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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