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Proceedings Papers

Reliability Analysis of Off-Plant Power for Multi-Units

Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 8–12, 2022

Paper No: ICONE29-91870

DOI: https://doi.org/10.1115/ICONE29-91870

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Topics: Accidents, Emergencies, Event history analysis, Failure, Modeling, Nuclear power, Nuclear power stations, Power grids, Probabilistic safety assessment, Reliability

Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022

Paper No: ICONE29-93082

DOI: https://doi.org/10.1115/ICONE29-93082

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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers

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

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 and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

Zhang Xingzhen, Sun Hui, Zhao Yanjun, Shi Xianzuo

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A056, August 8–12, 2022

Paper No: ICONE29-92834

DOI: https://doi.org/10.1115/ICONE29-92834

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Topics: Excitation, Excitation systems, Nuclear power stations, Simulation, Bridges (Structures), Maintenance, Failure, Nuclear power, Accidents, Construction

Proceedings Papers

A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis

Ming Zhang, Jinggang Li, Xiaohan Liu, Yong Lu, Yanan Zhu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 8–12, 2022

Paper No: ICONE29-88944

DOI: https://doi.org/10.1115/ICONE29-88944

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Topics: Cladding systems (Building), Collapse, Creep, Modeling

Proceedings Papers

Molten Salt Reactor Experiment Simulation Using ThorMOC

Ao Zhang, Ming Dai, Maosong Cheng, Jingen Chen

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A014, August 8–12, 2022

Paper No: ICONE29-90510

DOI: https://doi.org/10.1115/ICONE29-90510

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Topics: Molten salt reactors, Simulation, Modeling, Eigenvalues, Graphics processing units, Neutrons, Nuclear reactors

Proceedings Papers

Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification

Zhang Chunyu, Wang Yang, Deng Yongjun, Song Zifan, Lu Yong

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A017, August 8–12, 2022

Paper No: ICONE29-90557

DOI: https://doi.org/10.1115/ICONE29-90557

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Topics: Finite element model, Fuel rods, Modeling, Pressurized water reactors

Proceedings Papers

Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor

Yutai Cai, Wenzhong Zhou, Long Gu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 8–12, 2022

Paper No: ICONE29-91817

DOI: https://doi.org/10.1115/ICONE29-91817

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Topics: Fast neutron reactors, Fuels, Modeling, Thermomechanics, Uranium

Proceedings Papers

Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

NingYan Sun, ShiChang Liu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 8–12, 2022

Paper No: ICONE29-91727

DOI: https://doi.org/10.1115/ICONE29-91727

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Topics: Fuels, Geometry, Computer-aided design, Modeling, Particulate matter, Monte Carlo methods

Proceedings Papers

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

Yanfei Qiu

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022

Paper No: ICONE29-93201

DOI: https://doi.org/10.1115/ICONE29-93201

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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors

Proceedings Papers

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

Hao Wu, Liangzhi Yu, Fenglei Niu, Jiyuan Tu, Shengyao Jiang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A019, August 8–12, 2022

Paper No: ICONE29-92695

DOI: https://doi.org/10.1115/ICONE29-92695

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Topics: Heat, Machine learning, Modeling, Very high temperature reactors

Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022

Paper No: ICONE29-92364

DOI: https://doi.org/10.1115/ICONE29-92364

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Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)

Proceedings Papers

Study on the Applicability of a Machine-Learning Framework to Improve Modeling for the Stratification Phenomenon

Takuo Oda, Shimpei Okayasu, Nobuhide Hara, Koichi Tanimoto, Ali Haghiri, Xiaowei Xu, Richard Sandberg

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A026, August 8–12, 2022

Paper No: ICONE29-91829

DOI: https://doi.org/10.1115/ICONE29-91829

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Topics: Computer programming, Machine learning, Modeling, Thermal stratification, Turbulence

Proceedings Papers

Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience

Yujia Chen, Weifeng Lv, Zhenyu Jiang, Yonghai Zhou

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A024, August 8–12, 2022

Paper No: ICONE29-92385

DOI: https://doi.org/10.1115/ICONE29-92385

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Topics: Pressurized water reactors, Design, Nuclear power stations, Fluctuations (Physics), Light water reactors, Modeling, Radiation (Physics)

Proceedings Papers

Extension of the IVR Analysis Module in Modeling the Ex-Vessel Water Cooling

Peng Yu, Yuer Zhao, Chen Wang, Xiaoming Yang, Rubing Ma, Yidan Yuan

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A013, August 8–12, 2022

Paper No: ICONE29-91888

DOI: https://doi.org/10.1115/ICONE29-91888

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Topics: Boiling, Cooling, Heat transfer, Modeling, Vessels, Water

Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Xiao Ke

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022

Paper No: ICONE29-90343

DOI: https://doi.org/10.1115/ICONE29-90343

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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback

Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022

Paper No: ICONE29-89568

DOI: https://doi.org/10.1115/ICONE29-89568

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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability

Proceedings Papers

Model Evaluation of Various Thermo-Physical Properties of Nanofluids and ANN Modelling for 10kWe Integrated Reactor

Ling-Yun Zheng, Zhi-Gang Zhang, Xin-Wen Wang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A011, August 8–12, 2022

Paper No: ICONE29-92476

DOI: https://doi.org/10.1115/ICONE29-92476

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Topics: Artificial neural networks, Heat pipes, Modeling, Nanofluids

Proceedings Papers

Modeling and Analysis of Two-Phase Distribution in Large-Scale Separate Heat Pipe

Yiwu Kuang, Xin Jin, Rui Zhuan, Fang Xie, Kaidi Chen, Fei Han, Xiting Chen, Wen Wang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A050, August 8–12, 2022

Paper No: ICONE29-93438

DOI: https://doi.org/10.1115/ICONE29-93438

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Topics: Heat pipes, Modeling, Vapors

Proceedings Papers

Research and Application of Automatic Modeling Technology for Mechanical Analysis of Nuclear Power Pipelines Based on PepS

Xiao Cheng Gong, Xian Jing Jin, Yu Zhang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A013, August 8–12, 2022

Paper No: ICONE29-91928

DOI: https://doi.org/10.1115/ICONE29-91928

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Topics: Modeling, Nuclear power, Pipelines

NARROW

Reliability Analysis of Off-Plant Power for Multi-Units

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

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

Analysis and Simulation in Rotating Rectifier in Brushless Excitation of Nuclear Power Plant

A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis

Molten Salt Reactor Experiment Simulation Using ThorMOC

Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification

Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor

Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Study on the Applicability of a Machine-Learning Framework to Improve Modeling for the Stratification Phenomenon

Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience

Extension of the IVR Analysis Module in Modeling the Ex-Vessel Water Cooling

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Model Evaluation of Various Thermo-Physical Properties of Nanofluids and ANN Modelling for 10kWe Integrated Reactor

Modeling and Analysis of Two-Phase Distribution in Large-Scale Separate Heat Pipe

Research and Application of Automatic Modeling Technology for Mechanical Analysis of Nuclear Power Pipelines Based on PepS

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