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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, V001T03A008, August 4–5, 2020

Paper No: ICONE2020-16340

DOI: https://doi.org/10.1115/ICONE2020-16340

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Topics: Computational fluid dynamics, Discrete element methods, Engineering simulation, Graphite, Particle collisions, Simulation, Particulate matter, Flow (Dynamics), Collisions (Physics), Air flow

Journal Articles

Analysis of Clumped-Pebble Shape on Thermal Radiation and Conduction in Nuclear Beds by Subcell Radiation Model

Hao Wu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

J. Heat Transfer. March 2020, 142(3): 032101.

Paper No: HT-19-1405

DOI: https://doi.org/10.1115/1.4045685

Published Online: January 13, 2020

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Topics: Emissivity, Heat conduction, Particulate matter, Radiation (Physics), Shapes, Temperature, Thermal conductivity, Thermal radiation, Heat transfer, Flow (Dynamics)

Journal Articles

A New Uniform Continuum Modeling of Conductive and Radiative Heat Transfer in Nuclear Pebble Bed

Hao Wu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

J. Heat Transfer. August 2019, 141(8): 082001.

Paper No: HT-19-1057

DOI: https://doi.org/10.1115/1.4043852

Published Online: June 17, 2019

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Topics: Heat conduction, Modeling, Packing (Shipments), Packings (Cushioning), Particulate matter, Radiation (Physics), Radiative heat transfer, Thermal conductivity, Discrete element methods, Density

Proceedings Papers

Numerical Study of Effect of Contact Angles on Flow Boiling Employing Thermal LBM Simulation

Tingzhen Sun, Qian Liu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A017, July 22–26, 2018

Paper No: ICONE26-81569

DOI: https://doi.org/10.1115/ICONE26-81569

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Topics: Boiling, Flow (Dynamics), Simulation, Bubbles, Lattice Boltzmann methods, Shapes

Journal Articles

Particle-Scale Investigation of Thermal Radiation in Nuclear Packed Pebble Beds

Hao Wu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

J. Heat Transfer. September 2018, 140(9): 092002.

Paper No: HT-17-1686

DOI: https://doi.org/10.1115/1.4039913

Published Online: May 22, 2018

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Topics: Heat transfer, Particulate matter, Porosity, Radiation (Physics), Thermal radiation, Emissivity, Alpha particles, Simulation, Thermal conductivity

Journal Articles

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Yongyong Wu, Cheng Ren, Rui Li, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031006.

Paper No: NERS-17-1109

DOI: https://doi.org/10.1115/1.4039035

Published Online: May 16, 2018

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Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity

Journal Articles

Modeling Effective Thermal Conductivity of Thermal Radiation for Nuclear Packed Pebble Beds

Hao Wu, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

J. Heat Transfer. April 2018, 140(4): 042701.

Paper No: HT-17-1184

DOI: https://doi.org/10.1115/1.4038231

Published Online: December 27, 2017

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Topics: Heat transfer, Modeling, Packings (Cushioning), Particulate matter, Radiation (Physics), Temperature, Thermal conductivity, Thermal radiation, Alpha particles, High temperature

Proceedings Papers

Modeling the Irradiation Swelling of UO 2 at the Fuel Pellet Rim

Lijun Gao, Bingde Chen, Zhong Xiao, Shengyao Jiang, Jiyang Yu

Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A001, July 29–August 2, 2013

Paper No: ICONE21-15009

DOI: https://doi.org/10.1115/ICONE21-15009

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Topics: Fuels, Irradiation (Radiation exposure), Modeling, Nuclear fission, Density, Porosity, Fittings, Log normal distribution

Proceedings Papers

Studies on Source Effect in Experimental Design for Passive Cooling in Large Cavities Under LOCA conditions

Shengqiang Li, Yin Xiong, Yalei Hao, Hongyu Zhu, Shengyao Jiang

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A010, July 29–August 2, 2013

Paper No: ICONE21-15139

DOI: https://doi.org/10.1115/ICONE21-15139

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Topics: Cavities, Cooling, Experimental design, Design, Containment, Flow (Dynamics), Simulation, Transients (Dynamics), Accidents, Coolants

Proceedings Papers

Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

Beibei Feng, Darong Chen, Xingtuan Yang, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A016, July 29–August 2, 2013

Paper No: ICONE21-15427

DOI: https://doi.org/10.1115/ICONE21-15427

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Topics: Drag (Fluid dynamics), Flow (Dynamics), Noise control, Nuclear reactors, Cooling, Helium, Noise (Sound), Water, Engineering systems and industry applications, Heat transfer

Proceedings Papers

Elementary Analysis for the Decommissioning Schedule of High Temperature Reactors

Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A006, July 29–August 2, 2013

Paper No: ICONE21-15287

DOI: https://doi.org/10.1115/ICONE21-15287

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Topics: High temperature, Nuclear decommissioning, Safety

Proceedings Papers

Theoretical Analysis of a Natural Circulation System Under Rolling Condition Based on RELAP5/MOD3.3 Code

Haibo Lian, Hongye Zhu, Xingtuan Yang, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A020, July 29–August 2, 2013

Paper No: ICONE21-15441

DOI: https://doi.org/10.1115/ICONE21-15441

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Topics: Circuits, Flow (Dynamics), Heat, Ships, Symmetry (Physics), Theoretical analysis

Proceedings Papers

Elementary Analysis of the Quality Assurance for Probabilistic Safety Analysis

Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A007, July 29–August 2, 2013

Paper No: ICONE21-15288

DOI: https://doi.org/10.1115/ICONE21-15288

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Topics: Probabilistic safety assessment, Quality control, Accounting, Nuclear power stations, Probabilistic risk assessment, Project management, Regulations, Security, Uncertainty

Proceedings Papers

Experimental and Numerical Study on Natural Circulation Under Inclined Condition

Hongye Zhu, Xingtuan Yang, Haibo Lian, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A021, July 29–August 2, 2013

Paper No: ICONE21-15444

DOI: https://doi.org/10.1115/ICONE21-15444

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Topics: Accidents, Circuits, Computational fluid dynamics, Design, Flow (Dynamics), Numerical analysis, Thermal hydraulics

Proceedings Papers

Transient Analysis of Active Residual Heat Removal Process for HTR-PM

Hongye Zhu, Xingtuan Yang, Huaiming Ju, Shengyao Jiang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A022, July 29–August 2, 2013

Paper No: ICONE21-15448

DOI: https://doi.org/10.1115/ICONE21-15448

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Topics: Heat, Transient analysis, Boilers, Helium, Coolants, Shock (Mechanics), Boiling, Flow (Dynamics), Stress, China

Journal citation

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Supplemental Material

PTV Measurement of Whole-Field Monolayer Pebble Flow in Two-Dimensional Silo

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

Comparative Study on the Numerical Methods for View Factor Computation for Packed Pebble Beds: Back Propagation Neural Network Methods Versus Monte Carlo Methods

Numerical Study on Discharging Characteristics of Pebble Cluster Flow in Pebble Bed

Experimental Study on Gravity Driven Discharging of Quasi-Two-Dimensional Pebble Bed Based on Mathematical Morphology

CFD-DEM Simulations of Graphite Particle Collisions in Opposed Jet Mill

Analysis of Clumped-Pebble Shape on Thermal Radiation and Conduction in Nuclear Beds by Subcell Radiation Model

A New Uniform Continuum Modeling of Conductive and Radiative Heat Transfer in Nuclear Pebble Bed

Numerical Study of Effect of Contact Angles on Flow Boiling Employing Thermal LBM Simulation

Particle-Scale Investigation of Thermal Radiation in Nuclear Packed Pebble Beds

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Modeling Effective Thermal Conductivity of Thermal Radiation for Nuclear Packed Pebble Beds

Modeling the Irradiation Swelling of UO 2 at the Fuel Pellet Rim

Studies on Source Effect in Experimental Design for Passive Cooling in Large Cavities Under LOCA conditions

Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

Elementary Analysis for the Decommissioning Schedule of High Temperature Reactors

Theoretical Analysis of a Natural Circulation System Under Rolling Condition Based on RELAP5/MOD3.3 Code

Elementary Analysis of the Quality Assurance for Probabilistic Safety Analysis

Experimental and Numerical Study on Natural Circulation Under Inclined Condition

Transient Analysis of Active Residual Heat Removal Process for HTR-PM

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