Liangzhi Cao - Publications, H-index & Citations

Liangzhi Cao

xi'an jiaotong university

23H指数

419论文数

2.8K被引数

收录论文 33

发表时间

Development and validation of CFDT code for fission product release analysis of spherical and cylindrical TRISO-based fuel element in HTGRs 球形和圆柱形TRISO基燃料元件在高温气冷堆中裂变产物释放分析的CFDT代码的开发与验证

Annals of Nuclear Energy

IF2.3

2026-09-01

PREAI

Zhang, Liying; Yang, Defeng; Wang, Xiaoxia; Mi, Aijun; Liu, Guoming; Cao, Liangzhi; Liu, Jinkai; Liu, Shiyu; Xie, Pengpei; Zhang, Qingmin

Research advances in high-fidelity neutronics computational methods and applications for advanced nuclear reactors 先进核反应堆高保真中子学计算方法与应用研究进展

Chinese Science Bulletin-Chinese

IF1.2

2026-01-01

PREAI

Wu, Hongchun; Cao, Liangzhi; Zheng, Youqi; Li, Yunzhao; Zu, Tiejun; Liu, Zhouyu; He, Qingming; Wan, Chenghui; Wang, Yongping; Du, Xianan

Calculation and analysis of thermal scattering law data of sub-stoichiometric metal hydrides 亚化学计量金属氢化物热散射律数据的计算与分析

ACTA PHYSICA SINICA

IF0.8

2025-11-20

PREAI

Ma, Yutu; Zu, Tiejun; Wu, Hongchun; Cao, Liangzhi

Multigroup cross-section library generation for deterministic electron-transport calculation 多组截面库生成用于确定性电子输运计算

ANNALS OF NUCLEAR ENERGY

IF2.3

2025-10-01

PREAI

Li, Xiaoying; Li, Yunzhao; Shao, Ruizhi; Xu, Ning; Cao, Liangzhi; Zu, Tiejun

Feasibility study on the core design of high-flux fast neutron research reactors 高通量快中子研究堆核心设计的可行性研究

Nuclear Engineering and Technology

IF2.6

2025-09-06

OAAI

Miao Zhao; Xianan Du; Youqi Zheng; Mingyu Wu; Rui Yang; Li Xu; Liangzhi Cao; Hongchun Wu

Application of the half-boundary method to solving the neutron transport equation in 1D cylindrical coordinate 半边界法在1D圆柱坐标系下求解中子输运方程的应用

Progress in Nuclear Energy

IF3.2

2025-08-26

PREAI

Yang Liu; Lei Xue; Hangyu Shi; Zhiyi Ni; Liangzhi Cao; Xiaoping Ouyang

Deep learning-based prediction of transient power variation in pressurized water reactors

PROGRESS IN NUCLEAR ENERGY

IF3.2

2025-04-01

PREAI

Liu, Zhouyu; Liu, Jiawang; Shao, Shihao; Cao, Liangzhi; Wu, Hongchun

Implementation of one-phonon correction method to calculate inelastic scattering law data in nuclear data processing code NECP-Atlas

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-12-01

PREAI

Zu, Tiejun; Wu, Chengyao; Feng, Hao; Ma, Yutu; Cao, Liangzhi; Wu, Hongchun; Tang, Yongqiang

Verifications and applications of NECP-Bamboo2.0 for PWR whole-core multi-cycle pin-by-pin simulation

PROGRESS IN NUCLEAR ENERGY

IF3.2

2024-12-01

PREAI

Wang, Sicheng; Li, Yunzhao; Qin, Junwei; Liang, Yilin; Zhou, Yuancheng; Cao, Liangzhi; Wu, Hongchun

Capability of processing the GNDS format evaluated nuclear data in NECP-Atlas for neutronics calculations

PROGRESS IN NUCLEAR ENERGY

IF3.2

2022-08-01

PREAI

Huang, Yihan; Zu, Tiejun; Cao, Liangzhi; Wu, Hongchun

Uncertainty propagation of prompt fission neutron spectrum for physics analysis of fast and thermal reactors

PROGRESS IN NUCLEAR ENERGY

IF3.2

2022-02-01

PREAI

Zou, Xiaoyang; Cao, Liangzhi; Teng, Qichen; Zu, Tiejun; Wan, Chenghui

Performance of CENDL-3.2 evaluated nuclear data library for the shielding benchmarks

PROGRESS IN NUCLEAR ENERGY

IF3.2

2021-06-01

PREAI

Shu, Wenyu; Zu, Tiejun; Cao, Liangzhi; Wu, Hongchun

Neutronic calculations of the China dual-functional lithium-lead test blanket module with the parallel discrete ordinates code Hydra 并行离散纵坐标代码Hydra的中国双功能锂铅测试毯模块的中子计算

NUCLEAR SCIENCE AND TECHNIQUES

IF3.8

2020-07-27

PREAI

Zhang, Guang-Chun; Liu, Jie; Cao, Liang-Zhi; Wu, Hong-Chun; Yuan, Xian-Bao

SPERT III E-Core critical experiment benchmarks calculation with NECP-X and KENO-VI

PROGRESS IN NUCLEAR ENERGY

IF3.2

2020-06-01

PREAI

Zhao, Chen; Liu, Zhouyu; Cao, Lu; Shen, Qicang; Downar, Thomas; Cao, Liangzhi

Analysis of the thermal feedback effect and nuclides flow effect on the fuel-cycle characteristics of Molten Salt Reactors

INTERNATIONAL JOURNAL OF ENERGY RESEARCH

IF4.2

2020-04-27

OAAI

Hu, Tianliang; Cao, Liangzhi; Yang, Shouhai; Fratoni, Massimiliano; Wu, Hongchun

A processing method of generating S(α, β, T) tables considering resonance elastic scattering kernel for the Monte Carlo codes

PROGRESS IN NUCLEAR ENERGY

IF3.2

2020-04-01

PREAI

Zu, Tiejun; Xu, Jialong; Cao, Liangzhi

The on-the-fly subgroup method capable of treating spatial self-shielding, resonance interference and temperature distribution effects

PROGRESS IN NUCLEAR ENERGY

IF3.2

2020-01-01

PREAI

He, Qingming; Chen, Jun; Liu, Zhouyu; Cao, Liangzhi; Wu, Hongchun

Development and verification of resonance elastic scattering kernel processing module in nuclear data processing code NECP-Atlas 核数据处理代码necp-atlas中共振弹性散射核处理模块的开发与验证

PROGRESS IN NUCLEAR ENERGY

IF3.2

2019-01-01

PREAI

Xu, Jialong; Zu, Tiejun; Cao, Liangzhi

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

IF3.2

2018-09-01

PREAI

Wang, Bo; Liu, Zhouyu; Chen, Jun; Zhao, Chen; Cao, Liangzhi; Wu, Hongchun

Conceptual core design study of an innovative small transportable lead-bismuth cooled fast reactor (SPARK) for remote power supply

INTERNATIONAL JOURNAL OF ENERGY RESEARCH

IF4.2

2018-06-06

OAAI

Zhou, Shengcheng; Chen, Renzong; Shao, Yiqiong; Cao, Liangzhi; Bai, Bofeng; Wu, Hongchun

研究方向