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Liangzhi Cao

affiliation not provided to SSRN

  • affiliation not provided to SSRN

SCHOLARLY PAPERS

7

DOWNLOADS

177

TOTAL CITATIONS

1

Scholarly Papers (7)

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1.

Development and Validation of CFDT code for Fission Product Release Analysis of Spherical and Cylindrical TRISO-based Fuel Element in HTGRs

Number of pages: 22 Posted: 17 Nov 2025
Li-Ying Zhang, Defeng Yang, Xiaoxia Wang, Aijun Mi, Guoming Liu, Liangzhi Cao, Jinkai Liu, Shiyu Liu, Pengpei Xie and Qingmin Zhang
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 52 (1,052,702)

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TRISO Fuel, Fission product release, Finite volume method, Cylindrical fuel element, High-Temperature Gas-Cooled Reactors

2.

Study on Monte Carlo Iterative K-Source (IKS) Method for Frequency Domain Neutron Noise Calculation

Number of pages: 23 Posted: 05 Sep 2025
Xuran Yang, Qi Zheng, Liangzhi Cao, Qingming He and Hongchun Wu
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 36 (1,249,711)

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Neutron noise, Monte Carlo Iterative K-source, Frequency Domain Neutron Noise

3.

Particle-transport/depletion/activation/source-term coupling analysis for CFETR with NECP-MCX

Number of pages: 35 Posted: 03 Jun 2022
Qingming He, Jie Li, Liangzhi Cao, Hongchun Wu and Wei Shen
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 35 (1,249,711)
Citation 1

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TBR, SDDR, Monte Carlo, CFETR, NECP-MCX

4.

BRepNet-based BRep-to-CSG conversion for complex geometry modelling in Monte Carlo particle transport calculation

Number of pages: 22 Posted: 19 Feb 2026
Jingwen Shen, Liangzhi Cao, Qingming He, Jiandi Guo, Yuetong Luo, Kaihui Lei and Miao Yin
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Hefei University of Technology, affiliation not provided to SSRN and Southwestern Institute of Physics
Downloads 21 (1,470,786)

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BRep-to-CSG conversion, Monte carlo code, Neural network, pre-segmentation, CFETR

5.

Preliminary Neutronics/Thermal-Hydraulics Design and Analyses of the Helium-Cooled Mixed Bed Breeder Blanket for Cfetr Under 1.5 Gw Fusion Power

Number of pages: 30 Posted: 06 Oct 2022
Qingming He, Tao Dai, Hanlin Shu, Liangzhi Cao, Hongchun Wu, Qixiang Cao and Shen Qu
affiliation not provided to SSRN, Institute of Applied Physics and Computational Mathematics, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, Southwestern Institute of Physics and Southwestern Institute of Physics
Downloads 21 (1,436,435)

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Chinese Fusion Engineering Test Reactor (CFETR), blanket design, mixed bed breeder, neutronics, Thermal-Hydraulics

6.

Development of a Statistical Sampling-Based Uncertainty Analysis Platform for Criticality Safety Analysis

Number of pages: 26 Posted: 20 May 2026
Zhengming Liu, Tiejun Zu, Jin Cai, Jun Zhao, Chao Yu, Liangzhi Cao and Hongchun Wu
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 9 (1,566,597)

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Uncertainty Analysis, Criticality Safety Analysis, Spent Nuclear Fuel storage

7.

Calculation and validation of six-group decay constants and relative yields for 235U thermal and 238U fast fission

Number of pages: 24 Posted: 03 Jul 2026
Zixuan Liu, Tiejun Zu, Liangzhi Cao and Hongchun Wu
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 3

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delayed neutrons, six-group model, 235U thermal fission, 238U fast fission, dynamic rod worth measurement