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Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A047, August 8–12, 2022

Paper No: ICONE29-92633

DOI: https://doi.org/10.1115/ICONE29-92633

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Topics: Feedwater, Pumps, Rods, Nuclear power stations, Turbines

Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022

Paper No: ICONE29-89461

DOI: https://doi.org/10.1115/ICONE29-89461

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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods

Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022

Paper No: ICONE29-93095

DOI: https://doi.org/10.1115/ICONE29-93095

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Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers

Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022

Paper No: ICONE29-92788

DOI: https://doi.org/10.1115/ICONE29-92788

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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)

Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022

Paper No: ICONE29-91474

DOI: https://doi.org/10.1115/ICONE29-91474

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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling

Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022

Paper No: ICONE29-90296

DOI: https://doi.org/10.1115/ICONE29-90296

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Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods

Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022

Paper No: ICONE29-89917

DOI: https://doi.org/10.1115/ICONE29-89917

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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission

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

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

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

NARROW

Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor

Determination of Control Rod Position by Global Optimization Methods

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

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

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

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

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