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Proceedings Papers

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

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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

Modular Structure Selection and Design of ACP1000 Reactor Building

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Man Xu, Minghao Tang, Xiaopan Jia
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135725
https://doi.org/10.1115/ICONE31-135725
View Paper titled, Modular Structure Selection and Design of ACP1000 Reactor Building
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Topics: Concretes, Design, Modular construction, Steel
Proceedings Papers

Investigation About Classification of Stresses due to Radial Deformation Induced by Design Pressure Applied to the Tubes of Square Pitch Multi-Perforated Portion of Thick Plates

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Pascal Duranton, Marie Bernion, Aboubakr Amzil, Divjot Jolly, Abdelhak Benrabia, Tony Da Silva
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134544
https://doi.org/10.1115/ICONE31-134544
View Paper titled, Investigation About Classification of Stresses due to Radial Deformation Induced by Design Pressure Applied to the Tubes of Square Pitch Multi-Perforated Portion of Thick Plates
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Topics: Deformation, Design, Plates (structures), Pressure, Stress, Finite element methods, Welding, Heat exchangers, Mechanical behavior, Nuclear industry
Proceedings Papers

A Brief Introduction to Several Important Design Optimizations of Passive Nuclear Power Plants in China

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Baisong Ma, Zhengqiang Miao, Yuanhua Ma
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134488
https://doi.org/10.1115/ICONE31-134488
View Paper titled, A Brief Introduction to Several Important Design Optimizations of Passive Nuclear Power Plants in China
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Topics: China, Control rooms, Design, Gates (Closures), Nuclear power, Nuclear power stations
Proceedings Papers

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

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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

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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

Investigation in Design Technology of Load Follow Without Changing Soluble Boron of Hualong One

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Cui Huaiming, Ning Zhonghao, Liu TongXian, Wang ChenLin, Li Tian Ya, Cai Yun
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135183
https://doi.org/10.1115/ICONE31-135183
View Paper titled, Investigation in Design Technology of Load Follow Without Changing Soluble Boron of Hualong One
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Topics: Boron, Design, Stress, Water
Proceedings Papers

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

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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

Design and Calculation of Nuclear Heating System Utilizing a Molten Salt Heat Storage Circuit for Waste Heat Absorption and Peak Regulation

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Haofang Chong, Ruojun Xue, Sen Wang, Yaowu Cao, Furu Jing
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134681
https://doi.org/10.1115/ICONE31-134681
View Paper titled, Design and Calculation of Nuclear Heating System Utilizing a Molten Salt Heat Storage Circuit for Waste Heat Absorption and Peak Regulation
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Topics: Absorption, Circuits, Design, Energy storage, Heat storage, Heating, Waste heat
Proceedings Papers

A Kind of Shielding Design and Verification Test of Radioactive Source Transport Container

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Lei Chen, ZhiPeng Wang, LiMing Jiao, DaJie Zhuang, Qian Sun, ChangWu Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136170
https://doi.org/10.1115/ICONE31-136170
View Paper titled, A Kind of Shielding Design and Verification Test of Radioactive Source Transport Container
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Topics: Containers, Design
Proceedings Papers

Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN

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Hongwei Jiang, Guangliang Chen, Zhaofei Tian
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A048, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134838
https://doi.org/10.1115/ICONE31-134838
View Paper titled, Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN
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Topics: Computational fluid dynamics, Computer simulation, Coolants, Design, Flow (Dynamics), Fuel cells, Fuel rods, Fuels, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

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

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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

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

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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

Modeling and Control Scheme Design of a Multi-Modular High Temperature Gas Cooled Reactor Cogeneration Unit

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Zhonghua Cheng, Zhe Dong
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135166
https://doi.org/10.1115/ICONE31-135166
View Paper titled, Modeling and Control Scheme Design of a Multi-Modular High Temperature Gas Cooled Reactor Cogeneration Unit
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Topics: Combined heat and power, Control modeling, Design, Gas cooled reactors, High temperature
Proceedings Papers

Preliminary Design and Analysis of a Very-High-Temperature Reactor-Driven Hydrogen-Electricity Cogeneration System

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Hang Ni, Xinhe Qu, Gang Zhao, Jie Wang, Wei Peng
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134847
https://doi.org/10.1115/ICONE31-134847
View Paper titled, Preliminary Design and Analysis of a Very-High-Temperature Reactor-Driven Hydrogen-Electricity Cogeneration System
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Topics: Brayton cycle, Combined heat and power, Cycles, Design, Helium, Hydrogen, Hydrogen production, Sulfur, Temperature, Very high temperature reactors
Proceedings Papers

Optimization Design Study of a Radiant Heat Exchanger for a Small-Scale Underwater Nuclear Power Plant’s Residual Heat Removal System

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Yinan Guo, Lei Li, Yongsheng Wen
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A057, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135657
https://doi.org/10.1115/ICONE31-135657
View Paper titled, Optimization Design Study of a Radiant Heat Exchanger for a Small-Scale Underwater Nuclear Power Plant’s Residual Heat Removal System
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Topics: Design, Fins, Heat, Heat transfer, Nuclear power, Optimization, Radiant heat
Proceedings Papers

Conceptual Design of High-Power Nuclear Power System on the Surface of Mars

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Yansong Han
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A056, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135644
https://doi.org/10.1115/ICONE31-135644
View Paper titled, Conceptual Design of High-Power Nuclear Power System on the Surface of Mars
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Topics: Brayton cycle, Conceptual design, Design, Nuclear power
Proceedings Papers

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

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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
Proceedings Papers

Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA

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Akiyuki Seki, Yuki Kondo, Ryuta Hashidate, Masanori Yoshikawa, Kenji Yokoyama, Shigeru Takaya, Yasuhiro Enuma, Taira Hazama, Takashi Wakai, Tai Asayama
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131784
https://doi.org/10.1115/ICONE31-131784
View Paper titled, Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA
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Topics: Design, Knowledge management, Safety, Computer-aided design, Information retrieval, Sodium fast reactors, Artificial intelligence, Carbon, Computer simulation, Engineering drawings
Proceedings Papers

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

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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