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Proceedings Papers

Experimental Investigation of Early Response of Hot Water Rapid Blowdown in Separated Pipeline

Xiaoqiang He, Puzhen Gao, Ze Zhang, Jianjun Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A079, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135529
https://doi.org/10.1115/ICONE31-135529
View Paper titled, Experimental Investigation of Early Response of Hot Water Rapid Blowdown in Separated Pipeline
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Topics: Data acquisition, Flashing, Flow (Dynamics), Glass, Hot water, Pipelines, Pipes, Pressure, Rupture, Sensors
Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
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Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
Proceedings Papers

Manufacturing Challenges for Hot Isostatic Pressing Large-Scale Vessels

John Sulley, David Stewart
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136240
https://doi.org/10.1115/ICONE31-136240
View Paper titled, Manufacturing Challenges for Hot Isostatic Pressing Large-Scale Vessels
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Topics: Hot pressing, Manufacturing, Vessels, Failure, Nuclear power stations, Alloy steel, Contamination, Cycles, Design, Fracture toughness
Proceedings Papers

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

Xuejiao Shao, Hai Xie, Yixiong Zhang, Furui Xiong, Xinjun Wang, Kaikai Shi, Mingda Yu, Xuan Huang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93631
https://doi.org/10.1115/ICONE29-93631
View Paper titled, Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control
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Topics: Coolants, Fatigue, Numerical analysis, Stainless steel
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92656
https://doi.org/10.1115/ICONE29-92656
View Paper titled, Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90146
https://doi.org/10.1115/ICONE29-90146
View Paper titled, Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
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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

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

Huanchun Wu, Xinming Meng, Yaolei Han, Yanwei Zhang, Qunjia Peng
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90466
https://doi.org/10.1115/ICONE29-90466
View Paper titled, Effect of Surface Machining on Stress Corrosion Cracking Sensitivity of 304L and 316L Austenite Stainless Steel
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Topics: Deformation, High pressure (Physics), High temperature, Machining, Stainless steel, Stress corrosion cracking, Water
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89917
https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92535
https://doi.org/10.1115/ICONE29-92535
View Paper titled, Research on Laser Welding Process and Deformation Control of Irradiated Sample Holder
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91786
https://doi.org/10.1115/ICONE29-91786
View Paper titled, Research on Martensitic Stainless Steel Used on the Latch Housing of European Pressurized Reactor (EPR) Control Rod Drive Mechanism (CRDM)
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Topics: European pressurized reactors, Manufacturing, Pressure, Stainless steel
Proceedings Papers

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

Zhu Liu, Haozhan Su, Jiachen Long, Shuo Cong, Kai Chen, Xianglong Guo, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90718
https://doi.org/10.1115/ICONE29-90718
View Paper titled, Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High-Temperature Supercritical Carbon Dioxide
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90835
https://doi.org/10.1115/ICONE29-90835
View Paper titled, The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer
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Topics: Corrosion, Low temperature, Nitriding, Plasmas (Ionized gases), Stainless steel, Wear
Proceedings Papers

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

Zhenhe Li, Xi Huang, Zixiong Zhan, Qi Zhao, Junxiong Liu, Lihua Wei, Xiaoyan Li
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89235
https://doi.org/10.1115/ICONE29-89235
View Paper titled, Effect of Cr 6+ Concentrations on the Corrosion Behavior of 316LN Stainless Steel in Supercritical Water
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Topics: Corrosion, Stainless steel, Water, Weight (Mass)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63353
https://doi.org/10.1115/ICONE28-63353
View Paper titled, Nanoindentation Test of F321 Austenitic Stainless Steel Under Fe-ion Irradiation
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Topics: Damage, Hardening, Irradiation (Radiation exposure), Nanoindentation, Stainless steel, Temperature
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63277
https://doi.org/10.1115/ICONE28-63277
View Paper titled, Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth
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Topics: Alloys, Corrosion, Corrosion resistance, Iron, Oxygen, Stainless steel, Cancer, Fast neutron reactors, Irradiation (Radiation exposure), Mass production
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62252
https://doi.org/10.1115/ICONE28-62252
View Paper titled, 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
Open the PDF for 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 in another window
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
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, V003T12A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63301
https://doi.org/10.1115/ICONE28-63301
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64739
https://doi.org/10.1115/ICONE28-64739
View Paper titled, Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments
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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16634
https://doi.org/10.1115/ICONE2020-16634
View Paper titled, FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16175
https://doi.org/10.1115/ICONE2020-16175
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety