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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89345
https://doi.org/10.1115/ICONE29-89345
View Paper titled, Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER
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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 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92925
https://doi.org/10.1115/ICONE29-92925
View Paper titled, Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations
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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 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91804
https://doi.org/10.1115/ICONE29-91804
View Paper titled, Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity
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Topics: Composite materials, Computer simulation, Fuels, Silicon, Temperature distribution, Thermal conductivity, Thermal resistance, Uranium, Finite element methods, Accidents
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92224
https://doi.org/10.1115/ICONE29-92224
View Paper titled, Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide
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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 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64416
https://doi.org/10.1115/ICONE28-64416
View Paper titled, Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64622
https://doi.org/10.1115/ICONE28-64622
View Paper titled, Application of Finite Difference Jacobian Based Newton-Krylov Method for Coupled Neutronics/Thermal Conduction Problems of Nuclear Reactor
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Topics: Heat conduction, Nonlinear systems, Nuclear reactors, Physics
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16106
https://doi.org/10.1115/ICONE2020-16106
View Paper titled, Development and Verification of PWR Physical and Thermal Coupling Calculation Software
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16316
https://doi.org/10.1115/ICONE2020-16316
View Paper titled, Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film
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Topics: Coating processes, Coatings, Numerical analysis, Coolants, Cladding systems (Building), Convection, Fuels, Hydrogen, Chemical processes, Computational fluid dynamics
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16129
https://doi.org/10.1115/ICONE2020-16129
View Paper titled, Inverse Heat Conduction Problem in Estimating NPP Pipeline Performance
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16598
https://doi.org/10.1115/ICONE2020-16598
View Paper titled, Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16709
https://doi.org/10.1115/ICONE2020-16709
View Paper titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
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Topics: Heat transfer, Pool boiling, Quenching (Metalworking), Transients (Dynamics), Water, Temperature, Film boiling, Zirconium, Thermocouples, Accidents
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82042
https://doi.org/10.1115/ICONE26-82042
View Paper titled, Experimental Research on Heat Transfer Characteristic of Liquid Lead-Bismuth Eutectic Flowing in Annular Channel
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81295
https://doi.org/10.1115/ICONE26-81295
View Paper titled, Thermal and Mechanics Analysis Code of the PWR Nuclear Fuel Performance Based on FEM
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Topics: Finite element methods, Nuclear fuels, Pressurized water reactors, Deformation, Fuel rods, Coolants, Fuels, Safety, Stress, Temperature
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82037
https://doi.org/10.1115/ICONE26-82037
View Paper titled, Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81296
https://doi.org/10.1115/ICONE26-81296
View Paper titled, Numerical Investigation of Heat Transfer Characteristics of Debris Bed After Severe Accident of SFR Based on 1-D Heat Conduction Model
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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

Investigation of Thermohydraulic Models for Condensation and Boiling in Passive Safety Systems

Frances Viereckl, R. Manthey, C. Schuster, A. Hurtado
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A045, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67327
https://doi.org/10.1115/ICONE25-67327
View Paper titled, Investigation of Thermohydraulic Models for Condensation and Boiling in Passive Safety Systems
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Topics: Boiling, Condensation, Safety, Heat transfer, Heat, Chain, Condensed matter, Condensers (steam plant), Containment, Flow (Dynamics)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67560
https://doi.org/10.1115/ICONE25-67560
View Paper titled, Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT)
Open the PDF for Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT) in another window
Topics: Containment, Heat, Safety, Three-dimensional models, Shells, Steam, Vessels, Condensation, Evaporation, Water
Proceedings Papers

Development of a Sub-Channel Analysis Code “MIDAC” for Core Thermal-Hydraulic Design and Safety Analysis in PWR Plants

Tadakatsu Yodo, Naohiro Takeda, Naoko Iida, Motoko Kawachi
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A107, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67657
https://doi.org/10.1115/ICONE25-67657
View Paper titled, Development of a Sub-Channel Analysis Code “MIDAC” for Core Thermal-Hydraulic Design and Safety Analysis in PWR Plants
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Topics: Design, Pressurized water reactors, Safety, Temperature, Two-phase flow, Cladding systems (Building), Coolants, Fuel rods, Heat conduction, Nucleate boiling
Proceedings Papers

Numerical Simulation of Core Temperature and Melting Process of IVR Core After a Severe Water Loss Accident

Yiqun Liu, Xiaoying Zhang, Jingya Li, Biao Wang, Dekui Zhan, Huiyong Zhang, Junying Xu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66427
https://doi.org/10.1115/ICONE25-66427
View Paper titled, Numerical Simulation of Core Temperature and Melting Process of IVR Core After a Severe Water Loss Accident
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Topics: Accidents, Computer simulation, Melting, Temperature, Water, Fuel rods, Heat transfer, Heat conduction, Pressurized water reactors, Rods