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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

Research and Application Innovation of Digital Twin Technologies for Key Equipment of Nuclear Power Plants

Dong Zhao, Fenghua Guan
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A044, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93416
https://doi.org/10.1115/ICONE29-93416
View Paper titled, Research and Application Innovation of Digital Twin Technologies for Key Equipment of Nuclear Power Plants
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Topics: Digital twin, Innovation, Multiscale modeling, Nuclear power, Nuclear power stations, Virtual reality
Proceedings Papers

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma
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, V001T03A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64525
https://doi.org/10.1115/ICONE28-64525
View Paper titled, ARKADIA – for the Innovation of Advanced Nuclear Reactor Design
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Proceedings Papers

Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor

Yanzhu Chen, Zhichao Yang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65152
https://doi.org/10.1115/ICONE28-65152
View Paper titled, Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor
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Topics: Fire, Ignition, Probability, Safety, Design, Evaluation methods, Innovation, Sensitivity analysis
Proceedings Papers

Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

Shanfang Huang, Jiageng Wang, Yisheng Hao, Guodong Liu, Minyun Liu, Yugao Ma
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T07A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16033
https://doi.org/10.1115/ICONE2020-16033
View Paper titled, Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment
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Topics: Innovation, Nuclear engineering, Nuclear power stations, Safety, Teaching
Proceedings Papers

Foreseen Capabilities, Bottlenecks Identification and Potential Limitations of Serpent MC Transport Code in Large-Scale Full 3-D Burnup Calculations

Diego Ferraro, Manuel Garcia, Luigi Mercatali, Victor Hugo Sanchez Espinoza, Jaakko Leppänen, Ville Valtavirta
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A049, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82305
https://doi.org/10.1115/ICONE26-82305
View Paper titled, Foreseen Capabilities, Bottlenecks Identification and Potential Limitations of Serpent MC Transport Code in Large-Scale Full 3-D Burnup Calculations
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Topics: Architecture, Design, Fuels, Innovation, Light water reactors, Nuclear industry, Nuclear reactors, Physics, Safety, Steady state
Proceedings Papers

Structure Innovation and Thermal Hydraulics Analysis for Cold Trap of CEFR

Chen Zu-guo, Xu Yi-jun, Qi Wen-jing
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A049, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81533
https://doi.org/10.1115/ICONE26-81533
View Paper titled, Structure Innovation and Thermal Hydraulics Analysis for Cold Trap of CEFR
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Topics: Coolants, Cylinders, Density, Flow (Dynamics), Hydraulics, Innovation, Numerical analysis, Orifices, Precipitation, Sodium
Proceedings Papers

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

R. Marinari, M. Tarantino, F. S. Nitti, A. Alemberti, M. Caramello, A. Achilli, R. Ferri, E. Rizzo, F. Giannetti
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A054, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82379
https://doi.org/10.1115/ICONE26-82379
View Paper titled, SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases
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Topics: Gases, Heat, Coolants, Safety, Design, Computer simulation, Freezing, Liquid metals, Solidification, Accidents
Proceedings Papers

Research and Practice of Nuclear Equipment Procurement and Supply Management Based on “Internet+” Mode

Hui Zhou, Liang Ding, Xu Shi, Zhongkui Li
Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T02A002, June 24–28, 2018
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2018-7490
https://doi.org/10.1115/NUCLRF2018-7490
View Paper titled, Research and Practice of Nuclear Equipment Procurement and Supply Management Based on “Internet+” Mode
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Topics: Construction, Innovation, Internet, Nuclear power, Tracking control, Transparency
Proceedings Papers

Unprotected Overpower Transient Analysis of a Million Kilowatt Traveling Wave Reactor Core

Pengrui Qiao, Jian Zhang, Chao Lin
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66057
https://doi.org/10.1115/ICONE25-66057
View Paper titled, Unprotected Overpower Transient Analysis of a Million Kilowatt Traveling Wave Reactor Core
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Topics: Transient analysis, Traveling waves, Fuels, Safety, Accidents, Design, Innovation, Transients (Dynamics), China, Cladding systems (Building)
Proceedings Papers

Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

Yang Cheng, Zhang Xueliang, Xia Peng, Zeng Qingyue, Li Tian
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66028
https://doi.org/10.1115/ICONE25-66028
View Paper titled, Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs
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Topics: China, In-service inspection, Pressurized water reactors, Regulations, Nuclear power, Innovation, Inspection, Licensing, Nondestructive evaluation, Nuclear industry
Proceedings Papers

Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core

Wenjun Hu, Pengrui Qiao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A004, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66101
https://doi.org/10.1115/ICONE25-66101
View Paper titled, Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core
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Topics: Flow (Dynamics), Traveling waves, Fuels, Safety, Accidents, Design, Innovation, China, Cladding systems (Building), Combustion
Proceedings Papers

D&D and Waste Management: An AREVA Expertise From AREVA Sites Operations to Customers Projects

Stephane Bargues
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-68003
https://doi.org/10.1115/ICONE25-68003
View Paper titled, D&D and Waste Management: An AREVA Expertise From AREVA Sites Operations to Customers Projects
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Topics: Waste management, Decontamination, Nuclear power stations, Storage, Contamination, Feedback, Fuels, Industrial research, Innovation, Irradiation (Radiation exposure)
Proceedings Papers

Based on Human Behavior Process of Human Error Defensive Management Research for NPP

Shen Yang, Geng Bo, Li Dan
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66007
https://doi.org/10.1115/ICONE25-66007
View Paper titled, Based on Human Behavior Process of Human Error Defensive Management Research for NPP
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Topics: Errors, Nuclear power stations, Human factors, Quality control charts, Root cause analysis, Buses, Corrective actions, Databases, Defense industry, Innovation
Proceedings Papers

Application Research of Safety Control and Information Device Based on FirmSys Platform in ACPR1000 Nuclear Power Plant

Li-Ling Zhu, Bin Wu, Gang Li, Yi-Qin Xie, Yong-Bin Sun
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A051, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67882
https://doi.org/10.1115/ICONE25-67882
View Paper titled, Application Research of Safety Control and Information Device Based on FirmSys Platform in ACPR1000 Nuclear Power Plant
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Topics: Nuclear power stations, Safety, Computers, Innovation, Instrumentation
Proceedings Papers

Research on Simulation Technology for Supervisory Control Software in NPP DCS

Hanjun Gao, Ming Qu, CaiKe Zhang, Kui Xu, PeiBang Liu, Chenglong Xie
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A004, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66064
https://doi.org/10.1115/ICONE25-66064
View Paper titled, Research on Simulation Technology for Supervisory Control Software in NPP DCS
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Topics: Computer software, Nuclear power stations, Simulation, Reliability, Engineers, Innovation, Licensing, Process control
Proceedings Papers

Experiment for Wastewater Treatment Technology by Ultrasonic Standing Wave Method

Suxia Hou, Jijun Luo, Bin He
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T11A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60810
https://doi.org/10.1115/ICONE24-60810
View Paper titled, Experiment for Wastewater Treatment Technology by Ultrasonic Standing Wave Method
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Topics: Standing waves, Wastewater treatment, Radioisotopes, Separation (Technology), Hazards, Innovation, Radioactive wastes
Proceedings Papers

Chinese Innovative Patent Technologies for the Reactor Pressure Vessel

Qian Shi, Tianqi Zhang, Xiang Fang, Wei Peng
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30694
https://doi.org/10.1115/ICONE22-30694
View Paper titled, Chinese Innovative Patent Technologies for the Reactor Pressure Vessel
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Topics: Patents, Reactor vessels, Nuclear power, China, Design, Safety, Containers, Design methodology, Economics , Innovation
Proceedings Papers

Being Educated in a New Nuclear Engineering Program: A Graduate Student Perspective

Hector Medina
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T12A017, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16908
https://doi.org/10.1115/ICONE21-16908
View Paper titled, Being Educated in a New Nuclear Engineering Program: A Graduate Student Perspective
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Topics: Graduate students, Nuclear engineering, Students, Creativity, Education, Feedback, Innovation, Mechanical engineering, Undergraduate students
Proceedings Papers

Research on High and Low Pressure Filter Cartridge Replacement and Transport Process and Related Operating Equipments Design for AP1000 Nuclear Power Project

Xiangfei You, Kang Chen, Jiansheng Xing, Haida Shen, Lei Meng, Ke Shi
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T08A009, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15771
https://doi.org/10.1115/ICONE21-15771
View Paper titled, Research on High and Low Pressure Filter Cartridge Replacement and Transport Process and Related Operating Equipments Design for AP1000 Nuclear Power Project
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Topics: Design, Filters, Nuclear power, Pressure, Transport processes, Radiation (Physics), Innovation, Nuclear power stations, Pollution, Risk