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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A020, August 8–12, 2022

Paper No: ICONE29-90718

DOI: https://doi.org/10.1115/ICONE29-90718

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Topics: Carburization, Corrosion, High temperature, Oxidation, Stainless steel, Supercritical carbon dioxide, Surface finishing

Proceedings Papers

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Zhongli Han, Ping Lai, Wenhua Zhuang, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A026, August 8–12, 2022

Paper No: ICONE29-90835

DOI: https://doi.org/10.1115/ICONE29-90835

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Topics: Corrosion, Low temperature, Nitriding, Plasmas (Ionized gases), Stainless steel, Wear

Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022

Paper No: ICONE29-92656

DOI: https://doi.org/10.1115/ICONE29-92656

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Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature

Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022

Paper No: ICONE29-90146

DOI: https://doi.org/10.1115/ICONE29-90146

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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)

Proceedings Papers

Research on Laser Welding Process and Deformation Control of Irradiated Sample Holder

Shouyi Luo, Baochao Guo, Dawei Mi

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A034, August 8–12, 2022

Paper No: ICONE29-92535

DOI: https://doi.org/10.1115/ICONE29-92535

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Topics: Deformation, Lap joint welding, Laser welding, Lasers, Stainless steel

Proceedings Papers

Research on Martensitic Stainless Steel Used on the Latch Housing of European Pressurized Reactor (EPR) Control Rod Drive Mechanism (CRDM)

Cuizhu He, Yinhui Lan

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A018, August 8–12, 2022

Paper No: ICONE29-91786

DOI: https://doi.org/10.1115/ICONE29-91786

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Topics: European pressurized reactors, Manufacturing, Pressure, Stainless steel

Proceedings Papers

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Toshihide Takai, Tomohiro Furukawa, Shigeki Watanabe, Noriko S. Ishioka

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, V001T03A002, August 4–6, 2021

Paper No: ICONE28-63277

DOI: https://doi.org/10.1115/ICONE28-63277

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Topics: Alloys, Corrosion, Corrosion resistance, Iron, Oxygen, Stainless steel, Cancer, Fast neutron reactors, Irradiation (Radiation exposure), Mass production

Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

Proceedings Papers

Nanoindentation Test of F321 Austenitic Stainless Steel Under Fe-ion Irradiation

Meidan Liu, Junfeng Nie, Pandong Lin

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A010, August 4–6, 2021

Paper No: ICONE28-63353

DOI: https://doi.org/10.1115/ICONE28-63353

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Topics: Damage, Hardening, Irradiation (Radiation exposure), Nanoindentation, Stainless steel, Temperature

Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel

Shin Kikuchi, Toshihide Takai, Hidemasa Yamano, Kan Sakamoto

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, V003T12A003, August 4–6, 2021

Paper No: ICONE28-62252

DOI: https://doi.org/10.1115/ICONE28-62252

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Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel

Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Koji Morita, Kinya Nakamura

Paper No: ICONE28-63301

DOI: https://doi.org/10.1115/ICONE28-63301

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Topics: Accidents, Melting, Sodium fast reactors, Stainless steel

Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020

Paper No: ICONE2020-16465

DOI: https://doi.org/10.1115/ICONE2020-16465

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Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design

Proceedings Papers

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Richard Hernandez, Nicholas R. Brown, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A041, August 4–5, 2020

Paper No: ICONE2020-16758

DOI: https://doi.org/10.1115/ICONE2020-16758

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Topics: Boron, Critical heat flux, Pool boiling, Testing, Coolants, Design, Shapes, Accidents, Heat flux, Heat transfer

Proceedings Papers

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan

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, V001T01A015, August 4–5, 2020

Paper No: ICONE2020-16634

DOI: https://doi.org/10.1115/ICONE2020-16634

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Topics: Accidents, Computer software, Spent nuclear fuels, Fuels, Fluids, Heavy water reactors, Radiation (Physics), Stainless steel, Steel, Water

Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A019, August 4–5, 2020

Paper No: ICONE2020-16175

DOI: https://doi.org/10.1115/ICONE2020-16175

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Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety

Proceedings Papers

Experimental and Numerical Investigation of Thermal Performance of Synthetic Jet Impingement

Pushpanjay K. Singh, Rohit Kothari, Santosh K. Sahu, Prabhat K. Upadhyay, Shashwat Singh

Paper No: ICONE2020-16775

DOI: https://doi.org/10.1115/ICONE2020-16775

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Topics: Computation, Computer cooling, Computer simulation, Computer software, Diaphragms (Mechanical devices), Diaphragms (Structural), Electromagnetic actuators, Excitation, Flow (Dynamics), Geometry

NARROW

Effect of Surface Machining on Stress Corrosion Cracking Sensitivity of 304L and 316L Austenite Stainless Steel

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

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

Effect of Cr 6+ Concentrations on the Corrosion Behavior of 316LN Stainless Steel in Supercritical Water

Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High-Temperature Supercritical Carbon Dioxide

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Research on Laser Welding Process and Deformation Control of Irradiated Sample Holder

Research on Martensitic Stainless Steel Used on the Latch Housing of European Pressurized Reactor (EPR) Control Rod Drive Mechanism (CRDM)

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Nanoindentation Test of F321 Austenitic Stainless Steel Under Fe-ion Irradiation

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Experimental and Numerical Investigation of Thermal Performance of Synthetic Jet Impingement

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