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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

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

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

AHPR1000: Simplified, Intelligent and Environment-Friendly Advanced Nuclear Power Plant

Yuxiang Wu, Qianwen Liu, Di Yao, Guangfei Wang, Simin Xu, Yang Lu, Chengcheng Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135079
https://doi.org/10.1115/ICONE31-135079
View Paper titled, AHPR1000: Simplified, Intelligent and Environment-Friendly Advanced Nuclear Power Plant
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Topics: Nuclear power stations, Safety, Design, Maintenance, Accidents, Aircraft, Carbon, Chain, China, Construction
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
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Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

Design of a He-Xe Gas-Cooled Nuclear Microreactor System Based on Detailed Models of the Cycle Components

Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134951
https://doi.org/10.1115/ICONE31-134951
View Paper titled, Design of a He-Xe Gas-Cooled Nuclear Microreactor System Based on Detailed Models of the Cycle Components
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Topics: Brayton cycle, Cycles, Design, Turbomachinery, Carbon, Design methodology, Helium, Conceptual design, Emissions, Mechanical admittance
Proceedings Papers

Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle

Jiaolong Deng, Chaoran Guan, Xiaojing Liu, Hui He, Xiang Chai
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A041, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135136
https://doi.org/10.1115/ICONE31-135136
View Paper titled, Preliminary Design and Transient Simulation of a Nuclear-Solar Hybrid System Using an Open-Air Brayton Cycle
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Topics: Brayton cycle, Concentrating solar power, Design, Heat, Nuclear reactors, Pipes, Simulation, Solar energy, Thermal energy storage, Transients (Dynamics)
Proceedings Papers

Conduct a Tritium Radiation Safety Assessment on the Heating System Directly Supplied by the Steam From the Secondary Loop of the High-Temperature Gas-Cooled Reactor

Wenyi Wang, Chuan Li, Jianzhu Cao, Feng Xie, Hong Li
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132181
https://doi.org/10.1115/ICONE31-132181
View Paper titled, Conduct a Tritium Radiation Safety Assessment on the Heating System Directly Supplied by the Steam From the Secondary Loop of the High-Temperature Gas-Cooled Reactor
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Topics: Carbon, Heating, Radiation (Physics), Safety, Steam, Very high temperature reactors
Proceedings Papers

Vigorously Develop Nuclear Power to Meet the Challenge of the Rapid Growth of Electricity Consumption and Carbon Emission in the Information Industry

Yingnan Li, Fang Wu, Te Tang, Weili Liu
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A008, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136091
https://doi.org/10.1115/ICONE31-136091
View Paper titled, Vigorously Develop Nuclear Power to Meet the Challenge of the Rapid Growth of Electricity Consumption and Carbon Emission in the Information Industry
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Topics: Carbon, Emissions, Nuclear power
Proceedings Papers

Preliminary Assessment of CATHARE-MODELICA Codes Coupling for Safety Analyses in Nuclear Cogeneration

Alessandro De Angelis, Paolo Olita, Walter Ambrosini
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A094, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136017
https://doi.org/10.1115/ICONE31-136017
View Paper titled, Preliminary Assessment of CATHARE-MODELICA Codes Coupling for Safety Analyses in Nuclear Cogeneration
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Topics: Combined heat and power, Safety, Small modular reactors, Energy / power systems, Carbon, Transients (Dynamics), Dynamic modeling, Economics , Hydraulic drive systems, Mass production
Proceedings Papers

Thermohydraulic Simulation of Energy Well Micro Modular Reactor Using System Codes

Guido Mazzini, Marek Benčík, Mathieu Reungoat
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A083, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135616
https://doi.org/10.1115/ICONE31-135616
View Paper titled, Thermohydraulic Simulation of Energy Well Micro Modular Reactor Using System Codes
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Topics: Accidents, Carbon, Construction, Design, Emissions, Fluids, Nuclear research, Renewable energy, Safety, Simulation
Proceedings Papers

C-14 in Geological Repositories: Source Terms and Transport Models

Zhengzhe Qu, Jingni Guo, Qi Zhang, Yu Wang, Mengjie Wu, Feng Xie, Liqiang Wei, Jianzhu Cao
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134283
https://doi.org/10.1115/ICONE31-134283
View Paper titled, C-14 in Geological Repositories: Source Terms and Transport Models
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Topics: Biological tissues, Carbon, Chain, China, Computer simulation, Damage, Diffusion (Physics), Food products, Groundwater, Hazards
Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91761
https://doi.org/10.1115/ICONE29-91761
View Paper titled, Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR
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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat
Proceedings Papers

Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography

Renjie Liu, Yuewen Sun, Tianchen Zeng, Ximing Liu, Libin Sun, Li Shi, Peng Cong
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92345
https://doi.org/10.1115/ICONE29-92345
View Paper titled, Defect Detection Method for Large Size Graphite and Carbon Components of High Temperature Gas Cooled Reactor Based on Computed Tomography
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Topics: Carbon, Computerized tomography, Flaw detection, Gas cooled reactors, Graphite, High temperature
Proceedings Papers

Research on the Expected Carbon-14 Production and Discharge in Pressurized Water Reactors

Pengtao Fu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92807
https://doi.org/10.1115/ICONE29-92807
View Paper titled, Research on the Expected Carbon-14 Production and Discharge in Pressurized Water Reactors
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Topics: Carbon, Pressurized water reactors
Proceedings Papers

Nuclear Cognition and Public Acceptance

Weiqiang Zhu, Peng Wang, Changying Fu
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91416
https://doi.org/10.1115/ICONE29-91416
View Paper titled, Nuclear Cognition and Public Acceptance
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Topics: Carbon, Innovation, Leakage, Nuclear power, Radioactivity, Renewable energy, Risk, Safety, Sustainable development, Thermal energy
Proceedings Papers

Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance

Jianming Yu, Yibiao Cai
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A022, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91638
https://doi.org/10.1115/ICONE29-91638
View Paper titled, Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance
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Topics: Condition monitoring, Fault diagnosis, Maintenance, Monitoring systems, Nuclear power stations, Pattern recognition, Economics , Safety, Carbon, Construction
Proceedings Papers

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Qiang Zhong, Man Wang, Wen-Qiang Sun, Jun-Jie Wu, Jiong Qian, Sen-Sen Ning
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A023, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91676
https://doi.org/10.1115/ICONE29-91676
View Paper titled, Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H
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Topics: Alloys, Carbon, Computer software, Corrosion, Precipitation, Simulation
Proceedings Papers

Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example

Baoquan Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90277
https://doi.org/10.1115/ICONE29-90277
View Paper titled, Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example
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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction
Proceedings Papers

Strategies and Applications of Big Data and AI Technologies in Nuclear Power Public Opinion Prevention and Control System

Yun Liang, Shaolin Zhang, Shangyuan Liu
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93779
https://doi.org/10.1115/ICONE29-93779
View Paper titled, Strategies and Applications of Big Data and AI Technologies in Nuclear Power Public Opinion Prevention and Control System
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Topics: Control systems, Nuclear power, Carbon, Carbon neutrality, Simulation, China, Climate change, Construction, Emissions, Feedback
Proceedings Papers

Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies

Haomiao Lin
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90522
https://doi.org/10.1115/ICONE29-90522
View Paper titled, Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies
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Topics: Carbon, Climate change, Construction, Nuclear power, Safety, Stress, Sustainable development