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Proceedings Papers

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Gang Rong, He Zhu, Yi Yang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A017, August 8–12, 2022

Paper No: ICONE29-91753

DOI: https://doi.org/10.1115/ICONE29-91753

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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells

Proceedings Papers

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

Junliang Guo, Huanjun Kong, Miao Gui, Yujiao Peng, Jianqiang Shan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A066, August 8–12, 2022

Paper No: ICONE29-92115

DOI: https://doi.org/10.1115/ICONE29-92115

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Topics: Annulus, Critical heat flux

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

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Mingpeng Chen, Guanhui Xie, Dongyang Li, Sichao Tan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021

Paper No: ICONE28-65770

DOI: https://doi.org/10.1115/ICONE28-65770

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Topics: Boron, Flow measurement, Fluids, Lasers, Reactor vessels, Slug flows, Coolants, Flow (Dynamics), Pressure vessels, Annulus

Proceedings Papers

Quantitative Measurements of Bubbles and Foam Flow Generated From Two-Phase Subcooled Flow Boiling of Seawater in a Vertical Annulus

Yuanjie Li, Syed Waqar Ali Shah, Chin Pan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A025, August 4–6, 2021

Paper No: ICONE28-64748

DOI: https://doi.org/10.1115/ICONE28-64748

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Topics: Annulus, Boiling, Bubbles, Bubbly flow, Flow (Dynamics), Seawater, Subcooling

Proceedings Papers

Flow Pattern Transition Criteria for Upward Two-Phase Flow in Annulus

He Wen, Zhao Chenru, Bo Hanliang

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A009, August 4–5, 2020

Paper No: ICONE2020-16174

DOI: https://doi.org/10.1115/ICONE2020-16174

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Topics: Annulus, Flow (Dynamics), Two-phase flow

Proceedings Papers

Comparison of Drift-Flux Models for Void Fraction Prediction in Sub-Channel of Vertical Rod Bundles

Quanyao Ren, Liangming Pan, Wenxiong Zhou, Tingpu Ye, Hang Liu, Songsong Li

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A027, July 22–26, 2018

Paper No: ICONE26-81435

DOI: https://doi.org/10.1115/ICONE26-81435

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Topics: Fuel rods, Porosity, Annulus, Errors, Pipes, Two-phase flow, Momentum, Nuclear reactors, Physical laws, Safety

Proceedings Papers

On Experimental and Computational Investigation of Heat Transfer Deterioration and Hydraulic Resistance in Annular Channel and SCWR 3-Rod Bundle

Vladislav V. Filonov, Yuliia S. Filonova, Victor G. Razumovskiy, Evgeniy N. Pis'mennyi

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A020, July 22–26, 2018

Paper No: ICONE26-81289

DOI: https://doi.org/10.1115/ICONE26-81289

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Topics: Heat transfer, Supercritical water reactors, Flow (Dynamics), Pressure drop, Heat flux, Annulus, Computational fluid dynamics, Modeling, Pressure, Temperature

Proceedings Papers

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

R. Marinari, M. Tarantino, F. S. Nitti, A. Alemberti, M. Caramello, A. Achilli, R. Ferri, E. Rizzo, F. Giannetti

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A054, July 22–26, 2018

Paper No: ICONE26-82379

DOI: https://doi.org/10.1115/ICONE26-82379

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Topics: Gases, Heat, Coolants, Safety, Design, Computer simulation, Freezing, Liquid metals, Solidification, Accidents

Proceedings Papers

Analysis on Hydrogen Risk Induced by Containment Leakage

Peiwen Gu, Guobao Shi, Likai Fang, Jiayun Wang

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A013, July 2–6, 2017

Paper No: ICONE25-67012

DOI: https://doi.org/10.1115/ICONE25-67012

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Topics: Containment, Hydrogen, Leakage, Risk, Accidents, Annulus, Condensation, Explosions, Failure, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

Large Scale PWR Passive Containment Cooling System Wind Tunnel Test

Pan Xinxin, Huang Jingyu, Song Chunjing

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A033, July 2–6, 2017

Paper No: ICONE25-66320

DOI: https://doi.org/10.1115/ICONE25-66320

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Topics: Containment, Cooling systems, Pressurized water reactors, Wind tunnels, Air flow, Wind, Flow (Dynamics), Annulus, Pressure, Wind velocity

Proceedings Papers

Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium

Dalin Zhang, Jing Chen, Ping Song, Shibao Wang, Xin'an Wang, Linfeng Li, Suizheng Qiu, G. H. Su

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A053, July 2–6, 2017

Paper No: ICONE25-67865

DOI: https://doi.org/10.1115/ICONE25-67865

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Topics: Boiling, Heat transfer, Liquid metals, Sodium, Sodium fast reactors, Annulus, Critical heat flux, Friction, Coolants, Design

Proceedings Papers

Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System

Pan Xinxin, Huang Jingyu, Song Chunjing

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A011, July 2–6, 2017

Paper No: ICONE25-66321

DOI: https://doi.org/10.1115/ICONE25-66321

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Topics: Containment, Cooling systems, Simulation, Testing performance, Air flow, Wind, Computational fluid dynamics, Wind tunnels, Annulus, Wind velocity

Proceedings Papers

Vibration Effects on Bubbly Flow Structure in an Annulus

Xiu Xiao, Qingzi Zhu, Guanyi Wang, Shao-Wen Chen, Mamoru Ishii, Yajun Zhang

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A057, June 26–30, 2016

Paper No: ICONE24-60735

DOI: https://doi.org/10.1115/ICONE24-60735

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Topics: Annulus, Bubbly flow, Vibration, Porosity, Two-phase flow, Cycles, Electrical conductivity, Information Analysis Centers, Probes, Rotation

Proceedings Papers

New Models of Droplet Deposition and Entrainment for Prediction of Dryout in Uniform and Non-Uniform Heated Annuli

H. B. Zhang, G. F. Hewitt

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A068, June 26–30, 2016

Paper No: ICONE24-60903

DOI: https://doi.org/10.1115/ICONE24-60903

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Topics: Annulus, Drops, Flow (Dynamics), Heat flux, Heating, Modeling

Proceedings Papers

Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors

Songyang Li, Dingqu Wang, Wenli Guo, Yueyuan Jiang

Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A021, June 26–30, 2016

Paper No: ICONE24-60505

DOI: https://doi.org/10.1115/ICONE24-60505

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Topics: Fuels, Water, Design, Manufacturing, Nuclear fuels, Power density, Temperature, Annulus, Cutting, Geometry

Proceedings Papers

Thermal Mixing Behavior in the Annulus of Co-Axial Double-Walled Piping in HTGR

Daisuke Tochio, Yusuke Fujiwara, Masato Ono, Masanori Shinohara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A034, June 26–30, 2016

Paper No: ICONE24-60843

DOI: https://doi.org/10.1115/ICONE24-60843

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Topics: Annulus, Pipes, Very high temperature reactors, Helium, Temperature, Flow (Dynamics), Coolants, Cooling systems, Gas flow, Gases

Proceedings Papers

Experimental Measurements and CFD Evaluation of the Onset Flow Boiling at Low Pressure and High Subcooling Flow of R-11 Within Vertical Annulus

Y. Bouaichaoui, R. Kibboua, M. Matkovič

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A045, July 7–11, 2014

Paper No: ICONE22-31028

DOI: https://doi.org/10.1115/ICONE22-31028

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Topics: Annulus, Boiling, Computational fluid dynamics, Flow (Dynamics), Pressure, Subcooling, Boundary-value problems, Computational methods, Computers, Critical heat flux

Proceedings Papers

An Experimental Study on the Critical Heat Flux for Low Flow of Water in Bilaterally Heated Vertical Annuli Under Low Pressure Conditions

Lei Zhou, Guangxu Liu, Yuanfeng Zan, Xiao Yan

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A035, July 7–11, 2014

Paper No: ICONE22-30931

DOI: https://doi.org/10.1115/ICONE22-30931

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Topics: Annulus, Critical heat flux, Flow (Dynamics), Pressure, Water, Accidents, Experimental design, Light water reactors, Nuclear design, Nuclear engineering

Proceedings Papers

Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus

Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Guanghui Su

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A025, July 7–11, 2014

Paper No: ICONE22-30244

DOI: https://doi.org/10.1115/ICONE22-30244

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Topics: Annulus, Sodium, Flow (Dynamics), Fluids, Heat flux, Temperature, Friction, Heat transfer coefficients, Laminar flow, Turbulence

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NARROW

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

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

Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Quantitative Measurements of Bubbles and Foam Flow Generated From Two-Phase Subcooled Flow Boiling of Seawater in a Vertical Annulus

Flow Pattern Transition Criteria for Upward Two-Phase Flow in Annulus

Comparison of Drift-Flux Models for Void Fraction Prediction in Sub-Channel of Vertical Rod Bundles

On Experimental and Computational Investigation of Heat Transfer Deterioration and Hydraulic Resistance in Annular Channel and SCWR 3-Rod Bundle

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

Analysis on Hydrogen Risk Induced by Containment Leakage

Large Scale PWR Passive Containment Cooling System Wind Tunnel Test

Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium

Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System

Vibration Effects on Bubbly Flow Structure in an Annulus

New Models of Droplet Deposition and Entrainment for Prediction of Dryout in Uniform and Non-Uniform Heated Annuli

Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors

Thermal Mixing Behavior in the Annulus of Co-Axial Double-Walled Piping in HTGR

Experimental Measurements and CFD Evaluation of the Onset Flow Boiling at Low Pressure and High Subcooling Flow of R-11 Within Vertical Annulus

An Experimental Study on the Critical Heat Flux for Low Flow of Water in Bilaterally Heated Vertical Annuli Under Low Pressure Conditions

Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus

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