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Proceedings Papers

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A026, August 8–12, 2022

Paper No: ICONE29-92284

DOI: https://doi.org/10.1115/ICONE29-92284

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Topics: Heat, Molten salt reactors, Numerical analysis

Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022

Paper No: ICONE29-90172

DOI: https://doi.org/10.1115/ICONE29-90172

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Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation

Proceedings Papers

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

Xuejiao Shao, Hai Xie, Yixiong Zhang, Furui Xiong, Xinjun Wang, Kaikai Shi, Mingda Yu, Xuan Huang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A064, August 8–12, 2022

Paper No: ICONE29-93631

DOI: https://doi.org/10.1115/ICONE29-93631

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Topics: Coolants, Fatigue, Numerical analysis, Stainless steel

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

The Numerical Method Research for Simulating the SMR Steady-State Primary System Flow and Head Loss

Zhongying Ma, Ge Li, Ting Wang, Jinggang Li

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A007, August 8–12, 2022

Paper No: ICONE29-92987

DOI: https://doi.org/10.1115/ICONE29-92987

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Topics: Flow (Dynamics), Numerical analysis, Steady state, Pressure, Design, Nuclear reactor coolants, Finite element analysis, Finite element methods, Hydraulics

Proceedings Papers

Neutronics Analysis of Fusion Blanket Based on the Spherical Harmonic Function and Finite Element Method

Kang Li, Liangzhi Cao, Jianxin Miao, Haoyu Zhang, Tao Dai

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A099, August 8–12, 2022

Paper No: ICONE29-92622

DOI: https://doi.org/10.1115/ICONE29-92622

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Topics: Finite element methods, Neutrons, Numerical analysis, Simulation

Proceedings Papers

Numerical Analysis on Heat Transfer Characteristics and Buoyancy Effects of Supercritical Pressure Water in Vertical Tube

Yining Lou, Zhen Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A029, August 8–12, 2022

Paper No: ICONE29-92951

DOI: https://doi.org/10.1115/ICONE29-92951

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Topics: Buoyancy, Computer simulation, Heat transfer, Numerical analysis, Pressure, Water

Proceedings Papers

Numerical Analysis of Heat Transfer Enhancement With Spiral Tube in the Passive Containment System

Kai Chen, Ruiqi Wang, Chonghai Huang, Xiao Qi, Xiaoyan Wang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A002, August 8–12, 2022

Paper No: ICONE29-88875

DOI: https://doi.org/10.1115/ICONE29-88875

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Topics: Condensation, Containment systems, Heat transfer, Numerical analysis, Steam, Vapors, Heat, Liquid films, Pressure, Temperature

Proceedings Papers

Numerical Analysis on Pressurizer Liquid Level Characteristic Under Marine Conditions

Sijie Xu, Tianyi Wei, Jinyu Yue, Dongyang Li, Sichao Tan

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A039, August 8–12, 2022

Paper No: ICONE29-92322

DOI: https://doi.org/10.1115/ICONE29-92322

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Topics: Algorithms, Computational fluid dynamics, Computer simulation, Equations of motion, Flow (Dynamics), Numerical analysis, Ocean waves, Pressure, Sloshing, Transients (Dynamics)

Proceedings Papers

Numerical Analysis of Shell-Side Flow Field Characteristics of Condenser in Nuclear Power Plant

Shoubao Dai, Huiqiang Xu, Tengteng Zhan, Dongyang Zhang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A049, August 8–12, 2022

Paper No: ICONE29-92730

DOI: https://doi.org/10.1115/ICONE29-92730

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Topics: Condensers (steam plant), Flow (Dynamics), Nuclear power stations, Numerical analysis, Porous materials, Shells

Proceedings Papers

A Numerical Investigation of the Mixing in the VCT During the Dilution Process

Shengshuai Zhang, Naihua Wang, Xiangyu Chi

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A029, August 8–12, 2022

Paper No: ICONE29-91885

DOI: https://doi.org/10.1115/ICONE29-91885

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Topics: Computer simulation, Control systems, Delays, Density, Flow (Dynamics), Nuclear power plant operations, Numerical analysis, Stability, Water

Proceedings Papers

Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles: Numerical Analysis on Test Results

Zuoyi Kang, Yukihiko Okuda, Akemi Nishida, Haruji Tsubota, Yinsheng Li

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A001, August 8–12, 2022

Paper No: ICONE29-88884

DOI: https://doi.org/10.1115/ICONE29-88884

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Topics: Damage, Impact testing, Numerical analysis, Projectiles, Reinforced concrete

Proceedings Papers

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

Ping Song, Tangtao Feng, Dalin Zhang, Lie Chen, Shaodan Li, Yuansheng Lin, Suizheng Qiu

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A012, August 4–6, 2021

Paper No: ICONE28-64293

DOI: https://doi.org/10.1115/ICONE28-64293

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Topics: Cooling systems, Numerical analysis, Reactor vessels, Sodium fast reactors, Vessels

Proceedings Papers

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A007, August 4–6, 2021

Paper No: ICONE28-64525

DOI: https://doi.org/10.1115/ICONE28-64525

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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants

Proceedings Papers

Application of High Accuracy Numerical Methods for the Natural Circulation Problem

Fei Chao, Longze Li, Wen Yang, Jinrong Qiu, Yun Tai, Jianqiang Shan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A014, August 4–6, 2021

Paper No: ICONE28-64367

DOI: https://doi.org/10.1115/ICONE28-64367

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Topics: Accuracy and precision, Algorithms, Density, Diffusion (Physics), Errors, Fluids, Nuclear power, Numerical analysis, Pressure, Safety

Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A011, August 4–6, 2021

Paper No: ICONE28-64737

DOI: https://doi.org/10.1115/ICONE28-64737

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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles

Proceedings Papers

Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film

Omar S. Al-Yahia, Yacine Addad, Ho Joon Yoon, Sung Oh Cho

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T03A007, August 4–5, 2020

Paper No: ICONE2020-16316

DOI: https://doi.org/10.1115/ICONE2020-16316

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Topics: Coating processes, Coatings, Numerical analysis, Coolants, Cladding systems (Building), Convection, Fuels, Hydrogen, Chemical processes, Computational fluid dynamics

Proceedings Papers

Numerical Analysis of Nuclear Facility Reinforced Concrete Wall and Roof Slab Behavior Under Close-in Explosions

Li Rongpeng, Li Yumin, Sui Chunguang, Jiang Di

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A061, August 4–5, 2020

Paper No: ICONE2020-16957

DOI: https://doi.org/10.1115/ICONE2020-16957

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Topics: Computer simulation, Damage, Explosions, Numerical analysis, Reinforced concrete, Roofs, Slabs

Proceedings Papers

Numerical Analysis on Characteristic of Hydrogen Mixing and Stratification in a Containment Model

Cheng Peng, Lili Tong, Xuewu Cao

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A013, July 22–26, 2018

Paper No: ICONE26-81235

DOI: https://doi.org/10.1115/ICONE26-81235

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Topics: Containment, Hydrogen, Numerical analysis, Design, Helium, Nuclear power stations, Accidents, Buoyancy, China, Computational fluid dynamics

Proceedings Papers

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

Tangtao Feng, Wenxi Tian, Ping Song, Jun Wang, Mingjun Wang, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A049, July 22–26, 2018

Paper No: ICONE26-81738

DOI: https://doi.org/10.1115/ICONE26-81738

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Topics: Fuel rods, Accidents, Computer software, High temperature, Hydrogen, Nuclear fuels, Numerical analysis, Temperature, Transients (Dynamics), Tungsten

2 3 4 5

NARROW

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

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

The Numerical Method Research for Simulating the SMR Steady-State Primary System Flow and Head Loss

Neutronics Analysis of Fusion Blanket Based on the Spherical Harmonic Function and Finite Element Method

Numerical Analysis on Heat Transfer Characteristics and Buoyancy Effects of Supercritical Pressure Water in Vertical Tube

Numerical Analysis of Heat Transfer Enhancement With Spiral Tube in the Passive Containment System

Numerical Analysis on Pressurizer Liquid Level Characteristic Under Marine Conditions

Numerical Analysis of Shell-Side Flow Field Characteristics of Condenser in Nuclear Power Plant

A Numerical Investigation of the Mixing in the VCT During the Dilution Process

Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles: Numerical Analysis on Test Results

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Application of High Accuracy Numerical Methods for the Natural Circulation Problem

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film

Numerical Analysis of Nuclear Facility Reinforced Concrete Wall and Roof Slab Behavior Under Close-in Explosions

Numerical Analysis on Characteristic of Hydrogen Mixing and Stratification in a Containment Model

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

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