of the Long Life S-CO2 Cooled Fast Reactor With 300WMth.DOI
454. Tiejun Zu, Hongchun Wu, Youqi Zheng, Liangzhi Cao (2014). Burnup calculations of light water-cooled pressure tube blanket for a fusion-fission hybrid reactor. Fusion Engineering and Design.DOI
455. Ammar Ahmad, Liangzhi Cao, Hongchun Wu (2014). Coupled analysis and improvements for Canadian-SCWR core design. Nuclear Engineering and Design.DOI
456. Bao‐Wen Yang, Yassin A. Hassan, Jianqiang Shan, Bin Zhang, Junli Gou, Liangzhi Cao (2014). Subchannel Analysis, CFD Modeling and Verifications, CHF Experiments and Benchmarking. Science and Technology of Nuclear Installations.DOI
457. 周生诚，吴宏春，曹良志，郑友琦（2013）. 加速器驱动次临界堆芯中子学程序开发. 《原子能科学技术》.
458. 庄坤，曹良志，吴宏春，郑友琦（2013）. 球床型固体燃料熔盐堆计算软件开发. 《原子能科学技术》.
459. 张滕飞，朱磊，吴宏春，郑友琦，曹良志，孙寿华（2013）. 高通量堆燃料管理平台HEFT的研发与验证. 《原子能科学技术》.
460. 赵传奇，曹良志，吴宏春，郑友琦（2013）. 采用环形燃料的超临界水冷堆核热耦合分析. 《原子能科学技术》.
461. 杨文，郑友琦，吴宏春，曹良志，李云召（2013）. EFEN-SP3方法的加速与并行计算研究. 《原子能科学技术》.
462. 张乾，吴宏春，曹良志，郑友琦（2013）. 等价理论的偏差分析与改进研究. 《原子能科学技术》.
463. 张广春，曹良志，吴宏春，郑友琦（2013）. ITER实验包层模块的三维确定论方法计算. 《原子能科学技术》.
464. 刘琨，吴宏春，曹良志，郑友琦（2013）. 压水堆高放长寿命裂变产物堆内嬗变平衡循环设计. 《原子能科学技术》.
465. 李勋昭，吴宏春，曹良志，郑友琦（2013）. 加速器驱动的次临界系统初步概念设计. 《原子能科学技术》.
466. 刘保林，吴宏春，曹良志，郑友琦（2013）. 超临界水冷快堆增殖因子敏感性初步研究. 《原子能科学技术》.
467. 杨超，曹良志，吴宏春，郑友琦，祖铁军（2013）. 聚变驱动的次临界系统嬗变MA的研究. 《原子能科学技术》.
468. 赵传奇，曹良志，吴宏春，郑友琦（2013）. 改进双排棒组件超临界水堆堆芯设计. 《原子能科学技术》.
469. 贺雷，吴宏春，曹良志，张宏博（2013）. NECP软件包中NECL子群数据与任意几何共振模块研制. 《原子能科学技术》.
470. 李虹波，杨珏，程旭，单建强，曹良志，刘晓晶（2013）. SCWR堆芯和主要系统方案研究及初步分析. 《原子能科学技术》.
471. 李云召，吴宏春，曹良志，郑友琦（2013）. 扩散临界计算中的多重迭代优化技术. 《原子能科学技术》.
472. 贺雷，吴宏春，曹良志（2013）. 二维任意几何子群共振计算及加速优化. 《核动力工程》.
473. 祖铁军，吴宏春，郑友琦，曹良志（2013）. 聚变裂变混合堆中子学分析软件开发. 《核动力工程》.
474. 张宏博，吴宏春，曹良志，郑友琦，夏榜样（2013）. 基于Krylov子空间及区域分解理论的二维矩阵特征线方法. 《核动力工程》.
475. 夏榜样，赵传奇，曹良志，李庆，李翔，李满昌（2013）. 环形元件超临界水冷堆CSR1000A初步概念设计. 《核动力工程》.
476. 贺雷，吴宏春，曹良志（2013）. 先进耦合共振计算方法研究. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会会议摘要集》.
477. 肖云龙，吴宏春，曹良志，郑友琦，李云召（2013）. 增殖比可调快堆堆芯方案设计. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会会议摘要集》.
478. 杨文，郑友琦，吴宏春，曹良志，李云召（2013）. 三维矩形节块SP 3 方法的加速与并行计算研究. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会会议摘要集》.
479. 李云召，吴宏春，曹良志，郑友琦（2013）. 变分节块法扩散临界计算中的多重迭代优化技术. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会》.
480. 赵传奇，曹良志，吴宏春，郑友琦（2013）. 采用环形燃料的超临界水堆核热耦合分析. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会》.
481. 张滕飞，吴宏春，郑友琦，曹良志（2013）. HEFT高通量堆燃料管理平台研发与验证. 《第六届反应堆物理与核材料学术研讨会第三届核能软件自主化研讨会会议摘要集》.
482. Yuxiong Cheng, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Three-Dimensional Inverse Transport Solver Based on Compressive Sensing Technique. Transport Theory and Statistical Physics.DOI
483. Zheng Zheng, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Hongbo Zhang (2013). A deterministic and Monte Carlo coupling method for PWR cavity radiation streaming calculation. Annals of Nuclear Energy.DOI
484. Liangzhi Cao, Mengqi Wang, Hongchun Wu, Zhouyu Liu, Yuxiong Cheng, Hongbo Zhang (2013). SCATTERING CORRECTION FOR IMAGE RECONSTRUCTION IN FLASH RADIOGRAPHY. Nuclear Engineering and Technology.DOI
485. Liang Liang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Development of a Two-Dimensional Modularity Characteristics Code for Neutron Transport Calculation. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering.DOI
486. Kai Huang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Study on Improvement of Analytic Depletion Calculation Method.DOI
487. Qian Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Spatially Dependent Resonance Cross Sections in a Fuel Plate. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering.DOI
488. Xunzhao Li, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). A Neutronics Concept Design of Lead-Bismuth Cooled Accelerator-Driven System for Minor Actinide Transmutation. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors.DOI
489. Yong Zhang, Jue Yang, Dongsheng Li, Liangzhi Cao, Fei Wang, Shuai Zhao, Hongbo Li (2013). A Study on SCWR Core Design and Fuel Management. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors.DOI
490. Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Optimization Study on LLFPs Transmutation in PWRs. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering.DOI
491. Yunzhao Li, Hongchun Wu, Liangzhi Cao (2013). Unstructured Triangular Nodal- SP 3 Method Based on an Exponential Function Expansion. Nuclear Science and Engineering.DOI
492. Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2013). Studies on LLFP transmutation in a pressurized water reactor. Journal of Nuclear Science and Technology.DOI
493. Chao Yang, Liangzhi Cao, Hongchun Wu, Youqi Zheng, Tiejun Zu (2013). Neutronics analysis of minor actinides transmutation in a fusion-driven subcritical system. Fusion Engineering and Design.DOI
494. Guangchun Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Yunzhao Li, Zhouyu Liu (2013). Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method. Fusion Engineering and Design.DOI
495. Kunpeng Wang, A. Rineiski, Werner Maschek, Hongchun Wu, Liangzhi Cao (2013). Neutron transport model based on the transmission probability method. Energy Conversion and Management.DOI
496. Tiejun Zu, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Chao Yang (2013). NAPTH: Neutronics analysis code system for the fusion–fission hybrid reactor with pressure tube type blanket. Fusion Engineering and Design.DOI
497. Hongchun Wu, Tiejun Zu, Suizheng Qiu, Xinli Gao, Youqi Zheng, Liangzhi Cao, Wenxi Tian (2013). A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production. Progress in Nuclear Energy.DOI
498. Chuanqi Zhao, Liangzhi Cao, Hongchun Wu, Jue Yang, Yong Zhang (2013). Conceptual design of a supercritical water reactor with double-row-rod assembly. Progress in Nuclear Energy.DOI
499. Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Changhui Wang (2013). A code development for LLFP transmutation analysis based on the whole pin-wise calculation in PWRs. Nuclear Engineering and Design.DOI
500. Lei He, Hongchun Wu, Liangzhi Cao, Yunzhao Li (2013). Improvements of the subgroup resonance calculation code SUGAR. Annals of Nuclear Energy.DOI
501. Chuanqi Zhao, Liangzhi Cao, Hongchun Wu, Youqi Zheng (2013). Pre-conceptual core design of SCWR with annular fuel rods. Nuclear Engineering and Design.DOI
502. Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Yunzhao Li (2013). A 3D transport-based core analysis code for research reactors with unstructured geometry. Nuclear Engineering and Design.DOI
503. 郑征，吴宏春，曹良志，郑友琦，张宏博，王梦琪（2012）. 蒙特卡罗与离散纵标耦合方法在压水堆堆腔漏束计算中的应用. 《强激光与粒子束》.
504. 王梦琪，曹良志，吴宏春，程玉雄，张宏博（2012）. 闪光层析成像散射修正计算研究. 《原子能科学技术》.
505. 杜炳，吴宏春，曹良志，王常辉，张宏博（2012）. 基于预估修正改进准静态方法的中子时空动力学研究. 《原子能科学技术》.
506. 王梦琪，曹良志，吴宏春，程玉雄，刘宙宇，张宏博（2012）. 三维任意几何光子成像系统的散射修正及图像重建方法. 《西安交通大学学报》.
507. 杨珏，张勇，赵传奇，单建强，王飞，曹良志（2012）. 双排棒组件超临界水堆堆芯方案设计. 《西安交通大学学报》.
508. Youqi Zheng, Hongchun Wu, Liangzhi Cao (2012). Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equation. Nuclear Engineering and Design.DOI
509. Lei He, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Hongbo Zhang (2012). Research on the Subgroup Method and 2D Arbitrary Geometry Resonance Calculation Code. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio.DOI
510. Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Changhui Wang (2012). Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
511. Guangchun Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (2012). Calculations of the Dual Functional Lithium Lead-Test Blanket Module for ITER With Three-Dimensional Deterministic Method. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
512. Tiejun Zu, Hongchun Wu, Youqi Zheng, Liangzhi Cao (2012). Neutronics Performance of a Fusion-Fission Hybrid Reactor With Pressure Tube Assemblies. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
513. Youqi Zheng, Tiejun Zu, Hongchun Wu, Liangzhi Cao, Chao Yang (2012). The neutronics studies of a fusion fission hybrid reactor using pressure tube blankets. Fusion Engineering and Design.DOI
514. Youqi Zheng, Hongchun Wu, Liangzhi Cao (2012). Application of the wavelet expansion method in spatial-angular discretization of the neutron transport equation. Annals of Nuclear Energy.DOI
515. 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
516. Youqi Zheng, Hongchun Wu, Tiejun Zu, Chao Yang, Liangzhi Cao (2012). The neutronics studies of fusion fission hybrid power reactor. AIP conference proceedings.DOI
517. 张勇，杨珏，曹良志，赵传奇，卢冬华（2011）. 环形燃料SCWR物理特性分析. 《中国核科学技术进展报告（第二卷）——中国核学会2011年学术年会论文集第3册（核能动力分卷（下））》.
518. 刘庆杰，吴宏春，曹良志（2011）. 一维球形裂变系统二元随机介质中子输运数值求解. 《核动力工程》.
519. 程玉雄，曹良志，吴宏春，郑友琦，张宏博（2011）. 基于压缩传感的图像重建. 《第五届反应堆物理与核材料学术研讨会、第二届核能软件自主化研讨会》.
520. 贺雷，吴宏春，曹良志（2011）. 二维子群共振计算方法研究. 《第五届反应堆物理与核材料学术研讨会、第二届核能软件自主化研讨会会议摘要集》.
521. 刘琨，吴宏春，曹良志，郑友琦，王常辉（2011）. 高通量工程试验堆的嬗变靶件嬗变敏感性分析. 《第五届反应堆物理与核材料学术研讨会、第二届核能软件自主化研讨会会议摘要集》.
522. 张广春，吴宏春，曹良志，郑友琦，刘宙宇（2011）. ITER中国液态锂铅实验包层模块三维确定论方法中子学分析. 《第五届反应堆物理与核材料学术研讨会、第二届核能软件自主化研讨会会议摘要集》.
523. Hongbo Zhang, Hongchun Wu, Liangzhi Cao (2011). An acceleration technique for 2D MOC based on Krylov subspace and domain decomposition methods. Annals of Nuclear Energy.DOI
524. Changhui Wang, Hongchun Wu, Liangzhi Cao, Ping Yang (2011). On-line reconstruction of in-core power distribution by harmonics expansion method. Nuclear Engineering and Design.DOI
525. Ping Yang, Liangzhi Cao, Hongchun Wu, Changhui Wang (2011). Core design study on CANDU-SCWR with 3D neutronics/thermal-hydraulics coupling. Nuclear Engineering and Design.DOI
526. Liangzhi Cao (2011). Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry. Hedongli gongcheng.
527. 刘庆杰，吴宏春，曹良志，陈其昌（2010）. 二维任意几何子群共振计算程序的开发. 《核动力工程》.
528. 杨伟焱，吴宏春，曹良志，刘庆杰（2010）. 小波尺度函数展开共振自屏计算方法在有温度分布共振自屏计算问题中的应用研究. 《核动力工程》.
529. 李云召，吴宏春，曹良志，姚栋（2010）. 节块SP3方法求解中子输运方程. 《核动力工程》.
530. 王昆鹏，吴宏春，曹良志，王常辉（2010）. 三维三棱柱多群中子扩散方程的解析基函数展开方法. 《核动力工程》.
531. 郑征，吴宏春，曹良志，李云召，陈其昌（2010）. 一维平板几何中子输运方程PN-DPN耦合方法. 《核动力工程》.
532. 程玉雄，曹良志，吴宏春，王梦琪，陈其昌（2010）. 逆向输运问题的直接求解. 《核动力工程》.
533. 王昆鹏，徐晓燕，吴宏春，曹良志，宋小明，姚栋（2010）. 溶液堆落棒及弹棒事故分析. 《原子能科学技术》.
534. 刘国明，吴宏春，曹良志，陈其昌（2010）. 复杂几何中子输运方程离散方向概率方法研究. 《核动力工程》.
535. 祖铁军，吴宏春，曹良志，杨伟炎，刘国明（2010）. 小波尺度函数展开连续能量共振计算加速方法研究. 《核动力工程》.
536. 张宏博，吴宏春，曹良志，孙幸光（2010）. 中子输运计算的角度多重网格加速和L-W外推加速技术. 《核动力工程》.
537. 刘宙宇，吴宏春，曹良志，陈其昌，李云召（2010）. 三维模块化特征线方法. 《核动力工程》.
538. 贾士壮，曹良志，吴宏春，郑友琦，傅先刚，杨珏（2010）. 压水堆装载30%MOX燃料的燃料管理及经济性分析. 《核动力工程》.
539. 王常辉，吴宏春，曹良志（2010）. 在线监测压水堆堆芯功率分布的谐波展开法. 《核动力工程》.
540. Zhouyu Liu, Hongchun Wu, Liangzhi Cao, Qichang Chen, Yunzhao Li (2010). A new three-dimensional method of characteristics for the neutron transport calculation. Annals of Nuclear Energy.DOI
541. Weiyan Yang, Hongchun Wu, Youqi Zheng, Liangzhi Cao (2010). Application of wavelets scaling function expansion method in resonance self-shielding calculation. Annals of Nuclear Energy.DOI
542. Youqi Zheng, Hongchun Wu, Liangzhi Cao, Nam Zin Cho (2010). Daubechies’ Wavelet Method for Angular Solution of the Neutron Transport Equation. Nuclear Science and Engineering.DOI
543. Yulong Qin, Hongchun Wu, Liangzhi Cao, Qingjie Liu (2010). Resonance Calculation Code UFOP Based on the Hyper-Fine Group Neutron Resonance Calculation Method. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
544. Yunzhao Li, Hongchun Wu, Liangzhi Cao, Qichang Chen (2010). Exponential Function Expansion Nodal Diffusion Method. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
545. Hongbo Zhang, Hongchun Wu, Liangzhi Cao (2010). Acceleration Technique Using Krylov Subspace Methods for 2D Arbitrary Geometry Characteristics Solver. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
546. Kunpeng Wang, Hongchun Wu, Liangzhi Cao, Changhui Wang (2010). Analytic Basis Function Expansion Nodal Method for Neutron Diffusion Equations in Triangular Geometry. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
547. Ping Yang, Liangzhi Cao, Hongchun Wu, Changhui Wang (2010). Conceptual Design of CANDU-SCWR With Thermal-Hydraulics Coupling. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
548. Lei He, Hongchun Wu, Liangzhi Cao, Qingjie Liu, Zhiyan Liu (2010). Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
549. Zhouyu Liu, Hongchun Wu, Liangzhi Cao, Qichang Chen, Yunzhao Li (2010). Direct 3D MOC for Whole-Core Transport Calculation. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
550. Qingjie Liu, Hongchun Wu, Liangzhi Cao (2010). Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
551. Shizhuang Jia, Liangzhi Cao, Hongchun Wu (2010). Economic Analysis on MOX Fuels. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
552. Zhiyan Liu, Hongchun Wu, Liangzhi Cao, Qingjie Liu (2010). The Consistency of WIMS-D Library and ACE Format Library. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
553. Weiyan Yang, Hongchun Wu, Liangzhi Cao (2010). Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
554. Youqi Zheng, Hongchun Wu, Liangzhi Cao (2010). Neutron Transport Solution Using the Daubechies’ Wavelets in the Spatial Discretization. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
555. Changhui Wang, Hongchun Wu, Liangzhi Cao (2010). On Line Monitoring the Reactor Power Distribution Based on the Data Library of the Eigenfunctions. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
556. Tiejun Zu, Hongchun Wu, Liangzhi Cao, Qingjie Liu, Weiyan Yang (2010). Wavelets Scaling Function Expansion Resonance Self-Shielding Calculation Based on the DDPM. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
557. Hongchun Wu, Guoming Liu, Liangzhi Cao, Qichang Chen (2010). Determinant Methods for Solving Neutron Transport Equation in Unstructured Geometry. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
558. Liangzhi Cao (2010). Harmonics Expansion Method for On-line Monitoring of PWR Power Distribution. Hedongli gongcheng.
559. 陈其昌，吴宏春，曹良志（2009）. 基于AutoCAD二次开发实现中子输运方程特征线法求解. 《原子能科学技术》.
560. 黄伟兵，吴宏春，曹良志，杨伟焱（2009）. 任意几何燃料组件共振自屏计算的Multiband方法. 《核动力工程》.
561. 李云召，吴宏春，曹良志，彭思涛，卢皓亮，宋小明，姚栋（2009）. 溶液堆燃料管理计算方法初步研究与程序研制. 《核动力工程》.
562. 杨伟焱，吴宏春，曹良志，郑友琦（2009）. 小波尺度函数展开在连续能量中子输运方程计算中的应用. 《核动力工程》.
563. 郑友琦，吴宏春，曹良志，于颖锐（2009）. 中子输运方程的Daubechies小波角度离散. 《核动力工程》.
564. Yunzhao Li, Hongchun Wu, Liangzhi Cao, Qichang Chen, Haoliang Lu, Sitao Peng, Xiaoming Song, Dong Yao (2009). FMSR: A code system for in-core fuel management calculation of aqueous homogeneous solution reactor. Nuclear Engineering and Design.DOI
565. Qingjie Liu, Hongchun Wu, Liangzhi Cao (2009). Solution of the multiplying binary stochastic media based on L–P equation in 1D spherical geometry. Nuclear Engineering and Design.DOI
566. Youqi Zheng, Hongchun Wu, Liangzhi Cao (2009). Wavelet-based angular dependence analysis of the heterogeneous calculation on MOX fuel lattice. Nuclear Engineering and Design.DOI
567. Youqi Zheng, Hongchun Wu, Liangzhi Cao (2009). An improved three-dimensional wavelet-based method for solving the first-order Boltzmann transport equation. Annals of Nuclear Energy.DOI
568. Changhui Wang, Hongchun Wu, Liangzhi Cao (2009). On-Line Monitoring the In-Core Flux Distribution Using the Eigenfunctions.DOI
569. Weiyan Yang, Hongchun Wu, Liangzhi Cao (2009). Application of Wavelet Scaling Function Expansion to Continuous-Energy Resonance Calculation.DOI
570. Liangzhi Cao (2009). Realization of Method of Characteristics Based on Customization of AutoCAD. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
571. 吴宏春，孙幸光，曹良志，沈智军（2008）. 二维中子输运方程计算的角度多重网格加速方法及外推加速技术. 《核动力工程》.
572. 陈其昌，吴宏春，曹良志（2008）. 基于AutoCAD二次开发技术的任意几何中子输运方程特征线解法. 《第十二届反应堆数值计算与粒子输运学术会议》.
573. 王昆鹏，吴宏春，曹良志，彭思涛，宋小明，姚栋（2008）. 溶液堆启堆分析及瞬态研究. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
574. 李云召，吴宏春，卢皓亮，曹良志，宋小明，姚栋（2008）. 溶液堆堆芯计算方法研究与程序研制. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
575. 曹良志，郑友琦，吴宏春（2008）. 中子输运方程的Daubechies小波方法角度离散. 《第五届全国青年计算物理学术交流会》.
576. 刘庆杰，吴宏春，曹良志（2008）. 一维球形二元随机介质系统中子输运数值求解. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
577. 曹良志，吴宏春（2008）. 高功率密度超临界水冷快堆堆芯概念设计. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
578. 刘国明，吴宏春，曹良志（2008）. 基于三角形网格的线性源近似穿透概率方法研究. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
579. 郑友琦，曹良志，吴宏春（2008）. 二维中子输运方程小波分析方法. 《第十二届反应堆数值计算与粒子输运学术会议》.
580. 黄伟兵，杨伟炎，吴宏春，曹良志（2008）. 任意几何燃料组件共振自屏计算的multiband方法研究. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
581. 彭思涛，陈其昌，吴宏春，曹良志，宋小明，姚栋（2008）. 溶液堆少群截面参数计算方法研究. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
582. 吴宏春，曹良志，孙幸光，巨海涛，肖锋，张俊（2008）. 中子输运方程数值计算的加速方法研究. 《第十二届反应堆数值计算与粒子输运学术会议论文集》.
583. Liangzhi Cao, Y. Oka, Yuki Ishiwatari, Satoshi Ikejiri (2008). Three-dimensional core analysis on a super fast reactor with negative local void reactivity. Nuclear Engineering and Design.DOI
584. Qichang Chen, Hongchun Wu, Liangzhi Cao (2008). Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD. Nuclear Engineering and Design.DOI
585. Liangzhi Cao, Hongchun Wu, Youqi Zheng (2008). Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization. Nuclear Engineering and Design.DOI
586. Guoming Liu, Hongchun Wu, Liangzhi Cao (2008). Transmission probability method for solving neutron transport equation in three-dimensional triangular-z geometry. Nuclear Engineering and Design.DOI
587. Liangzhi CAO, Y. Oka, Yuki Ishiwatari, Zhi Shang (2008). Fuel, Core Design and Subchannel Analysis of a Superfast Reactor. Journal of Nuclear Science and Technology.DOI
588. Qichang Chen, Hongchun Wu, Liangzhi Cao (2008). The Method of Characteristics for Arbitrary Geometry Based on the Customization of Autocad. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
589. 吴宏春，巨海涛，卢皓亮，刘国明，曹良志（2007）. 基于非结构网格的中子输运方程计算方法研究. 《西安交通大学学报》.
590. 曹良志，吴宏春，姚栋（2007）. 用于复杂环境下中子时空动力学计算的简化球谐函数方法. 《核动力工程》.
591. 郑友琦，曹良志，吴宏春（2007）. 中子输运方程的小波分析方法研究. 《第三届反应堆物理与核材料学术研讨会论文集》.
592. Liangzhi Cao, Hongchun Wu (2007). A spherical harmonics—Finite element discretization of the self-adjoint angular flux neutron transport equation. Nuclear Engineering and Design.DOI
593. Hongchun Wu, Pingping Liu, Yongqiang Zhou, Liangzhi Cao (2007). Transmission probability method based on triangle meshes for solving the unstructured geometry neutron transport problem. Frontiers of Energy and Power Engineering in China.DOI
594. Haoliang Lu, Hongchun Wu, Liangzhi Cao, Yongqiang Zhou, Xian Chunyu, Dong Yao (2007). Two-dimensional nodal transport method for triangular geometry. Annals of Nuclear Energy.DOI
595. 曹良志，吴宏春，周永强（2006）. 非结构几何下二阶自共轭中子输运方程中的简化球谐函数方法研究. 《核动力工程》.
596. 刘启伟，吴宏春，周永强，曹良志（2006）. 三维离散纵标中子输运稳态及瞬态动力学计算. 《西安交通大学学报》.
597. 卢皓亮，吴宏春，曹良志，周永强，咸春宇，姚栋（2006）. 非结构网格中子输运方程的离散纵标节块数值解法. 《西安交通大学学报》.
598. 卢皓亮，吴宏春，曹良志，周永强，咸春宇，姚栋（2006）. 中子输运方程的三角形节块SN方法研究. 《核动力工程》.
599. 巨海涛，吴宏春，曹良志，周永强，姚栋，咸春宇（2006）. 二维中子输运方程的非结构网格离散纵标数值解法. 《核动力工程》.
600. 曹良志，吴宏春（2004）. 非结构网格中子输运方程的球谐函数解法研究. 《核动力工程》.
601. 曹良志，谢仲生，吴宏春，廖承奎，孔德萍，吴锡锋（2003）. 先进的压水堆燃料管理计算方法研究及软件研制. 《西安交通大学学报》.

书籍章节

1. L C Zhang, Defeng Yang, Xiaoxia Wang, Aijun Mi, Liangzhi Cao (2023). Analysis of Fission Product Diffusion Behavior of Fully Ceramic Micro-encapsulated Fuel. Springer proceedings in physics.DOI
2. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Introduction. Elsevier eBooks.DOI
3. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Subgroup method. Elsevier eBooks.DOI
4. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Resonance cross-section processing. Elsevier eBooks.DOI
5. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). High-fidelity resonance self-shielding calculation. Elsevier eBooks.DOI
6. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Wavelet expansion method. Elsevier eBooks.DOI
7. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Resonance treatment in Monte Carlo method. Elsevier eBooks.DOI
8. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Equivalence theory method. Elsevier eBooks.DOI
9. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Ultrafine group method. Elsevier eBooks.DOI
10. Liangzhi Cao, Hongchun Wu, Qian Zhang, Qingming He, Tiejun Zu (2022). Resonance treatment for double heterogeneity. Elsevier eBooks.DOI
11. Liangzhi Cao, Chao Fang (2020). P -FEM method. Elsevier eBooks.DOI
12. Qingming He, Liangzhi Cao (2020). Current-coupled collision probability method. Elsevier eBooks.DOI
13. Liangzhi Cao (2020). Neutron transport equation. Elsevier eBooks.DOI
14. Youqi Zheng, Yunzhao Li, Liangzhi Cao (2020). Other methods. Elsevier eBooks.DOI