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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

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

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022

Paper No: ICONE29-92642

DOI: https://doi.org/10.1115/ICONE29-92642

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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods

Proceedings Papers

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Weichao Liu, Guoliang Zhang, Changzheng Li, Jin Cao, Shaofang Lin, Xiangang Fu, Lihong Nie, Yongjun Deng

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A060, August 8–12, 2022

Paper No: ICONE29-93004

DOI: https://doi.org/10.1115/ICONE29-93004

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Topics: Cladding systems (Building), Fuel rods, Heat transfer, Heat transfer coefficients, Surface roughness

Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022

Paper No: ICONE29-93417

DOI: https://doi.org/10.1115/ICONE29-93417

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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis

Proceedings Papers

Analysis Method to Predict Grid-to-Rod Fretting Wear of Fuel Rod in Pressurized Water Reactors

Libing Zhu, Shufeng Zhao, Jingya Sun, Shiyin Xu, Fujun Gan, Sirui Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A074, August 8–12, 2022

Paper No: ICONE29-93076

DOI: https://doi.org/10.1115/ICONE29-93076

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Topics: Fuel rods, Pressurized water reactors, Wear

Proceedings Papers

Key Impact Factors Analysis of Fuel Rod End Plug Welding Based on QFD

Yinghong Li, Zhipeng Lv, Changzheng Li, Yuyu Lin, Shaofang Lin, Zhiyi Cai, Yongjun Deng, Lihong Nie

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A064, August 8–12, 2022

Paper No: ICONE29-92803

DOI: https://doi.org/10.1115/ICONE29-92803

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Topics: Fuel rods, Fuels, Reliability, Welding

Proceedings Papers

Study and Development of Irradiation Test Device for Fuel Rods In Research Reactor

Wenbin Zhao, Junping Si, Liang Zhang, Sheng Sun, Wenhua Yang, Shuai Jin, Jin Lei, Hao Liu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A028, August 8–12, 2022

Paper No: ICONE29-90997

DOI: https://doi.org/10.1115/ICONE29-90997

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Topics: Fuel rods, Irradiation (Radiation exposure)

Proceedings Papers

Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification

Zhang Chunyu, Wang Yang, Deng Yongjun, Song Zifan, Lu Yong

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A017, August 8–12, 2022

Paper No: ICONE29-90557

DOI: https://doi.org/10.1115/ICONE29-90557

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Topics: Finite element model, Fuel rods, Modeling, Pressurized water reactors

Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022

Paper No: ICONE29-92788

DOI: https://doi.org/10.1115/ICONE29-92788

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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)

Proceedings Papers

Experimental Study on Dryout and Post-Dryout Heat Transfer in a Three-Rod Bundle With Spacer Grids

Shuo Chen, Tenglong Cong, Yao Xiao, Hanyang Gu

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A055, August 8–12, 2022

Paper No: ICONE29-93567

DOI: https://doi.org/10.1115/ICONE29-93567

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Topics: Fuel rods, Heat transfer

Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022

Paper No: ICONE29-92364

DOI: https://doi.org/10.1115/ICONE29-92364

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Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)

Proceedings Papers

Study on Natural Circulation Flow Resistance Characteristics in a Rod Bundle Channel

Zhiqiang Zhu, Tingting Ren, Shuaijun Li, Chunping Tian, Changqi Yan, Jianjun Wang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A042, August 8–12, 2022

Paper No: ICONE29-93292

DOI: https://doi.org/10.1115/ICONE29-93292

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Topics: Flow (Dynamics), Friction, Fuel rods

Proceedings Papers

Effects of Bubbles Sizes on the Phase Distributions in a Bare Rod Bundle Channel

Sanjia Han, Wei Qi, Shanshan Bu, Zhenzhong Li, Deqi Chen

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A059, August 8–12, 2022

Paper No: ICONE29-93259

DOI: https://doi.org/10.1115/ICONE29-93259

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Topics: Bubbles, Fuel rods, Two-phase flow

Proceedings Papers

Assessment of Multiphase CFD Method for PWR Fuel Rod Bundle

Bing Ren, Fujun Gan, Ping Yang, Jie Zhang

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A017, August 8–12, 2022

Paper No: ICONE29-91637

DOI: https://doi.org/10.1115/ICONE29-91637

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Topics: Boiling, Computational fluid dynamics, Fuel rods, Pressurized water reactors

Proceedings Papers

Numerical Simulation of the Effect of Total Blockage of a Sub-Channel on Two-Phase Flow Through a 5 X 5 Rod Bundle

Ayodeji A. Ala, Sichao Tan

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A044, August 8–12, 2022

Paper No: ICONE29-92544

DOI: https://doi.org/10.1115/ICONE29-92544

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Topics: Computer simulation, Fuel rods, Two-phase flow

Proceedings Papers

Study on Fluid-Structure Interaction of Fuel Rod Bundle With Spacer

Shuang Li, Lanxin Sun

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A052, August 8–12, 2022

Paper No: ICONE29-92891

DOI: https://doi.org/10.1115/ICONE29-92891

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Topics: Fluid structure interaction, Fuel rods

Proceedings Papers

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Xinhai Zhao, Peng Chen, Dongyu He, Ruhao Zhong

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A017, August 8–12, 2022

Paper No: ICONE29-92717

DOI: https://doi.org/10.1115/ICONE29-92717

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Topics: Accidents, Algorithms, Collapse, Dams, Flow (Dynamics), Fuel rods, Geometry, Heat transfer, Melting, Porous materials

Proceedings Papers

Characteristic Behavior of Flow Field in Blocked Fuel Assembly Flow Channel under Steady Flow Condition

Mathew Jayeola, Sichao Tan, Shouxu Qiao, Ayodeji Ala, Fulgence Dione

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A051, August 8–12, 2022

Paper No: ICONE29-91739

DOI: https://doi.org/10.1115/ICONE29-91739

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Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Turbulence

Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022

Paper No: ICONE29-90296

DOI: https://doi.org/10.1115/ICONE29-90296

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Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods

2 3 4 5

NARROW

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Analysis Method to Predict Grid-to-Rod Fretting Wear of Fuel Rod in Pressurized Water Reactors

Key Impact Factors Analysis of Fuel Rod End Plug Welding Based on QFD

Study and Development of Irradiation Test Device for Fuel Rods In Research Reactor

Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Experimental Study on Dryout and Post-Dryout Heat Transfer in a Three-Rod Bundle With Spacer Grids

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Study on Natural Circulation Flow Resistance Characteristics in a Rod Bundle Channel

Effects of Bubbles Sizes on the Phase Distributions in a Bare Rod Bundle Channel

Assessment of Multiphase CFD Method for PWR Fuel Rod Bundle

Numerical Simulation of the Effect of Total Blockage of a Sub-Channel on Two-Phase Flow Through a 5 X 5 Rod Bundle

Study on Fluid-Structure Interaction of Fuel Rod Bundle With Spacer

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Characteristic Behavior of Flow Field in Blocked Fuel Assembly Flow Channel under Steady Flow Condition

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

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