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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A001, August 8–12, 2022

Paper No: ICONE29-88937

DOI: https://doi.org/10.1115/ICONE29-88937

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Topics: Eigenvalues, Fuels, Modeling, Particulate matter

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

Paper No: ICONE29-91463

DOI: https://doi.org/10.1115/ICONE29-91463

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.

Paper No: NERS-19-1024

DOI: https://doi.org/10.1115/1.4045035

Published Online: February 24, 2020

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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality

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

Paper No: ICONE26-81388

DOI: https://doi.org/10.1115/ICONE26-81388

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Topics: Coolants, Corrosion, Cyber-physical systems, Radiation (Physics), Design, Emergencies, Half-life, Matlab, Neutron flux, Pressurized water reactors

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

Paper No: ICONE26-82196

DOI: https://doi.org/10.1115/ICONE26-82196

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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

Paper No: ICONE26-82008

DOI: https://doi.org/10.1115/ICONE26-82008

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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

Paper No: ICONE26-81041

DOI: https://doi.org/10.1115/ICONE26-81041

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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

Paper No: ICONE26-81516

DOI: https://doi.org/10.1115/ICONE26-81516

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Topics: Information processing systems, Computational physics, Nuclear engineering

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041003.

Paper No: NERS-17-1165

DOI: https://doi.org/10.1115/1.4039971

Published Online: September 10, 2018

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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

Paper No: ICONE25-66511

DOI: https://doi.org/10.1115/ICONE25-66511

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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

Paper No: ICONE25-66191

DOI: https://doi.org/10.1115/ICONE25-66191

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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

Paper No: ICONE25-67316

DOI: https://doi.org/10.1115/ICONE25-67316

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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

Paper No: ICONE25-66444

DOI: https://doi.org/10.1115/ICONE25-66444

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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

Paper No: ICONE25-66810

DOI: https://doi.org/10.1115/ICONE25-66810

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Topics: Ceramics, Fuels, Resonance, Computational methods, Cross section (Physics), Modeling, Particulate matter

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

Paper No: ICONE24-60313

DOI: https://doi.org/10.1115/ICONE24-60313

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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

Paper No: ICONE24-60331

DOI: https://doi.org/10.1115/ICONE24-60331

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Topics: Fast neutron reactors, Collapse, Anisotropy, Cross section (Physics), Electromagnetic scattering, Neutrons, Radiation scattering, Scattering (Physics), Spectra (Spectroscopy)

Proceedings Papers

Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation

Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Qingming He

Paper No: ICONE24-60401

DOI: https://doi.org/10.1115/ICONE24-60401

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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

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

Paper No: ICONE24-60382

DOI: https://doi.org/10.1115/ICONE24-60382

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Topics: Fuels, Particulate matter, Packing (Shipments), Packings (Cushioning), High temperature, Modeling, Monte Carlo methods, Simulation, Very high temperature reactors

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Journal citation

NARROW

Layout Optimization of Self-Powered Neutron Detector for HPR1000

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

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

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

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

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

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

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

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

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

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

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

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

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

Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

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

Neutron Up-Scattering Effect in Refined Energy Group Structure

The Generation of Few-Group Constants for Fast Reactor Analysis

Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation

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

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