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Proceedings Papers

Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity

Linyuan Lu, LiHua Guo, Yajuan Zhong, Feng Zhang, Jun Lin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A040, August 8–12, 2022
Paper No: ICONE29-91804
DOI: https://doi.org/10.1115/ICONE29-91804
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Topics: Composite materials, Computer simulation, Fuels, Silicon, Temperature distribution, Thermal conductivity, Thermal resistance, Uranium, Finite element methods, Accidents
Proceedings Papers

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Susumu Yamashita, Shinichiro Uesawa, Hiroyuki Yoshida
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A006, August 8–12, 2022
Paper No: ICONE29-89345
DOI: https://doi.org/10.1115/ICONE29-89345
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Topics: Computer simulation, Cooling, Fuels, Natural convection, Porous materials, Temperature, Accidents, Boiling water reactors, Computational fluid dynamics, Containment vessels
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

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

Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM

Jincheng Wang, Ming Ding
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, V001T03A005, August 4–6, 2021
Paper No: ICONE28-64416
DOI: https://doi.org/10.1115/ICONE28-64416
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Topics: Fuels, Heat conduction, Very high temperature reactors
Proceedings Papers

Application of Finite Difference Jacobian Based Newton-Krylov Method for Coupled Neutronics/Thermal Conduction Problems of Nuclear Reactor

Baokun Liu, Yingjie Wu, Han Zhang, Jiong Guo, Fu Li
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, V003T09A004, August 4–6, 2021
Paper No: ICONE28-64622
DOI: https://doi.org/10.1115/ICONE28-64622
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Topics: Heat conduction, Nonlinear systems, Nuclear reactors, Physics
Proceedings Papers

Inverse Heat Conduction Problem in Estimating NPP Pipeline Performance

Salvatore A. Cancemi, Rosa Lo Frano
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A007, August 4–5, 2020
Paper No: ICONE2020-16129
DOI: https://doi.org/10.1115/ICONE2020-16129
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Topics: Heat conduction, Monitoring systems, Nuclear power stations, Pipelines, Stress, Temperature, Transients (Dynamics), Heat transfer, Pipes, Safety
Proceedings Papers

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Ramon J. M. Pulido, Eric R. Lindgren, Samuel G. Durbin, Alex Salazar
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A031, August 4–5, 2020
Paper No: ICONE2020-16598
DOI: https://doi.org/10.1115/ICONE2020-16598
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Topics: Air flow, Cladding systems (Building), Cooling, Gases, Heat conduction, Model validation, Physics, Spent nuclear fuels, Storage, Temperature
Proceedings Papers

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Libo Qian, Rong Cai, Jinbiao Xiong, Lei Zhong, Yugao Ma
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A038, August 4–5, 2020
Paper No: ICONE2020-16709
DOI: https://doi.org/10.1115/ICONE2020-16709
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Topics: Heat transfer, Pool boiling, Quenching (Metalworking), Transients (Dynamics), Water, Temperature, Film boiling, Zirconium, Thermocouples, Accidents
Proceedings Papers

Development and Verification of PWR Physical and Thermal Coupling Calculation Software

Zhigang Li
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, V001T05A003, August 4–5, 2020
Paper No: ICONE2020-16106
DOI: https://doi.org/10.1115/ICONE2020-16106
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Topics: Computer software, Cylinders, Heat conduction, Pressurized water reactors
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

Experimental Research on Heat Transfer Characteristic of Liquid Lead-Bismuth Eutectic Flowing in Annular Channel

Fengjie Zhu, Junmei Wu, Leitai Shi, G. H. Su
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A023, July 22–26, 2018
Paper No: ICONE26-82042
DOI: https://doi.org/10.1115/ICONE26-82042
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Topics: Heat transfer, Flow (Dynamics), Convection, Coolants, Friction, Pumps, Gas flow, Heat conduction, Mechanical structures, Security
Proceedings Papers

Thermal and Mechanics Analysis Code of the PWR Nuclear Fuel Performance Based on FEM

Yongbo Hui, Bo Zhang, Wenhua Zhang, Di Yun, Peichao Zhai
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A013, July 22–26, 2018
Paper No: ICONE26-81295
DOI: https://doi.org/10.1115/ICONE26-81295
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Topics: Finite element methods, Nuclear fuels, Pressurized water reactors, Deformation, Fuel rods, Coolants, Fuels, Safety, Stress, Temperature
Proceedings Papers

Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method

Xin Li, Ikken Sato, Akifumi Yamaji, Guangtao Duan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A023, July 22–26, 2018
Paper No: ICONE26-82037
DOI: https://doi.org/10.1115/ICONE26-82037
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Topics: Concretes, Ablation (Vaporization technology), Particulate matter, Modeling, Containment, Metals, Accident management, Accidents, Cavities, Computer simulation
Proceedings Papers

Numerical Investigation of Heat Transfer Characteristics of Debris Bed After Severe Accident of SFR Based on 1-D Heat Conduction Model

Mengwei Zhang, Bin Zhang, Jianqiang Shan
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A025, July 22–26, 2018
Paper No: ICONE26-81296
DOI: https://doi.org/10.1115/ICONE26-81296
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Topics: Accidents, Heat conduction, Heat transfer, Sodium fast reactors, China, Disasters, Energy transformation, Errors, Fast neutron reactors, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Paper No: ICONE26-82381
DOI: https://doi.org/10.1115/ICONE26-82381
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

A New Numerical Method for Fuel Temperature Calculation

Jin Xin, Xiaohan Liu, Xiaoyan Wei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A009, July 2–6, 2017
Paper No: ICONE25-66248
DOI: https://doi.org/10.1115/ICONE25-66248
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Topics: Fuels, Numerical analysis, Temperature, Heat conduction, Stability, Fuel rods, Thermal conductivity, Density, Dimensions, Specific heat
Proceedings Papers

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A056, July 2–6, 2017
Paper No: ICONE25-67478
DOI: https://doi.org/10.1115/ICONE25-67478
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Topics: Accidents, Composite materials, Nuclear fuels, Fuels, Temperature, Temperature gradient, Thermal conductivity, Aluminum, Approximation, Cracking (Materials)
Proceedings Papers

Thermal Performance Investigation of Hexagonal Spent Fuel Dry Storage Facilities

Bing Ren, Chenxiao Ni, Yu Dang, Jiazheng Liu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A018, July 2–6, 2017
Paper No: ICONE25-66545
DOI: https://doi.org/10.1115/ICONE25-66545
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Topics: Spent nuclear fuels, Storage, Computational fluid dynamics, Design, Flow (Dynamics), Fuels, Heat, Heat transfer, Temperature, Geometry
Proceedings Papers

Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT)

Guodong Wang, Shengjie Wei, Chenxiao Ni, Di Zhang, Zhe Wang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A100, July 2–6, 2017
Paper No: ICONE25-67560
DOI: https://doi.org/10.1115/ICONE25-67560
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Topics: Containment, Heat, Safety, Three-dimensional models, Shells, Steam, Vessels, Condensation, Evaporation, Water