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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

The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

Yuxin Guan, Yingjie Zhan, Shuiyong Wang, Qingwu Wang, Wenxin Ti, Bing Gong

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A028, August 8–12, 2022

Paper No: ICONE29-91966

DOI: https://doi.org/10.1115/ICONE29-91966

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Topics: Graphite, Size effect, Surface roughness, Tensile strength

Proceedings Papers

Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole

Xianghua Xu, Guihong Hu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A046, August 8–12, 2022

Paper No: ICONE29-93045

DOI: https://doi.org/10.1115/ICONE29-93045

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Topics: Accuracy and precision, Boilers, Bridges (Structures), Dimensions, Errors, Heat, Inspection, Manufacturing, Surface roughness

Proceedings Papers

The Experimental Research of Surface Characteristics on CHF for the Downward Facing Surface

Bo Lin, Lei Zhang, Dongshan Wei, Junying Xu, Xiangyu Yun, Huiyong Zhang

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, V003T12A014, August 4–6, 2021

Paper No: ICONE28-64130

DOI: https://doi.org/10.1115/ICONE28-64130

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Topics: Coating processes, Coatings, Critical heat flux, Surface roughness

Proceedings Papers

Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

Arièle Défossez, Eric Dupont, Laurence Grammosenis, Hervé Cordier, Tiphaine Le Morvan

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A012, August 4–5, 2020

Paper No: ICONE2020-16136

DOI: https://doi.org/10.1115/ICONE2020-16136

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Topics: Computational fluid dynamics, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Safety, Wind velocity, Structures, Wind, Power stations, Storms

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

Paper No: ICONE2020-16316

DOI: https://doi.org/10.1115/ICONE2020-16316

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Topics: Coating processes, Coatings, Numerical analysis, Coolants, Cladding systems (Building), Convection, Fuels, Hydrogen, Chemical processes, Computational fluid dynamics

Proceedings Papers

A Study of Seismic Probability Safety Assessment for a Typical Three-Loop Pressurized Water Reactor Nuclear Power Plant

Yuqing Wang, Lingzhi Li, Dongmei Wang

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A040, July 2–6, 2017

Paper No: ICONE25-67793

DOI: https://doi.org/10.1115/ICONE25-67793

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Topics: Nuclear power stations, Pressurized water reactors, Probability, Safety, Earthquake risk, Earthquakes, Accidents, Alternating current (Electricity), Ceilings, Computer software

Proceedings Papers

Numerical Simulation of Crud Effects on the Flow and Heat Transfer Performance in PWR 17×17 Rod Bundles

Bing Ren, Fujun Gan, Yu Dang, Libing Zhu

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A017, July 2–6, 2017

Paper No: ICONE25-66537

DOI: https://doi.org/10.1115/ICONE25-66537

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Topics: Computer simulation, Flow (Dynamics), Fuel rods, Heat transfer, Pressurized water reactors, Cladding systems (Building), Corrosion, Fuels, Risk, Simulation

Proceedings Papers

Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure

Huang Hao, Huang Xiaoming, Xu Guoliang, Fang Lin, Shi Chunyu, Sun Jiawei, Lv Xiangkui

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A040, July 2–6, 2017

Paper No: ICONE25-67735

DOI: https://doi.org/10.1115/ICONE25-67735

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Topics: Gates (Closures), Leakage, Pressure, Rubber, Sealing (Process), Seals, Finite element methods, Accidents, Design, Mechanical behavior

Proceedings Papers

A New Effective Numerical Method for Leakage Rate Prediction of the Metal Gasket Sealing Assembly

Fang Lin, Xu Guoliang, Xiaoming Huang, Huang Hao, Du Yang, Zhu Yiping, Yang Wenjian

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A041, July 2–6, 2017

Paper No: ICONE25-67739

DOI: https://doi.org/10.1115/ICONE25-67739

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Topics: Gaskets, Leakage, Manufacturing, Metals, Numerical analysis, Sealing (Process), Surface roughness, Separation (Technology), Deformation, Channel flow

Proceedings Papers

Natural Convection: A Case of Simple Harmonics

Shoaib Usman

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A094, July 2–6, 2017

Paper No: ICONE25-67500

DOI: https://doi.org/10.1115/ICONE25-67500

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Topics: Natural convection, Surface roughness, Springs, Convection, Dimensionless numbers, Fluids, Gravity (Force), Kinematics, Rayleigh number, Thermal systems

Proceedings Papers

Experimental Study of Helix-Finned Surface for Nucleate Pool Boiling

Kailun Chen, Changqi Yan, Cable Kurwitz, Kun Cheng, Haozhi Bian

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A003, June 26–30, 2016

Paper No: ICONE24-60106

DOI: https://doi.org/10.1115/ICONE24-60106

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Topics: Additive manufacturing, Atmospheric pressure, Boiling, Bubbles, Cavities, Dimensions, Energy dissipation, Fins, Heat, Heat flux

Proceedings Papers

Isothermal Rectangular Roughness Elements in a Rectangular Cavity Heated at Bottom

M. Yousaf, S. Usman

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A067, June 26–30, 2016

Paper No: ICONE24-60908

DOI: https://doi.org/10.1115/ICONE24-60908

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Topics: Cavities, Surface roughness, Algorithms, Fluids, Heat transfer, Lattice Boltzmann methods, Natural convection, Prandtl number, Relaxation (Physics)

Proceedings Papers

A Prediction of the Leakage Through Cracks for Leak Before Break

Jing Zhang, Yingwei Wu, Lei Ding, Hongwei Qiao, Pengzhou Li, Guanghui Su, Suizheng Qiu, Wenxi Tian

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A018, July 7–11, 2014

Paper No: ICONE22-30708

DOI: https://doi.org/10.1115/ICONE22-30708

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Topics: Fracture (Materials), Leakage, Leak-before-break, Flow (Dynamics), Surface roughness, Corners (Structural elements), Displacement, Enthalpy, Fluids, Friction

Proceedings Papers

Small Modular Reactor and Large Nuclear Reactor Fuel Cost Comparison

Christopher P. Pannier, Radek Škoda

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T16A009, July 7–11, 2014

Paper No: ICONE22-30903

DOI: https://doi.org/10.1115/ICONE22-30903

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Topics: Nuclear fuels, Small modular reactors, Fuels, Design, Economics , Construction, Electric power generation, Nuclear construction, Nuclear reactors, Pressurized water reactors

Proceedings Papers

Experimental Study of the Wall Boundary Layer “Heavy Liquid-Metal Coolant – Constructional Material” as Applied to Fast Reactors

Kirill Makhov, Aleksander V. Beznosov, Tatyana Bokova, Artem Shumilkov, Aleksei Chernysh, Alexander Vladimirovich Knyazev

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A031, July 7–11, 2014

Paper No: ICONE22-30269

DOI: https://doi.org/10.1115/ICONE22-30269

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Topics: Boundary layers, Coolants, Fast neutron reactors, Liquid metals, Particulate matter, Microhardness, Oxide coatings, Steel, Turbulence, Alloys

Proceedings Papers

CFD Analysis of the Flow in Crud-Coated Nuclear Rod Bundles

Nicolas Cinosi, Simon P. Walker, Mike Bluck, Raad I. Issa

Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A035, July 7–11, 2014

Paper No: ICONE22-30788

DOI: https://doi.org/10.1115/ICONE22-30788

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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Pressurized water reactors, Rods, Surface roughness, Coolants, Fuels, Heat transfer, Reynolds-averaged Navier–Stokes equations

Proceedings Papers

Modeling and Control Strategy of the China LBE Cooled Fast Reactor

Shoujun Yan, Zhao Wang, Pengfei Wang, Jiashuang Wan, Huawei Fang, Fuyu Zhao

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T13A007, July 7–11, 2014

Paper No: ICONE22-30376

DOI: https://doi.org/10.1115/ICONE22-30376

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Topics: China, Control modeling, Fast neutron reactors, Coolants, Simulation, Control equipment, Feedforward control, Temperature, Control systems, Design

Proceedings Papers

Influence of In-Vessel Melt Progression on Uncertainty of Source Term During a Severe Accident

Hiroto Itoh, Xiaoyu Zheng, Hitoshi Tamaki, Yu Maruyama

Paper No: ICONE22-30012

DOI: https://doi.org/10.1115/ICONE22-30012

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Topics: Accidents, Uncertainty, Vessels, Uncertainty analysis, Radioactive substances, Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Reactor vessels, Surface roughness

Proceedings Papers

Optimized Surface Treatments and Manufacturing Techniques for Components of Sodium Cooled Fast Reactors

Emmanuel Horowitz

Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A004, July 7–11, 2014

Paper No: ICONE22-30119

DOI: https://doi.org/10.1115/ICONE22-30119

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Topics: Fast neutron reactors, Manufacturing, Sodium, Surface finishing, Shot peening, Laser hardening, Blades, Brittleness, Coatings, Corrosion

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NARROW

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

The Effect of Specimen Size and Surface Roughness on Tensile Strength of Nuclear Graphite

Research on Measurement Method of a Device for Measuring the Perpendicularity of Tubesheet Hole

The Experimental Research of Surface Characteristics on CHF for the Downward Facing Surface

Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film

A Study of Seismic Probability Safety Assessment for a Typical Three-Loop Pressurized Water Reactor Nuclear Power Plant

Numerical Simulation of Crud Effects on the Flow and Heat Transfer Performance in PWR 17×17 Rod Bundles

Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure

A New Effective Numerical Method for Leakage Rate Prediction of the Metal Gasket Sealing Assembly

Natural Convection: A Case of Simple Harmonics

Experimental Study of Helix-Finned Surface for Nucleate Pool Boiling

Isothermal Rectangular Roughness Elements in a Rectangular Cavity Heated at Bottom

A Prediction of the Leakage Through Cracks for Leak Before Break

Small Modular Reactor and Large Nuclear Reactor Fuel Cost Comparison

Experimental Study of the Wall Boundary Layer “Heavy Liquid-Metal Coolant – Constructional Material” as Applied to Fast Reactors

CFD Analysis of the Flow in Crud-Coated Nuclear Rod Bundles

Modeling and Control Strategy of the China LBE Cooled Fast Reactor

Influence of In-Vessel Melt Progression on Uncertainty of Source Term During a Severe Accident

Optimized Surface Treatments and Manufacturing Techniques for Components of Sodium Cooled Fast Reactors

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