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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

Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure

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

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A016, August 4–6, 2021

Paper No: ICONE28-64434

DOI: https://doi.org/10.1115/ICONE28-64434

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Topics: Eigenvalues, Fluids, Pressure

Proceedings Papers

Investigation on Methods for Uncertainty Quantification of Constitutive Models and the Application in BEPU

Qingwen Xiong, Junli Gou, Jianqiang Shan

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A025, July 22–26, 2018

Paper No: ICONE26-81425

DOI: https://doi.org/10.1115/ICONE26-81425

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Topics: Constitutive equations, Uncertainty quantification, Uncertainty, Cladding systems (Building), Design, Safety, Temperature

Proceedings Papers

Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor

Chunming Teng, Bin Zhang, Jianqiang Shan

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A044, July 22–26, 2018

Paper No: ICONE26-82493

DOI: https://doi.org/10.1115/ICONE26-82493

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Topics: Computer simulation, Sodium fast reactors, Particulate matter, Shear strength, Fuels, Accidents, Boiling, Coolants, Cooling, Density

Proceedings Papers

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Fei Chao, Jianqiang Shan, Junli Gou, Pan Wu, Li Ge

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A013, July 22–26, 2018

Paper No: ICONE26-81942

DOI: https://doi.org/10.1115/ICONE26-81942

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Topics: Fluids, Pressure, Water, Gravity (Force), Diffusion (Physics), Flow (Dynamics), Waves, Algorithms, Drag (Fluid dynamics), Pressure gradient

Proceedings Papers

Development of the LMFBR Subchannel Analysis Code ATHAS-LMR and Analysis of Blockage Accident

Peng Du, Jianqiang Shan, Bo Zhang

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A059, July 22–26, 2018

Paper No: ICONE26-81600

DOI: https://doi.org/10.1115/ICONE26-81600

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Topics: Accidents, Liquid metal fast breeder reactors, Flow (Dynamics), Design, Engineering simulation, Fast neutron reactors, Pressurized water reactors, Safety, Simulation, Simulation results

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

Interfacial Drag Force Improvement in Two-Fluid Model

Longxiang Zhu, Jianqiang Shan

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A007, July 22–26, 2018

Paper No: ICONE26-81070

DOI: https://doi.org/10.1115/ICONE26-81070

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Topics: Drag (Fluid dynamics), Fluids, Porosity, Bubbles, Flow (Dynamics), Momentum, Pressure, Vapors

Proceedings Papers

Development of a Thermal-Hydraulic Analysis Code for Helical Coiled Once Through Steam Generator

Jun Huang, Junli Gou, Haifu Ma, Jie Fan, Jianqiang Shan

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A014, July 22–26, 2018

Paper No: ICONE26-81945

DOI: https://doi.org/10.1115/ICONE26-81945

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Topics: Boilers, Heat transfer, Computers, Databases, Fluids, Heat exchangers, Nuclear power stations, Pressurized water reactors

Proceedings Papers

Sub-Channel Analysis of SCWR Assembly With Double-Row Rods

Fei Wang, Jue Yang, Xiangang Fu, Hongbo Li, Yong Zhang, Jianmin Zhang, Jianqiang Shan, Junli Gou, Bo Zhang, Chao Chen

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A007, July 29–August 2, 2013

Paper No: ICONE21-15105

DOI: https://doi.org/10.1115/ICONE21-15105

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Topics: Manufacturing, Rods, Supercritical water reactors, Coolants, Temperature, Fuels, Cladding systems (Building), Computer software, Cycles, Density

Proceedings Papers

LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator

Hongwei Hu, Jianqiang Shan, Junli Gou, Bo Zhang, Haitao Wang, Zijiang Yang

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A094, July 29–August 2, 2013

Paper No: ICONE21-16480

DOI: https://doi.org/10.1115/ICONE21-16480

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Topics: Nuclear power stations, Secondary cells, Flow (Dynamics), Temperature, Accidents, Safety, Cladding systems (Building), Design, Pressure, Pressure drop

Proceedings Papers

The Development and Assessment of a New CHF Correlation for PWR Fuel Assemblies

Ning Bai, Wei Liu, Yuanbing Zhu, Jianqiang Shan, Bo Zhang, Junli Gou, Zhihao Ren, Jinggang Li

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A120, July 29–August 2, 2013

Paper No: ICONE21-16844

DOI: https://doi.org/10.1115/ICONE21-16844

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Topics: Critical heat flux, Fuels, Heart failure, Pressurized water reactors

Proceedings Papers

Safety Analysis of CPR1000 Spent Fuel Pool in Case of Loss of Heat Sink

Haitao Wang, Li Ge, Jianqiang Shan, Junli Gou, Bo Zhang

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A096, July 29–August 2, 2013

Paper No: ICONE21-16503

DOI: https://doi.org/10.1115/ICONE21-16503

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Topics: Heat sinks, Safety, Spent nuclear fuels, Water, Cooling, Boiling, Water temperature, Fuels, Coolants, Cooling systems

Proceedings Papers

Preliminary Safety Analysis of CSR1000

Pan Wu, Junli Gou, Jianqiang Shan, Bo Zhang, Xiang Li

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A055, July 29–August 2, 2013

Paper No: ICONE21-16502

DOI: https://doi.org/10.1115/ICONE21-16502

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Topics: Safety, Accidents, Coolants, Supercritical water reactors, China, Cladding systems (Building), Delays, Design, Flow (Dynamics), Nuclear power

Journal citation

NARROW

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

Numerical Investigation of Melt Fragmentation in Sodium-Cooled Fast Reactor Based on Moving Particle Method

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

The Experimental Study on Critical Heat Flux in Vertical Eccentric Internally Heated Annuli

Experimental Investigation on the Reflooding in a 5×5 Rod Bundle

Study on Developed Mechanism Model With R-134a CHF Experiment in Round Tubes

Application of High Accuracy Numerical Methods for the Natural Circulation Problem

Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure

Investigation on Methods for Uncertainty Quantification of Constitutive Models and the Application in BEPU

Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor

Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem

Development of the LMFBR Subchannel Analysis Code ATHAS-LMR and Analysis of Blockage Accident

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

Interfacial Drag Force Improvement in Two-Fluid Model

Development of a Thermal-Hydraulic Analysis Code for Helical Coiled Once Through Steam Generator

Sub-Channel Analysis of SCWR Assembly With Double-Row Rods

LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator

The Development and Assessment of a New CHF Correlation for PWR Fuel Assemblies

Safety Analysis of CPR1000 Spent Fuel Pool in Case of Loss of Heat Sink

Preliminary Safety Analysis of CSR1000

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