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Proceedings Papers

Layout Optimization of Self-Powered Neutron Detector for HPR1000

Yao Zhou, Liangzhi Cao, Changyou Zhao, Zhifeng Li, Yuxiang Zhu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91784
https://doi.org/10.1115/ICONE29-91784
View Paper titled, Layout Optimization of Self-Powered Neutron Detector for HPR1000
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Topics: Design, Monitoring systems, Neutrons, Optimization, Sensors
Proceedings Papers

Research on Modeling Method and Eigenvalue Calculation of Single Dispersion of Fuel Particles

Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shenzhi Yu, Yi Liao, Jinrong Qiu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88937
https://doi.org/10.1115/ICONE29-88937
View Paper titled, Research on Modeling Method and Eigenvalue Calculation of Single Dispersion of Fuel Particles
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Topics: Eigenvalues, Fuels, Modeling, Particulate matter
Proceedings Papers

Neutronics Analysis of Fusion Blanket Based on the Spherical Harmonic Function and Finite Element Method

Kang Li, Liangzhi Cao, Jianxin Miao, Haoyu Zhang, Tao Dai
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A099, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92622
https://doi.org/10.1115/ICONE29-92622
View Paper titled, Neutronics Analysis of Fusion Blanket Based on the Spherical Harmonic Function and Finite Element Method
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Topics: Finite element methods, Neutrons, Numerical analysis, Simulation
Proceedings Papers

Analysis of Double Heterogeneous Effect Under Double Dispersion of Fuel and Burnable Poison Particles

Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shengzhi Yu, Qianglong Wang, Jinrong Qiu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91463
https://doi.org/10.1115/ICONE29-91463
View Paper titled, Analysis of Double Heterogeneous Effect Under Double Dispersion of Fuel and Burnable Poison Particles
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Topics: Fuels, Particulate matter
Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.
Paper No: NERS-19-1024
https://doi.org/10.1115/1.4045035
Published Online: February 24, 2020
View Article titled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality
Proceedings Papers

Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods

Jikui Li, Tiejun Zu, Liangzhi Cao, HongChun Wu, Qingming He
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A045, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82196
https://doi.org/10.1115/ICONE26-82196
View Paper titled, Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods
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Topics: Rods, Resonance, Errors, Absorption, Fuels, Cross section (Physics), Neutrons, Nuclear reactors, Nuclides, Physics
Proceedings Papers

Fast Sub-Grid Scale Finite Element Method for the First Order Neutron Transport Equation

Chao Fang, Hongchun Wu, Liangzhi Cao, Yunzhao Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A036, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82008
https://doi.org/10.1115/ICONE26-82008
View Paper titled, Fast Sub-Grid Scale Finite Element Method for the First Order Neutron Transport Equation
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Topics: Finite element methods, Neutrons, Convection, Finite element analysis, Vacuum
Proceedings Papers

Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices

Qian Zhang, Qiang Zhao, Hongchun Wu, Liangzhi Cao, Zheng Zheng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81041
https://doi.org/10.1115/ICONE26-81041
View Paper titled, Multi-Dimensional Heterogeneous Resonance Integral Tables Generated for Embedded Self-Shielding Method Towards Irregular Lattices
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Topics: Resonance, Fuels, Density, Dimensions, Pins (Engineering)
Proceedings Papers

Development and Verification of a New Nuclear Data Processing System NECP-Atlas

Jialong Xu, Tiejun Zu, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A024, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81516
https://doi.org/10.1115/ICONE26-81516
View Paper titled, Development and Verification of a New Nuclear Data Processing System NECP-Atlas
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Topics: Information processing systems, Computational physics, Nuclear engineering
Proceedings Papers

Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000

Fiaz Mahmood, Huasi Hu, Liangzhi Cao
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81388
https://doi.org/10.1115/ICONE26-81388
View Paper titled, Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000
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Topics: Coolants, Corrosion, Cyber-physical systems, Radiation (Physics), Design, Emergencies, Half-life, Matlab, Neutron flux, Pressurized water reactors
Journal Articles

Neutronic Study of Burnable Poison Materials and Their Alternative Configurations in Fully Ceramic Microencapsulated Loaded Pressurized Water Reactor Fuel Assembly

Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu, Chuanqi Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041003.
Paper No: NERS-17-1165
https://doi.org/10.1115/1.4039971
Published Online: September 10, 2018
View Article titled, Neutronic Study of Burnable Poison Materials and Their Alternative Configurations in Fully Ceramic Microencapsulated Loaded Pressurized Water Reactor Fuel Assembly
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Topics: Fuels, Manufacturing, Pressurized water reactors, Temperature, Cycles, Particulate matter
Proceedings Papers

Preliminary Verification of the High-Fidelity Neutronics and Thermal-Hydraulics Coupling System NECP-X/SUBSC

Jun Chen, Liangzhi Cao, Zhouyu Liu, Hongchun Wu, Yijun Zhang
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66511
https://doi.org/10.1115/ICONE25-66511
View Paper titled, Preliminary Verification of the High-Fidelity Neutronics and Thermal-Hydraulics Coupling System NECP-X/SUBSC
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Topics: Thermal hydraulics, Pressurized water reactors, Eigenvalues
Proceedings Papers

Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations

Chenghui Wan, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66191
https://doi.org/10.1115/ICONE25-66191
View Paper titled, Uncertainty Analysis for the Steady-Stated BEAVRS Benchmark Problem at ARO and ARI Situations
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Topics: Uncertainty analysis, Uncertainty, Engineering simulation, Physics, Simulation, Fuels, Sampling methods
Proceedings Papers

Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors

Tianliang Hu, Liangzhi Cao, Hongchun Wu, Kun Zhuang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A051, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67316
https://doi.org/10.1115/ICONE25-67316
View Paper titled, Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors
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Topics: Molten salt reactors, Thermal hydraulics, Transient analysis, Simulation, Transients (Dynamics), Dynamics (Mechanics), Cross section (Physics), Flow (Dynamics), Modeling, Slug flows
Proceedings Papers

Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A012, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66444
https://doi.org/10.1115/ICONE25-66444
View Paper titled, Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly
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Topics: Fuels, Manufacturing, Pressurized water reactors, Boron, Cycles, Nuclear reactors, Safety, Accidents, High temperature, Ceramics
Proceedings Papers

Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method

Jikui Li, Liangzhi Cao, Tiejun Zu, HongChun Wu, Qingming He
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66810
https://doi.org/10.1115/ICONE25-66810
View Paper titled, Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method
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Topics: Ceramics, Fuels, Resonance, Computational methods, Cross section (Physics), Modeling, Particulate matter
Proceedings Papers

Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation

Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Qingming He
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A019, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60401
https://doi.org/10.1115/ICONE24-60401
View Paper titled, Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation
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Topics: Eigenvalues, Physics, Resonance, Uncertainty analysis, Boiling water reactors, Computational methods, Cross section (Physics), Light water reactors, Nuclear fission, Nuclides
Proceedings Papers

Neutron Up-Scattering Effect in Refined Energy Group Structure

Qingming He, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Tiejun Zu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60313
https://doi.org/10.1115/ICONE24-60313
View Paper titled, Neutron Up-Scattering Effect in Refined Energy Group Structure
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Topics: Electromagnetic scattering, Neutrons, Radiation scattering, Scattering (Physics), S-matrix theory, Absorption, Cladding systems (Building), Cross section (Physics), Fuels, Resonance
Proceedings Papers

The Generation of Few-Group Constants for Fast Reactor Analysis

Xianan Du, Liangzhi Cao, Youqi Zheng
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A015, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60331
https://doi.org/10.1115/ICONE24-60331
View Paper titled, The Generation of Few-Group Constants for Fast Reactor Analysis
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Topics: Fast neutron reactors, Collapse, Anisotropy, Cross section (Physics), Electromagnetic scattering, Neutrons, Radiation scattering, Scattering (Physics), Spectra (Spectroscopy)
Proceedings Papers

Effects of Applying the Implicit Particle Fuel Model for Pebble-Bed Reactors

Zhifeng Li, Liangzhi Cao, Hongchun Wu, Chenghui Wan, Tianliang Hu
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A016, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60382
https://doi.org/10.1115/ICONE24-60382
View Paper titled, Effects of Applying the Implicit Particle Fuel Model for Pebble-Bed Reactors
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Topics: Fuels, Particulate matter, Packing (Shipments), Packings (Cushioning), High temperature, Modeling, Monte Carlo methods, Simulation, Very high temperature reactors