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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

Paper No: ICONE29-91761

DOI: https://doi.org/10.1115/ICONE29-91761

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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat

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

Paper No: ICONE29-90277

DOI: https://doi.org/10.1115/ICONE29-90277

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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction

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

Paper No: ICONE29-91416

DOI: https://doi.org/10.1115/ICONE29-91416

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Topics: Carbon, Innovation, Leakage, Nuclear power, Radioactivity, Renewable energy, Risk, Safety, Sustainable development, Thermal energy

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

Paper No: ICONE29-93779

DOI: https://doi.org/10.1115/ICONE29-93779

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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

Paper No: ICONE29-90522

DOI: https://doi.org/10.1115/ICONE29-90522

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Topics: Carbon, Climate change, Construction, Nuclear power, Safety, Stress, Sustainable development

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

Paper No: ICONE29-91638

DOI: https://doi.org/10.1115/ICONE29-91638

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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

Paper No: ICONE29-91676

DOI: https://doi.org/10.1115/ICONE29-91676

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Topics: Alloys, Carbon, Computer software, Corrosion, Precipitation, Simulation

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

Paper No: ICONE29-92807

DOI: https://doi.org/10.1115/ICONE29-92807

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Topics: Carbon, Pressurized water reactors

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

Paper No: ICONE29-92345

DOI: https://doi.org/10.1115/ICONE29-92345

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Topics: Carbon, Computerized tomography, Flaw detection, Gas cooled reactors, Graphite, High temperature

Proceedings Papers

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma

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, V001T02A004, August 4–6, 2021

Paper No: ICONE28-63633

DOI: https://doi.org/10.1115/ICONE28-63633

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Topics: Carbon, Dehumidification, Thermogravimetry, Very high temperature reactors, Temperature, Boron, Graphite, High temperature, Corrosion, Desorption

Proceedings Papers

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta

Paper No: ICONE28-64346

DOI: https://doi.org/10.1115/ICONE28-64346

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Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation

Proceedings Papers

A Statistical Approach for Modeling the Effect of Hot Press Conditions on the Mechanical Strength Properties of HTGR Fuel Elements

Aihara Jun, Kuroda Masatoshi, Tachibana Yukio

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A011, August 4–6, 2021

Paper No: ICONE28-64507

DOI: https://doi.org/10.1115/ICONE28-64507

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Topics: Fuels, Modeling, Strength (Materials), Very high temperature reactors, Carbon, Design, Experimental design, Oxidation, Pressure, Response surface methodology

Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg

Paper No: ICONE28-65765

DOI: https://doi.org/10.1115/ICONE28-65765

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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics

Proceedings Papers

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma

Paper No: ICONE28-64525

DOI: https://doi.org/10.1115/ICONE28-64525

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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants

Proceedings Papers

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Charles Forsberg, Daniel Stack, Patrick McDaniel

Paper No: ICONE28-64638

DOI: https://doi.org/10.1115/ICONE28-64638

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Topics: Combined cycles, Heat storage, Hydrogen, Heat, Compressed air, High temperature, Combined cycle gas turbines, Carbon, Cycles, Energy storage

Proceedings Papers

Public Engagement of Nuclear Energy in China: The Characteristics of Public Knowledge, Risk Perception, Trust Perception and Environmental Concern

Priscilla Obeng Oforiwaa, Zhang Chao, Liang Manchun, Su Guofeng, Wang Jiahao

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T07A003, August 4–5, 2020

Paper No: ICONE2020-16064

DOI: https://doi.org/10.1115/ICONE2020-16064

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Topics: China, Nuclear power, Risk, Risk perception, Carbon, Climate change, Emissions

Proceedings Papers

3D Immersive Display Application for Nuclear Education and Public Acceptance

Bing Lam Luk, Miu-Ling Lam, Ting-Hsuan Chen, Jiyun Zhao, Suet Man Tsui, Ching-Chang Chieng

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A005, July 22–26, 2018

Paper No: ICONE26-81161

DOI: https://doi.org/10.1115/ICONE26-81161

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Topics: Education, Nuclear power, Nuclear reactors, Carbon, Containment buildings, Nuclear power stations, Boilers, China, Computer-aided design, Containment

Proceedings Papers

Influence Factors on Moisture Absorption Process of Carbon Material in HTGR

Jun Li, Huaqiang Yin, Xuedong He

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A016, July 22–26, 2018

Paper No: ICONE26-81412

DOI: https://doi.org/10.1115/ICONE26-81412

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Topics: Absorption, Carbon, Very high temperature reactors, Boron, Corrosion, Diffusion (Physics), Graphite, High temperature, Temperature

Proceedings Papers

Design and Non-Proliferation Viability of Small Modular Reactors

Zafar ullah Koreshi

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A013, July 22–26, 2018

Paper No: ICONE26-81651

DOI: https://doi.org/10.1115/ICONE26-81651

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Topics: Design, Small modular reactors, Nuclear power, Carbon, Emissions, Nuclear reactors, Power density, Risk, Safety, Signals

Proceedings Papers

Approach to UK SMR Component Design

Christopher D. Bell

Paper No: ICONE26-81188

DOI: https://doi.org/10.1115/ICONE26-81188

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Topics: Design, Inspection, Manufacturing, Safety, Carbon, Design for Manufacturing, Energy generation, Failure, Failure mechanisms, Nuclear power stations

NARROW

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

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

Nuclear Cognition and Public Acceptance

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

Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies

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

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

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

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

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

A Finnish District Heating Reactor: Background and General Overview

A Statistical Approach for Modeling the Effect of Hot Press Conditions on the Mechanical Strength Properties of HTGR Fuel Elements

A Sodium-Cooled Thermal-Spectrum Fission Battery

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Public Engagement of Nuclear Energy in China: The Characteristics of Public Knowledge, Risk Perception, Trust Perception and Environmental Concern

3D Immersive Display Application for Nuclear Education and Public Acceptance

Influence Factors on Moisture Absorption Process of Carbon Material in HTGR

Design and Non-Proliferation Viability of Small Modular Reactors

Approach to UK SMR Component Design

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