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Proceedings Papers

Alternative Absorber Materials for Control Rods in ALFRED

Hui Guo, Xin Jin, Kuaiyuan Feng, Hanyang Gu

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A001, August 4–6, 2021

Paper No: ICONE28-61123

DOI: https://doi.org/10.1115/ICONE28-61123

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Topics: Fast neutron reactors, Rods

Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

Paper No: ICONE28-64347

DOI: https://doi.org/10.1115/ICONE28-64347

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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

Proceedings Papers

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Jeff Ridgway, Bryant Slater

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A058, August 4–5, 2020

Paper No: ICONE2020-16810

DOI: https://doi.org/10.1115/ICONE2020-16810

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Topics: Fluids, Gravity (Force), Sensors, Vessels, Leakage, Nuclear power, Sensor placement, Simulation, Accuracy and precision, Algorithms

Proceedings Papers

Multi-Group Staggered Tests for Highly Redundant Systems

Shota Soga

Paper No: ICONE2020-16172

DOI: https://doi.org/10.1115/ICONE2020-16172

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Topics: Boiling water reactors, Failure, Notch testing, Reactor protection systems, Redundancy (Engineering), Reliability, Risk, Rods, Safety

Proceedings Papers

High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures

Takahiro Arai, Atsushi Ui, Masahiro Furuya, Riichiro Okawa, Tsugumasa Iiyama, Shota Ueda, Kenetsu Shirakawa, Kazuaki Kito

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A042, August 4–5, 2020

Paper No: ICONE2020-16759

DOI: https://doi.org/10.1115/ICONE2020-16759

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Topics: Boiling, Computerized tomography, Fuel rods, High pressure (Physics), Porosity, Rods, Temperature, Two-phase flow

Proceedings Papers

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

Susumu Yamashita, Hiroyuki Yoshida

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A033, July 22–26, 2018

Paper No: ICONE26-82088

DOI: https://doi.org/10.1115/ICONE26-82088

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Topics: Computer simulation, Fuels, Nuclear reactors, Accidents, Melting, Alpha decay, Cladding systems (Building), Computational fluid dynamics, Fukushima nuclear disaster, Japan, 2011, Heat

Proceedings Papers

Experimental Study on Flow Instability During Gravity-Driven Reflooding

Lili Tong, Dandi Zhang, Liqiang Hou, Xiaoji Wang

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A005, July 22–26, 2018

Paper No: ICONE26-81736

DOI: https://doi.org/10.1115/ICONE26-81736

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Topics: Flow instability, Gravity (Force), Cooling, Steam, Pressure, Water, Accidents, Condensed matter, Coolants, Cylinders

Proceedings Papers

Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1

Heriberto Sánchez-Mora, Carlos Chávez-Mercado, Chris Allison, Judith Hohorst

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A014, July 22–26, 2018

Paper No: ICONE26-81991

DOI: https://doi.org/10.1115/ICONE26-81991

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Topics: Accidents, Blades, Boiling water reactors, Computer software, Fuel rods, Hydrogen production, Nuclear industry, Nuclear reactors, Rods, Simulation

Proceedings Papers

Structural Analysis and Manufacturing of HL-2M Vacuum Vessel and Support Structures

Yuncong Huang, Hong Ran, Zeng Cao, Jilai Hou, Binbin Song

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A006, July 22–26, 2018

Paper No: ICONE26-81273

DOI: https://doi.org/10.1115/ICONE26-81273

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Topics: Manufacturing, Structural analysis, Vacuum, Vessels, Stress, Tokamaks, Construction, Plasmas (Ionized gases), Rods, Dimensions

Proceedings Papers

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Zehua Ma, Yingwei Wu, G. H. Su, Wenxi Tian, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A063, July 22–26, 2018

Paper No: ICONE26-81891

DOI: https://doi.org/10.1115/ICONE26-81891

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Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods

Proceedings Papers

Experimental Research on the Flow Resistance and Heat Transfer Characteristics in Rod Bundle Channel

Zhiqiang Zhu, Chunping Tian, Changqi Yan, Jianjun Wang, Tingting Ren, Zehua Guo

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A075, July 22–26, 2018

Paper No: ICONE26-82195

DOI: https://doi.org/10.1115/ICONE26-82195

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Topics: Flow (Dynamics), Fuel rods, Heat transfer, Reynolds number, Friction, Pipes, Convection, Heat flux, Heating, Rods

Proceedings Papers

Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods

Jikui Li, Tiejun Zu, Liangzhi Cao, HongChun Wu, Qingming He

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A045, July 22–26, 2018

Paper No: ICONE26-82196

DOI: https://doi.org/10.1115/ICONE26-82196

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Topics: Rods, Resonance, Errors, Absorption, Fuels, Cross section (Physics), Neutrons, Nuclear reactors, Nuclides, Physics

Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018

Paper No: ICONE26-82381

DOI: https://doi.org/10.1115/ICONE26-82381

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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods

Proceedings Papers

The Effect of Functional Spacers on the Liquid Film Thickness and Dryout in a BWR Fuel Bundle Model

Christian Bolesch, Lukas Robers, Robert Zboray, Horst-Michael Prasser

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A060, July 22–26, 2018

Paper No: ICONE26-81602

DOI: https://doi.org/10.1115/ICONE26-81602

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Topics: Boiling water reactors, Fuels, Liquid films, Flow (Dynamics), Heating, Design, Rods, Computational fluid dynamics, Computers, Drops

Proceedings Papers

Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals

J. Pacio, M. Daubner, T. Wetzel, I. Di Piazza, M. Tarantino, D. Martelli, M. Angelucci

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A041, July 22–26, 2018

Paper No: ICONE26-82213

DOI: https://doi.org/10.1115/ICONE26-82213

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Topics: Fuel rods, Metals, Flow (Dynamics), Fuels, Temperature, Coolants, Heat transfer, Thermocouples, Wire, Computer simulation

Proceedings Papers

Experimental Activities on Thermal Hydraulics of Heavy Liquid Metal Flow in Typical Elements of Nuclear Power Stations

O. Kashinsky, A. Kurdyumov, P. Lobanov, A. Svetonosov, M. Vorobyev, N. Pribaturin

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A055, July 22–26, 2018

Paper No: ICONE26-82407

DOI: https://doi.org/10.1115/ICONE26-82407

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Topics: Flow (Dynamics), Liquid metals, Nuclear power stations, Thermal hydraulics, Coolants, Temperature, Junctions, Rods, Manufacturing, Computational fluid dynamics

Proceedings Papers

A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Heng Yu, Guan-bo Wang, Da-zhi Qian, Yu-chuan Guo, Bo Hu

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A011, July 22–26, 2018

Paper No: ICONE26-81755

DOI: https://doi.org/10.1115/ICONE26-81755

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Topics: Reliability, Safety, China, Damage, Design, Failure, Probability, Rods, Scram, Transients (Dynamics)

Proceedings Papers

Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants

Zhang Bin, Qiao Su-kai, Hao Qing-jun, Huang Hong-zhi, Ding Ming, Liu Pan

Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A035, July 2–6, 2017

Paper No: ICONE25-67447

DOI: https://doi.org/10.1115/ICONE25-67447

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Topics: Die cutting, Nuclear power stations, Shearing (Deformation), Spent nuclear fuels, Storage, Spent fuel storage, Shear (Mechanics), Bearings, Blades, Extruding

Proceedings Papers

Control System Design for NuScale

Kai Wang, Peiwei Sun

Paper No: ICONE25-66629

DOI: https://doi.org/10.1115/ICONE25-66629

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Topics: Control systems, Design, Coolants, Boilers, Feedwater, Pressure, Temperature, Dynamic models, Flow (Dynamics), Steam

2 3 4 5

NARROW

Alternative Absorber Materials for Control Rods in ALFRED

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Multi-Group Staggered Tests for Highly Redundant Systems

High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

Experimental Study on Flow Instability During Gravity-Driven Reflooding

Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1

Structural Analysis and Manufacturing of HL-2M Vacuum Vessel and Support Structures

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Experimental Research on the Flow Resistance and Heat Transfer Characteristics in Rod Bundle Channel

Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

The Effect of Functional Spacers on the Liquid Film Thickness and Dryout in a BWR Fuel Bundle Model

Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals

Experimental Activities on Thermal Hydraulics of Heavy Liquid Metal Flow in Typical Elements of Nuclear Power Stations

A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants

Control System Design for NuScale

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