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Proceedings Papers

Research on Qualification Requirements for Electrical and Instrumentation Equipment Based on Safety Classification

Qian Sun, Jiahao Liu
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136504
https://doi.org/10.1115/ICONE31-136504
View Paper titled, Research on Qualification Requirements for Electrical and Instrumentation Equipment Based on Safety Classification
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Topics: Design, Equipment qualification, Instrumentation, Safety
Proceedings Papers

Risk Assessment of the Integration of a Large-Scale Hydrogen Cogeneration Facility Into a VVER Power Plant

Eduard Diaz-Pescador, Marco Viebach, Florian Gamaleja, Antonio Hurtado
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130640
https://doi.org/10.1115/ICONE31-130640
View Paper titled, Risk Assessment of the Integration of a Large-Scale Hydrogen Cogeneration Facility Into a VVER Power Plant
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Topics: Combined heat and power, Hydrogen, Power stations, Risk assessment, Safety
Proceedings Papers

Progress in Isolation Analysis and Experimental Research of HPR1000 Nuclear Island Plant

Chencheng Shi, Jian Chen, Xiaoying Sun, Xiaoyi Yang, Hehuan Ren
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A044, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136330
https://doi.org/10.1115/ICONE31-136330
View Paper titled, Progress in Isolation Analysis and Experimental Research of HPR1000 Nuclear Island Plant
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Topics: Aircraft, China, Design, Earthquakes, Economics , Nuclear engineering, Nuclear power stations, Safety, Soil
Proceedings Papers

Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components

Antony Hurst, Louis Chang, Mike Nielsen, Sam Holcroft
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136097
https://doi.org/10.1115/ICONE31-136097
View Paper titled, Development of Requirements for Demonstrating Structural Integrity of the Highest Reliability Components
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Topics: Design, Reliability, Safety, Failure, Nuclear power, Jets, Missiles, Pressure, Classification, Construction
Proceedings Papers

NPP Modification Opportunity by Hydrogen Technologies Implementation: Assessment in Frame of the Euratom Project NPHyCo

Martin Kykal, Oleksandr Mazurok, Martin Glueckler, Cecilia Herrero Moriana, Canet Serin, Vasyl Korolchuk
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A042, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136129
https://doi.org/10.1115/ICONE31-136129
View Paper titled, NPP Modification Opportunity by Hydrogen Technologies Implementation: Assessment in Frame of the Euratom Project NPHyCo
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Topics: Hydrogen, Nuclear power stations, Economics , Nuclear power, Carbon, Combined heat and power, Construction, Fossil fuels, Hydrogen production, Innovation
Proceedings Papers

Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands

Guang Du, Danfeng Zhao, Daping Lin, Xiaoxia Chen
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135047
https://doi.org/10.1115/ICONE31-135047
View Paper titled, Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands
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Topics: Floods, Nuclear power stations, Design, Hazards, Safety, Water, Computational methods, Engineering design, Evaluation methods, Nuclear power
Proceedings Papers

Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor

Jianhui Wu, Chunyan Zou, Chenggang Yu, Hongkai Zhao, Yong Cui, Haotian Bao, Xiangzhou Cai, Jingen Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134819
https://doi.org/10.1115/ICONE31-134819
View Paper titled, Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor
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Topics: Molten salt reactors, Nuclear fuel cycle, Safety, Temperature, Transients (Dynamics), Uranium
Proceedings Papers

TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme

Junxiao Zhang, Songyang Liu, Junhao Xie, Tian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136107
https://doi.org/10.1115/ICONE31-136107
View Paper titled, TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme
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Topics: Fuels, High temperature, Particulate matter, Nuclear fission, Temperature, Very high temperature reactors, Diffusion (Physics), Failure, Flow (Dynamics), Safety
Proceedings Papers

A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors

Yue Song, Heng Xie, Meng Lv
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A034, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135005
https://doi.org/10.1115/ICONE31-135005
View Paper titled, A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors
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Topics: Corrosion, Fuels, Irradiation (Radiation exposure), Safety, Temperature effects
Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Shichang Liu, Zhenyu Wang, Rui Che
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134661
https://doi.org/10.1115/ICONE31-134661
View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
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Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Proceedings Papers

Effects of Magnetic Ordering on the Ground-State Energy of Plutonium Dioxide: A Study Using Adiabatic Connection Fluctuation-Dissipation Theory

Hiroki Nakamura, Masahiko Machida
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A026, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134660
https://doi.org/10.1115/ICONE31-134660
View Paper titled, Effects of Magnetic Ordering on the Ground-State Energy of Plutonium Dioxide: A Study Using Adiabatic Connection Fluctuation-Dissipation Theory
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Topics: Energy dissipation, Ground state, Nuclear fuels, Approximation, Computer simulation, Density functional theory, High temperature, Magnetism, Safety
Proceedings Papers

Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM

Qianye Yang, Nan Gui, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131880
https://doi.org/10.1115/ICONE31-131880
View Paper titled, Research on Fuel Pebble Modeling Methods Comparison and Eigenvalue Analysis of the Running-in Phase of HTR-PM
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Topics: Design, Eigenvalues, Fuels, Modeling, Graphite, Simulation, High temperature, Nuclear fuels, Particulate matter, Safety
Proceedings Papers

Development and Demonstration Testbed for the Remote Operations and Monitoring of Microreactors

Joseph Oncken, Thomas Ulrich, Kaeley Stevens, Zachary Sellers, Jeren Browning
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133205
https://doi.org/10.1115/ICONE31-133205
View Paper titled, Development and Demonstration Testbed for the Remote Operations and Monitoring of Microreactors
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Topics: Construction, Defense industry, Digital twin, Economics , Emergency management, Heat, Logistics, Machinery, Mining, Nuclear industry
Proceedings Papers

Influence of Nuclear Power Plant Interface Complexity on Operator Performance: A Modeling Study

Pu Chen, Jiejuan Tong
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134997
https://doi.org/10.1115/ICONE31-134997
View Paper titled, Influence of Nuclear Power Plant Interface Complexity on Operator Performance: A Modeling Study
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Topics: Control rooms, Machinery, Modeling, Network models, Nuclear power stations, Optimization, Stress, Accidents, Design, Engineering simulation
Proceedings Papers

United States NRC Modernization Efforts to Enable the Safe Use of Digital Instrumentation and Controls in Nuclear Power Plant Safety Systems

Samir Darbali, Dinesh Taneja, Erick Martinez Rodriguez, Gilberto Blas Rodriguez
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135026
https://doi.org/10.1115/ICONE31-135026
View Paper titled, United States NRC Modernization Efforts to Enable the Safe Use of Digital Instrumentation and Controls in Nuclear Power Plant Safety Systems
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Topics: Instrumentation, Nuclear power stations, Safety
Proceedings Papers

Research on Operation and Control Characteristics of Large Parallel Pipeline Fluid System

Niu Yuchen, Minjun Peng, Bowen Zhang, Zhe Yuan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134879
https://doi.org/10.1115/ICONE31-134879
View Paper titled, Research on Operation and Control Characteristics of Large Parallel Pipeline Fluid System
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Topics: Fluids, Pipeline systems, Pipelines, Control equipment, Flow (Dynamics), Pressure, Circuits, Cycles, Fuzzy control, Industrial lubrication systems
Proceedings Papers

Control Rod Cooperative Control Strategy Based on Multipoint Reactor Model

Bowen Tu, Airan Dang, Xiuchun Luan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135073
https://doi.org/10.1115/ICONE31-135073
View Paper titled, Control Rod Cooperative Control Strategy Based on Multipoint Reactor Model
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Topics: Delays, Fuzzy control, Rods, Safety, Simulation results
Proceedings Papers

Features of Space Reactor Brayton Cycle Under Power Regulation by Control Drums

Wenkui Ma, Ping Ye, Yue Gao, Yadong Hao, Yi Yao, Xiaoyong Yang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A055, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135642
https://doi.org/10.1115/ICONE31-135642
View Paper titled, Features of Space Reactor Brayton Cycle Under Power Regulation by Control Drums
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Topics: Brayton cycle, Safety
Proceedings Papers

Development of Thermal-Hydraulic and Safety Analysis Code for a Heat Pipe Cooled Reactor

Guanghui Jiao, Genglei Xia, Tao Zhou, Jianjun Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A023, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133432
https://doi.org/10.1115/ICONE31-133432
View Paper titled, Development of Thermal-Hydraulic and Safety Analysis Code for a Heat Pipe Cooled Reactor
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Topics: Heat pipes, Safety
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design