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Proceedings Papers

Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR

Yun Cai, TianYa Li, Rui Guo, Tongxian Liu, Qing Li, LingFang Yang, Wenbo Zhao
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A026, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135284
https://doi.org/10.1115/ICONE31-135284
View Paper titled, Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR
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Topics: Computer software, Pressurized water reactors, Spacetime, Neutrons, China, Electricity (Physics), Errors, Nuclear power, Physics, Power stations
Proceedings Papers

Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software

Dipanjan Ray, Martin Lovecký, Jiří Závorka, Radek Škoda
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133182
https://doi.org/10.1115/ICONE31-133182
View Paper titled, Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software
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Topics: Computer software, Diffusion (Physics), Neutrons
Proceedings Papers

Optimal Sensor Placement in Nuclear Power Steam Water System Based on Signed Directed Graph

Tianyang Xing, Chunyang Zeng, Bin Han, Mudi Jiang, Yunze He, Shenghui Liu, Junling Huang, Xiaoliang Zhu
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135960
https://doi.org/10.1115/ICONE31-135960
View Paper titled, Optimal Sensor Placement in Nuclear Power Steam Water System Based on Signed Directed Graph
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Topics: Nuclear power, Nuclear power stations, Pareto optimization, Sensor placement, Steam, Water, Sensors, Flaw detection, Reliability, Computer simulation
Proceedings Papers

Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR

Tamás Varju, Attila Kiss, Csenge Antók, Boglárka Babcsány, Ildikó Boros, Péter Mészáros, Zeno Bertesina, Szabolcs Czifrus
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135760
https://doi.org/10.1115/ICONE31-135760
View Paper titled, Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR
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Topics: Biomedical engineering, Supercritical water reactors, Design, Fuels, Physics, Circuits, Computational fluid dynamics, Computer software, Finite element analysis, Heat
Proceedings Papers

Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor

Jipu Hu, Yuyang Shen, Ruixiang Wang, Kuaiyuan Feng, Lei Lou, Hui Guo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-124442
https://doi.org/10.1115/ICONE31-124442
View Paper titled, Multiphysics Coupling Analysis of an FCM-Fueled Gas-Cooled Microreactor
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Topics: Accidents, Ceramics, Computer software, Coolants, Design, Engineering simulation, Flow (Dynamics), Fluids, Fuels, Graphite
Proceedings Papers

Analysis of the Acceleration Effect of Anderson’s Fixed-Point Acceleration Method in Core Neutronics Calculations

Ping An, Wei Lu, Rui Liu, Zhigang Li, Qifen Tang, Jie Shen
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134930
https://doi.org/10.1115/ICONE31-134930
View Paper titled, Analysis of the Acceleration Effect of Anderson’s Fixed-Point Acceleration Method in Core Neutronics Calculations
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Topics: Boron, Computer software, Cycles, Iterative methods, Neutron flux
Proceedings Papers

OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors

Emir Hanic, Xiang Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A071, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135256
https://doi.org/10.1115/ICONE31-135256
View Paper titled, OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors
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Topics: Fast neutron reactors, Simulation, Alpha decay, Bubbles, Computational fluid dynamics, Computer simulation, Computer software, Cooling, Fluids, Multiphase flow
Proceedings Papers

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

Numerical Study on the Operational Behavior of Catalytic Components With Spherical Packed Bed Structures

Tianming Man, Zehua Guo, Ming Ding, Wenkai Liang
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134633
https://doi.org/10.1115/ICONE31-134633
View Paper titled, Numerical Study on the Operational Behavior of Catalytic Components With Spherical Packed Bed Structures
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Topics: Accidents, Catalysts, Chemical kinetics, Computational fluid dynamics, Computer simulation, Computer software, Containment, Explosions, Flow (Dynamics), Hydrogen
Proceedings Papers

Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment

Boyuan Li, Duo Li, Jianghai Li, Chao Guo, Huasheng Xiong, Shuqiao Zhou, Xiaojin Huang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135382
https://doi.org/10.1115/ICONE31-135382
View Paper titled, Quantifying Software Safety in Nuclear Power Plants: A Framework for Requirements Phase Assessment
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Topics: Computer software, Gates (Closures), Hazards, Nuclear power stations, Safety
Proceedings Papers

Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

Lixin Du, Peng Zhou, Hao Zhang, Yanhua Yang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134794
https://doi.org/10.1115/ICONE31-134794
View Paper titled, Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model
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Topics: Accidents, Circuits, Computer software, Design, Fluids, Heat transfer, Hydraulic drive systems, Nuclear power, Nuclear power stations, Power stations
Proceedings Papers

Development of Two-Dimensional Heat Conduction Model in Subchannel Code Based on OpenFOAM

Zhengyang Dong, Kai Liu, Mingjun Wang, Junmei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134543
https://doi.org/10.1115/ICONE31-134543
View Paper titled, Development of Two-Dimensional Heat Conduction Model in Subchannel Code Based on OpenFOAM
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Topics: Heat conduction, Heat transfer, Fuel rods, Accidents, Errors, Temperature, Temperature distribution, Algorithms, Computational fluid dynamics, Computer software
Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93008
https://doi.org/10.1115/ICONE29-93008
View Paper titled, A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
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Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering
Proceedings Papers

Software Design of High Reliable Decentralized Control System

Shuqiao Zhou, Duo Li, Chao Guo, Fan Chen, Xiaojin Huang
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90717
https://doi.org/10.1115/ICONE29-90717
View Paper titled, Software Design of High Reliable Decentralized Control System
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Topics: Computer software, Control systems, Instrumentation, Nuclear power stations, Reliability, Software design
Proceedings Papers

Application of Recurrent Neural Network in Improving Software Reliability Model of Reactor Protection System

Duo Li, Wenji Zhang, Chao Guo, Shuqiao Zhou
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89440
https://doi.org/10.1115/ICONE29-89440
View Paper titled, Application of Recurrent Neural Network in Improving Software Reliability Model of Reactor Protection System
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Topics: Artificial neural networks, Computer software, Reactor protection systems, Reliability
Proceedings Papers

Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact

Mengyan Song, Di Jiang, Changkai Li, Chaoqi Zhang, Xudong Zhi
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A050, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92808
https://doi.org/10.1115/ICONE29-92808
View Paper titled, Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact
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Topics: Concrete slabs, Reinforced concrete, Slabs, Displacement, Prestressed concrete, Containment, Nuclear power stations, Bonding, Computer software, Concretes
Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92137
https://doi.org/10.1115/ICONE29-92137
View Paper titled, Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap
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Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding
Proceedings Papers

Software of Radioactivity Measurement and Control System for Barreled Nuclear Waste With Segmented Gamma Scanning

Liu Yitang, Shi Rui, Wang Zhou, Wang Zhenchuan, Lan Yunliang, Zhao Wei, Tuo Xianguo
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93603
https://doi.org/10.1115/ICONE29-93603
View Paper titled, Software of Radioactivity Measurement and Control System for Barreled Nuclear Waste With Segmented Gamma Scanning
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Topics: Computer software, Control systems, Radiation measurement, Radioactive wastes
Proceedings Papers

Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor

Xinyue Luo, Daogang Lu, Jiaqi Feng, Yuhao Zhang
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A040, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92323
https://doi.org/10.1115/ICONE29-92323
View Paper titled, Study on the Radiation Heat Transfer Effect of the Covered Gas Space of the Pool Reactor
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Topics: Heat transfer, Radiation (Physics), Sodium fast reactors, Cavities, Fast neutron reactors, Temperature, Vessels, Computational fluid dynamics, Construction, Containers
Proceedings Papers

Application of Self-Developed Advanced Three-Dimensional Simulation Software in Internal Flooding of Nuclear Power Plant

Chenhui Wang, Ran Zhang, Xiaoyun Huang, Chao Wang, Meng Zhao
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93264
https://doi.org/10.1115/ICONE29-93264
View Paper titled, Application of Self-Developed Advanced Three-Dimensional Simulation Software in Internal Flooding of Nuclear Power Plant
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Topics: Computer software, Floods, Nuclear power stations, Safety, Simulation