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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

Research on Deposition Performance of Fine Particles of Heat Pipe in Small Reactor

Xiaofang Liu, Tao Zhou, Shang Mao, Dong Wei

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 8–12, 2022

Paper No: ICONE29-89180

DOI: https://doi.org/10.1115/ICONE29-89180

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Topics: Flow (Dynamics), Heat pipes, Particulate matter, Temperature

Proceedings Papers

Numerical Simulation of the Effect of Mixed Gas Temperature and Steam Injection Rate on Hydrogen Distribution at Steady State in Small Volumes

Yu Feng, Hongliang Wang, Mingrui Yu, Yidan Yuan

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A021, August 8–12, 2022

Paper No: ICONE29-91506

DOI: https://doi.org/10.1115/ICONE29-91506

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Topics: Accidents, Computer simulation, Hydrogen, Steady state, Steam, Temperature

Proceedings Papers

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022

Paper No: ICONE29-91516

DOI: https://doi.org/10.1115/ICONE29-91516

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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors

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

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Li Jiang, Jianqiang Shan

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A038, August 8–12, 2022

Paper No: ICONE29-93217

DOI: https://doi.org/10.1115/ICONE29-93217

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Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature

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

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

Huaichang Lu, Tao Zhou, Wenbin Liu, Jianyu Tang, Tianyu Gao

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A024, August 8–12, 2022

Paper No: ICONE29-91655

DOI: https://doi.org/10.1115/ICONE29-91655

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Topics: Heat pipes, Heat transfer, Temperature, Thermal resistance, Computer simulation, Computer software, Heat, Heat transfer coefficients, High temperature, Mechanical admittance

Proceedings Papers

U Influence of Non-Condensable Gas in Mobile Heat Pipe Small Reactor on Heat Pipe Heat Transfer Performance

Gao Tianyu, Zhou Tao, Liu Wenbin, Tang Jianyu, Lu Huaichang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A007, August 8–12, 2022

Paper No: ICONE29-89437

DOI: https://doi.org/10.1115/ICONE29-89437

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Topics: Heat pipes, Heat transfer, Lithium, Temperature

Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022

Paper No: ICONE29-89017

DOI: https://doi.org/10.1115/ICONE29-89017

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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis

Proceedings Papers

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A009, August 8–12, 2022

Paper No: ICONE29-89102

DOI: https://doi.org/10.1115/ICONE29-89102

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Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Heat, Oxidation, Melting, Temperature, Leakage, Nuclear decommissioning, Nuclear power stations

Proceedings Papers

Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

Ao Sun, Jie Cheng, Dongbao Zhu, Chunping Tian, Pengzheng Li

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A040, August 8–12, 2022

Paper No: ICONE29-91508

DOI: https://doi.org/10.1115/ICONE29-91508

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Topics: Heat, Thermal stratification, Nuclear power stations, Ocean engineering, Boilers, Cooling, Design, Flow (Dynamics), Heat exchangers, Oceans

Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022

Paper No: ICONE29-92431

DOI: https://doi.org/10.1115/ICONE29-92431

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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design

Proceedings Papers

Research on Influence of Fuel Crud in Reactivity Initiated Accident

Liye Zang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A014, August 8–12, 2022

Paper No: ICONE29-89385

DOI: https://doi.org/10.1115/ICONE29-89385

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Topics: Accidents, Cladding systems (Building), Fuels, Temperature, Thermal conductivity

Proceedings Papers

Development of Quench Analysis Program Based on ARSAC

Lei Zhong, Hongxing Yu, Deqi Chen, Hanzhou Liu, Jian Deng, Dan Wu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A062, August 8–12, 2022

Paper No: ICONE29-92080

DOI: https://doi.org/10.1115/ICONE29-92080

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Topics: Boiling, China, Cladding systems (Building), Film boiling, Fuels, Heat transfer, Nuclear reactors, Oxidation, Quenching (Metalworking), Temperature

Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022

Paper No: ICONE29-89917

DOI: https://doi.org/10.1115/ICONE29-89917

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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission

Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022

Paper No: ICONE29-91707

DOI: https://doi.org/10.1115/ICONE29-91707

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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry

Proceedings Papers

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

Junlin Fang, Qian Sun, Yu Ji, Zishen Ye, Jun Sun, Zhe Sui

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A105, August 8–12, 2022

Paper No: ICONE29-92925

DOI: https://doi.org/10.1115/ICONE29-92925

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Topics: Gas flow, Heat conduction, Heat transfer, Thermal radiation, Convection, Design, Fuel rods, Pressurized water reactors, Radiation (Physics), Sodium fast reactors

Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022

Paper No: ICONE29-92872

DOI: https://doi.org/10.1115/ICONE29-92872

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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)

Proceedings Papers

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A044, August 8–12, 2022

Paper No: ICONE29-91437

DOI: https://doi.org/10.1115/ICONE29-91437

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Topics: Fuels, Heat transfer, Modeling, Physics, Process control, Computational fluid dynamics, Nuclear reactors, Simulation, Convection, Finite element analysis

NARROW

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

Research on Deposition Performance of Fine Particles of Heat Pipe in Small Reactor

Numerical Simulation of the Effect of Mixed Gas Temperature and Steam Injection Rate on Hydrogen Distribution at Steady State in Small Volumes

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

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

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

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

Research on Heat Transfer Performance of Heat Pipe in Mobile Small Reactor

U Influence of Non-Condensable Gas in Mobile Heat Pipe Small Reactor on Heat Pipe Heat Transfer Performance

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Research on Influence of Fuel Crud in Reactivity Initiated Accident

Development of Quench Analysis Program Based on ARSAC

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

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