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Proceedings Papers

Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

Hanyang Lyu, Xiang Wang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A028, August 8–12, 2022

Paper No: ICONE29-92564

DOI: https://doi.org/10.1115/ICONE29-92564

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Topics: Particulate matter, Plasmas (Ionized gases), Simulation

Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022

Paper No: ICONE29-94534

DOI: https://doi.org/10.1115/ICONE29-94534

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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization

Proceedings Papers

Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based on Modelica Language

Xiang Tang, Xiang Wang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A029, August 8–12, 2022

Paper No: ICONE29-92567

DOI: https://doi.org/10.1115/ICONE29-92567

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Topics: Lasers, Simulation

Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022

Paper No: ICONE29-91761

DOI: https://doi.org/10.1115/ICONE29-91761

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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat

Proceedings Papers

Study on the Plutonium Holdup Measurement in Glove-Box

Yimei Cheng, Xiaoming Xu, Honghe Yin, Xinjun Li, Sijia Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A010, August 8–12, 2022

Paper No: ICONE29-90455

DOI: https://doi.org/10.1115/ICONE29-90455

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Topics: Design, Electronics, Measurement systems, Neutrons, Optimization, Sensors, Simulation, Stability

Proceedings Papers

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Yali Qiu, Qin Zeng, Hongli Chen

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A031, August 8–12, 2022

Paper No: ICONE29-92104

DOI: https://doi.org/10.1115/ICONE29-92104

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Topics: Fast neutron reactors, Radioisotopes, Coolants, Volatility, Accidents, Circuits, Computational fluid dynamics, Containment, Hazards, Irradiation (Radiation exposure)

Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022

Paper No: ICONE29-92103

DOI: https://doi.org/10.1115/ICONE29-92103

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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results

Proceedings Papers

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Wang Kai, Ming Jia Zhou, Wei Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A037, August 8–12, 2022

Paper No: ICONE29-91242

DOI: https://doi.org/10.1115/ICONE29-91242

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Topics: Automatic control, Control systems, Cooling, Design, Heating, Heating and cooling, Nuclear power stations, Pressure, Simulation, Temperature

Proceedings Papers

Simulation and Experimental Verification of Boron Diffusion and Mixing in T-Tube Flow

Xinyu Zhang, Bing Dong, Hui Yang, Wentao Zhou, Dezhong Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A038, August 8–12, 2022

Paper No: ICONE29-92341

DOI: https://doi.org/10.1115/ICONE29-92341

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Topics: Boron, Diffusion (Physics), Flow (Dynamics), Fluorescence, Lasers, Simulation

Proceedings Papers

Complementary Simulations to Determine Heat Transfer Coefficients and the Maximum Heat Flux in Multi-Nozzle Spray Cooling Experiments

Yuxuan Du, Satya V. Ravikumar Bandaru, Walter Villanueva

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A002, August 8–12, 2022

Paper No: ICONE29-89086

DOI: https://doi.org/10.1115/ICONE29-89086

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Topics: Computer simulation, Cooling, Engineering simulation, Heat flux, Heat transfer coefficients, Nozzles, Simulation, Sprays, Temperature profiles

Proceedings Papers

Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net

Jinchao Liu, Yaozu Lin, Bijun Chen, Xue Lyu, Jiayi Li, Heng Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A044, August 8–12, 2022

Paper No: ICONE29-92540

DOI: https://doi.org/10.1115/ICONE29-92540

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Topics: Nuclear power, Pumps, Simulation, Stress

Proceedings Papers

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Tianchen Zeng, Yuewen Sun, Peng Cong

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A037, August 8–12, 2022

Paper No: ICONE29-92295

DOI: https://doi.org/10.1115/ICONE29-92295

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Topics: Damage, Graphite, Simulation

Proceedings Papers

Study on Simulation Test of Hydrogen Deflagration Environment In Nuclear Power Plants

Huian Zhan, Shaokun Jiang, Zhiyong Tao, Ning Zhao, Shengnan Yuan

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A040, August 8–12, 2022

Paper No: ICONE29-92375

DOI: https://doi.org/10.1115/ICONE29-92375

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Topics: Accidents, Explosions, Hydrogen, Nuclear power stations, Simulation

Proceedings Papers

Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break

Shripad T. Revankar, Derek W. Kultgen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A004, August 8–12, 2022

Paper No: ICONE29-88852

DOI: https://doi.org/10.1115/ICONE29-88852

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Topics: Accidents, Coolants, Design, Engineering design, Simulation, Test facilities, Very high temperature reactors

Proceedings Papers

Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

Dapeng Xi, Minyun Liu, Shenghui Liu, Jinguang Zang, Yanping Huang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A073, August 8–12, 2022

Paper No: ICONE29-92224

DOI: https://doi.org/10.1115/ICONE29-92224

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Topics: Flow (Dynamics), Fuel rods, Heat transfer, Numerical analysis, Supercritical carbon dioxide, Annulus, Heat transfer coefficients, Heating, Nuclear power, Turbulence

Proceedings Papers

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Xiaoyan Yang, Hongyi Yang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A072, August 8–12, 2022

Paper No: ICONE29-92214

DOI: https://doi.org/10.1115/ICONE29-92214

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Topics: Kalman filters, Design, Nuclear reactors, Porosity, Safety, Simulation, Transients (Dynamics)

Proceedings Papers

A Combined Analytical, Experimental and Simulation Investigation on LBE Natural Circulation Flow and Heat Transmission

Yiquan Zhou, Bo Kuang, Xin Wang, Shuting Wang, Wenjun Hu, Lixia Ren

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A056, August 8–12, 2022

Paper No: ICONE29-93584

DOI: https://doi.org/10.1115/ICONE29-93584

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Topics: Flow (Dynamics), Heat transfer, Simulation

Proceedings Papers

Wall Friction Model to Improve the Stability of Fluid Network Simulation Under Low-Flow Conditions

Dong Shubiao, Zhang Xian, Zhang Xiaoyu, Zhuang Li, Shan Fuchang, Li Fei

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A038, August 8–12, 2022

Paper No: ICONE29-91479

DOI: https://doi.org/10.1115/ICONE29-91479

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Topics: Flow (Dynamics), Fluids, Friction, Simulation, Stability

Proceedings Papers

CFD transient simulation of natural convection characteristics based on detailed core rod bundles model in PLANDTL-DHX experimental device

Xueyuan Zhang, Yuhao Zhang, Jingsong Guo, Daogang Lu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A037, August 8–12, 2022

Paper No: ICONE29-93169

DOI: https://doi.org/10.1115/ICONE29-93169

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Topics: Computational fluid dynamics, Computer simulation, Fuel rods, Natural convection, Simulation, Sodium fast reactors, Transients (Dynamics)

Proceedings Papers

Simulation Study on Start-Up Strategy and Characteristics of Helical Coil Once-Through Steam Generator

Yaxin Gao, Jing Tang, Yisong Hu, Tianming Ruan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A071, August 8–12, 2022

Paper No: ICONE29-92205

DOI: https://doi.org/10.1115/ICONE29-92205

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Topics: Boilers, Flow instability, Simulation

NARROW

Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based on Modelica Language

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Study on the Plutonium Holdup Measurement in Glove-Box

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Simulation and Experimental Verification of Boron Diffusion and Mixing in T-Tube Flow

Complementary Simulations to Determine Heat Transfer Coefficients and the Maximum Heat Flux in Multi-Nozzle Spray Cooling Experiments

Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Study on Simulation Test of Hydrogen Deflagration Environment In Nuclear Power Plants

Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break

Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

A Combined Analytical, Experimental and Simulation Investigation on LBE Natural Circulation Flow and Heat Transmission

Wall Friction Model to Improve the Stability of Fluid Network Simulation Under Low-Flow Conditions

CFD transient simulation of natural convection characteristics based on detailed core rod bundles model in PLANDTL-DHX experimental device

Simulation Study on Start-Up Strategy and Characteristics of Helical Coil Once-Through Steam Generator

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