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Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022

Paper No: ICONE29-93244

DOI: https://doi.org/10.1115/ICONE29-93244

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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)

Proceedings Papers

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Xiaolin Chen, Simon Li, Songbai Cheng

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022

Paper No: ICONE29-92109

DOI: https://doi.org/10.1115/ICONE29-92109

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Topics: Accidents, Flow (Dynamics), Sodium fast reactors, Three-dimensional models, Transients (Dynamics)

Proceedings Papers

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate

Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A066, August 8–12, 2022

Paper No: ICONE29-93641

DOI: https://doi.org/10.1115/ICONE29-93641

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Topics: Radiation (Physics), Radioactive substances, Safety, Transportation systems, Regulations, Containers, Accidents, Biomedicine, China, Pollution

Proceedings Papers

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A019, August 8–12, 2022

Paper No: ICONE29-91812

DOI: https://doi.org/10.1115/ICONE29-91812

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Topics: Accidents, Fast neutron reactors, Sodium fast reactors

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

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

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

Chong Qin, Kefan Zhang, Wenpei Feng, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A065, August 8–12, 2022

Paper No: ICONE29-92114

DOI: https://doi.org/10.1115/ICONE29-92114

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Topics: Accidents, Boilers, Fast neutron reactors, Pressure, Rupture, Waves

Proceedings Papers

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Bo Lin, Xiangyu Yun, Junying Xu, Dongshan Wei, Huiyong Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A055, August 8–12, 2022

Paper No: ICONE29-93157

DOI: https://doi.org/10.1115/ICONE29-93157

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Topics: Boiling, Coating processes, Coatings, Concretes, Critical heat flux, Glass reinforced plastics, Water, Coolants, Accidents, Construction

Proceedings Papers

Research and Application of Diversity Design of Nuclear Power Plant Based on High-Frequency Occurring Accidents Mitigation

Jiaoshen Xu, Zhengjie Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A065, August 8–12, 2022

Paper No: ICONE29-93635

DOI: https://doi.org/10.1115/ICONE29-93635

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Topics: Accidents, Design, Failure, Nuclear power stations

Proceedings Papers

Research on Radionuclide Diffusion and Verification in the Ocean Under Nuclear Leakage Accidents

Zichao Li, Rongchang Chen, Qingqing Xue, Chen Liu, Zhixia Wang, Tao Zhou

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A005, August 8–12, 2022

Paper No: ICONE29-89256

DOI: https://doi.org/10.1115/ICONE29-89256

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Topics: Accidents, Diffusion (Physics), Leakage, Oceans, Radioisotopes

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

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

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

Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents

Bowen Yang, Jianqiang Shan, Li Ge, Kaidong Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A067, August 8–12, 2022

Paper No: ICONE29-92118

DOI: https://doi.org/10.1115/ICONE29-92118

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Topics: Accidents, Fuels, Performance evaluation, Pressurized water reactors, Safety

Proceedings Papers

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A012, August 8–12, 2022

Paper No: ICONE29-89360

DOI: https://doi.org/10.1115/ICONE29-89360

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Topics: Evaluation methods, Manufacturing, Pressurized water reactors, Safety, Accidents, Computer programming, Design, Engineers, Steam

Proceedings Papers

Study on Reverse Heat Transfer Phenomenon of Steam Generator in Station Blackout Accident

Yu-sheng Liu, Shao-xin Zhuang, Chao Xu, Jian-ping Jing, Si-chao Tan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A078, August 8–12, 2022

Paper No: ICONE29-92316

DOI: https://doi.org/10.1115/ICONE29-92316

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Topics: Accidents, Boilers, Cooling, Heat transfer

Proceedings Papers

Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor

Ang Li, Yuqing Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A027, August 8–12, 2022

Paper No: ICONE29-90347

DOI: https://doi.org/10.1115/ICONE29-90347

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Topics: Accidents, Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Uncertainty

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

Development of Containment Spray Removal Model for Integrated Severe Accident Analysis Code ISAA

Jishen Li

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A020, August 8–12, 2022

Paper No: ICONE29-92721

DOI: https://doi.org/10.1115/ICONE29-92721

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Topics: Accidents, Aerosols, Containment, Sprays

NARROW

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

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

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Research and Application of Diversity Design of Nuclear Power Plant Based on High-Frequency Occurring Accidents Mitigation

Research on Radionuclide Diffusion and Verification in the Ocean Under Nuclear Leakage Accidents

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

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

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

Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Study on Reverse Heat Transfer Phenomenon of Steam Generator in Station Blackout Accident

Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor

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

Development of Containment Spray Removal Model for Integrated Severe Accident Analysis Code ISAA

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