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Proceedings Papers

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

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Anton Pshenichnikov, Yuji Nagae, Masaki Kurata
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, V003T11A012, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65129
https://doi.org/10.1115/ICONE28-65129
View Paper titled, Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test
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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons
Proceedings Papers

Control Rod Blades Size Reduction Using Underwater Plasma Cutting and its Effects on Boron Carbide Powder Scattering

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Yassine Serbouti, Keisuke Kurihara, Yutaka Kometani, Masatoshi Itagaki, Makoto Tatemura
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, V001T04A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16414
https://doi.org/10.1115/ICONE2020-16414
View Paper titled, Control Rod Blades Size Reduction Using Underwater Plasma Cutting and its Effects on Boron Carbide Powder Scattering
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Topics: Blades, Boron, Electromagnetic scattering, Image segmentation, Nuclear decommissioning, Plasma arc cutting, Radiation scattering, Scattering (Physics), Size reduction (Materials)
Proceedings Papers

Research on Structural Design and Analysis of S-CO 2 Turbine Impeller

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Jun Wu, Can Ma, Chunhui Dai, Zhenxing Zhao, Lu Dai, Zhouyang Liu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81267
https://doi.org/10.1115/ICONE26-81267
View Paper titled, Research on Structural Design and Analysis of S-CO 2 Turbine Impeller
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Topics: Impellers, Structural design, Supercritical carbon dioxide, Turbines, Deformation, Stress, Safety, Blades, Brayton cycle, Carbon
Proceedings Papers

Modular Boiling Water Reactor Concept

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Liao Yi, Wang Cong, Chen Lei
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81196
https://doi.org/10.1115/ICONE26-81196
View Paper titled, Modular Boiling Water Reactor Concept
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Topics: Boiling water reactors, Cycles, Equilibrium (Physics), Blades, Fuels, Manufacturing, Nuclear fuel cycle, Safety, Computer software, Construction
Proceedings Papers

Application of Vorticity Method in Auxiliary Impeller Optimization of HTR-PM Main Helium Fan

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Mo Fei, Zhang Youjie
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82559
https://doi.org/10.1115/ICONE26-82559
View Paper titled, Application of Vorticity Method in Auxiliary Impeller Optimization of HTR-PM Main Helium Fan
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Topics: Helium, Impellers, Optimization, Vorticity, Flow (Dynamics), Design, Engines, Heat, Motors, Axial flow
Proceedings Papers

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

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Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81411
https://doi.org/10.1115/ICONE26-81411
View Paper titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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Topics: Accidents, Fuels, Heating, Manufacturing, Melting, Plasmas (Ionized gases), Blades, Computerized tomography, Electrons, Engineering prototypes
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81991
https://doi.org/10.1115/ICONE26-81991
View Paper titled, Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1
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Topics: Accidents, Blades, Boiling water reactors, Computer software, Fuel rods, Hydrogen production, Nuclear industry, Nuclear reactors, Rods, Simulation
Proceedings Papers

Coupling Dependence of Multiple Operating Parameters on Burnup Credit Calculations for BWR Spent Fuel Assemblies

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Shang-Chien Wu, Der-Sheng Chao, Jenq-Horng Liang
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A073, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82156
https://doi.org/10.1115/ICONE26-82156
View Paper titled, Coupling Dependence of Multiple Operating Parameters on Burnup Credit Calculations for BWR Spent Fuel Assemblies
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Topics: Boiling water reactors, Spent nuclear fuels, Fuels, Blades, Computers, Density, Manufacturing, Neutrons, Polynomials, Storage
Proceedings Papers

Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement

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Ashutosh Kumar Yadav, Parantak Sharma, Avadhesh Kumar Sharma, Mayank Modak, Vishal Nirgude, Santosh K. Sahu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A099, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67537
https://doi.org/10.1115/ICONE25-67537
View Paper titled, Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement
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Topics: Heat transfer, Cooling, Water, Emergency core cooling systems, Heat flux, Impingement cooling, Nozzles, Sprays, Steel, Accidents
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67447
https://doi.org/10.1115/ICONE25-67447
View Paper titled, Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants
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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

Effect of Steam Injection on Last-Stage Blade Temperature of Low Pressure Steam Turbine at Low Volume Flow Condition

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Can Ma, Jun Wu, Yuansheng Lin
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A078, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67090
https://doi.org/10.1115/ICONE25-67090
View Paper titled, Effect of Steam Injection on Last-Stage Blade Temperature of Low Pressure Steam Turbine at Low Volume Flow Condition
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Topics: Blades, Flow (Dynamics), Pressure, Steam, Steam turbines, Temperature, Vibration, Damage, Design, Exhaust systems
Proceedings Papers

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

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Qin Benke, Li Leishi, Bo Hanliang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66463
https://doi.org/10.1115/ICONE25-66463
View Paper titled, Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System
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Topics: Experimental analysis, Hydraulic drive systems, Cylinders, Temperature, Flow (Dynamics), Scram, Blades, Design, Dynamics (Mechanics), Fuels
Proceedings Papers

The Electro Magnetic Compatibility Tests for the AMB System on HTR-10GT

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Zhou Yan, Yan Xunshi, Mo Ni, Yang Guojun, Shi Zhengang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A039, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66350
https://doi.org/10.1115/ICONE25-66350
View Paper titled, The Electro Magnetic Compatibility Tests for the AMB System on HTR-10GT
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Topics: Bearings, Blades, Cables, China, Control rooms, Control systems, Design, Electrical wires, Electromagnetic compatibility, Engineering systems and industry applications
Proceedings Papers

Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology

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Yuta Abe, Ikken Sato, Akihiro Ishimi, Toshio Nakagiri, Yuji Nagae
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, V002T07A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60249
https://doi.org/10.1115/ICONE24-60249
View Paper titled, Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology
Open the PDF for Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology in another window
Topics: Accidents, Boiling water reactors, Design, Heat conduction, Heating, Plasmas (Ionized gases), Blades, Rods, Uncertainty
Proceedings Papers

Parametric Study of the Burnup Credit Criticality Analysis in BWR Fuels

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Shang-Chien Wu, Der-Sheng Chao, Jenq-Horng Liang
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A040, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60592
https://doi.org/10.1115/ICONE24-60592
View Paper titled, Parametric Study of the Burnup Credit Criticality Analysis in BWR Fuels
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Topics: Boiling water reactors, Fuels, Blades, Density, Nuclides, Spent nuclear fuels
Proceedings Papers

Design of a Two-Stage Centrifugal Pump for Nuclear Systems

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Qian Shi, Ping Ye, Gang Zhao
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A069, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60928
https://doi.org/10.1115/ICONE24-60928
View Paper titled, Design of a Two-Stage Centrifugal Pump for Nuclear Systems
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Topics: Centrifugal pumps, Design, Pumps, Flow (Dynamics), Magnetic bearings, Blades, Computer simulation, Condensers (steam plant), Guide vanes, Heat
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30119
https://doi.org/10.1115/ICONE22-30119
View Paper titled, Optimized Surface Treatments and Manufacturing Techniques for Components of Sodium Cooled Fast Reactors
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Topics: Fast neutron reactors, Manufacturing, Sodium, Surface finishing, Shot peening, Laser hardening, Blades, Brittleness, Coatings, Corrosion
Proceedings Papers

Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI

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Zhang Ji-Ge, Zhu Yue
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, V004T10A023, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30587
https://doi.org/10.1115/ICONE22-30587
View Paper titled, Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI
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Topics: Coolants, Fluid structure interaction, Pumps, Stress analysis (Engineering), Impellers, Stress, Blades, Flow (Dynamics), Fracture (Materials), Fracture (Process)
Proceedings Papers

Advancement of Reactor Coolant Pump (RCP) Performance Verification Test in KAERI

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Yun-Je Cho, Yeon-Sik Kim, Seok Cho, Seok Kim, Byoung-Uhn Bae, Heung-June Chung, Young-Jung Youn, Jong-Kuk Park, Hae-Seob Choi, Woo-Jin Jeon, Bok-Deuk Kim, Tae-Soon Kwon, Chul-Hwa Song
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A047, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31075
https://doi.org/10.1115/ICONE22-31075
View Paper titled, Advancement of Reactor Coolant Pump (RCP) Performance Verification Test in KAERI
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Topics: Nuclear reactor coolants, Pumps, Flow (Dynamics), Pressure, Temperature, Transients (Dynamics), Errors, Flowmeters, Fluids, Resonance
Proceedings Papers

Neutronic Analysis and Fuel Cycle Simulation of the MIT Reactor Using MCODE-FM and Experimental Validation

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Kaichao Sun, Michael Ames, Thomas Newton, Jr., Lin-wen Hu
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A018, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16670
https://doi.org/10.1115/ICONE21-16670
View Paper titled, Neutronic Analysis and Fuel Cycle Simulation of the MIT Reactor Using MCODE-FM and Experimental Validation
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Topics: Nuclear fuel cycle, Simulation, Blades, Fuel management, Algorithms, Fuels, Irradiation (Radiation exposure), Neutron flux