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Proceedings Papers

Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States

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Takahiro Usui, Hiroki Nakamura, Kenichi Ihara, Yuki Hirai, Hitoshi Nojima, Satoshi Yoneda, Kenichi Kanda, Kazunobu Noriyasu, Daichi Shiota, Naoki Hirokawa
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134400
https://doi.org/10.1115/ICONE31-134400
View Paper titled, Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States
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Topics: Accidents, Airbags, Boiling water reactors, Design, Electricity (Physics), Engineering standards, Failure data, Fault tree analysis, Fukushima nuclear disaster, Japan, 2011, Human reliability analysis
Proceedings Papers

Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector

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Wenzhang Xie, Jia Huang, Chenyu Shan, Qingxin Lei, Kang Chang, Hao Zhou, Feng Liu, Peng Lin, Xiajie Liu, Li Li
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91233
https://doi.org/10.1115/ICONE29-91233
View Paper titled, Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector
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Topics: Containers, Nuclear power stations, Sensors, Simulation, Density, Radioactive wastes, Chemical stability, Engineering standards, Evaporation, Filtration
Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

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Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Research on Electromagnetic Interference Protection of Nuclear Power Unit Equipment Under the Application of New Wireless Technology in Smart Nuclear Power

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Bing Chen, Guidan Zhao, Zhiping Zhong, Yong Zheng, Charlie Yu
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91926
https://doi.org/10.1115/ICONE29-91926
View Paper titled, Research on Electromagnetic Interference Protection of Nuclear Power Unit Equipment Under the Application of New Wireless Technology in Smart Nuclear Power
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Topics: Electromagnetic interference, Nuclear power, Nuclear power stations, Signals, Electromagnetic compatibility, Engineering standards, Generators, Instrumentation, Nuclear industry, Radio waves
Proceedings Papers

Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake

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Rui Wang, Kechen Xu, Kehao Zeng, Hongmei Yan, Wei Bai
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92414
https://doi.org/10.1115/ICONE29-92414
View Paper titled, Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake
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Topics: Engineering standards, Nuclear power stations, Water
Proceedings Papers

Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety

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Chen Yuxiu, Wang Yuhong, Luo Haiying, Wang Jinkai, Shi Qing, Zhu Zengpei, Wu Bei
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92615
https://doi.org/10.1115/ICONE29-92615
View Paper titled, Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety
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Topics: Engineering standards, Nuclear power stations, Safety
Proceedings Papers

Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

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Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93746
https://doi.org/10.1115/ICONE29-93746
View Paper titled, Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment
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Topics: Engineering standards, Pressure equipment, Pressurized water reactors
Proceedings Papers

Recent Activities and New Challenges for the EUR Organization

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Vincent Sorel
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, V001T02A026, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64617
https://doi.org/10.1115/ICONE28-64617
View Paper titled, Recent Activities and New Challenges for the EUR Organization
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Topics: Accidents, Design, Engineering standards, Fukushima nuclear disaster, Japan, 2011, Light water reactors, Nuclear power stations, Safety, Small modular reactors
Proceedings Papers

The Effect of Functional Spacers on the Liquid Film Thickness and Dryout in a BWR Fuel Bundle Model

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Christian Bolesch, Lukas Robers, Robert Zboray, Horst-Michael Prasser
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A060, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81602
https://doi.org/10.1115/ICONE26-81602
View Paper titled, The Effect of Functional Spacers on the Liquid Film Thickness and Dryout in a BWR Fuel Bundle Model
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Topics: Boiling water reactors, Fuels, Liquid films, Flow (Dynamics), Heating, Design, Rods, Computational fluid dynamics, Computers, Drops
Proceedings Papers

Research About the Uniform Field Breakdown Strength of Helium Gas at High Temperature and Pressure in Millimeter-Scale Gaps

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You Qi, Shi Zhengang, Liu Xingnan, Yan Xunshi, Yang Guojun
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81293
https://doi.org/10.1115/ICONE26-81293
View Paper titled, Research About the Uniform Field Breakdown Strength of Helium Gas at High Temperature and Pressure in Millimeter-Scale Gaps
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Topics: Helium, High temperature, Pressure, Insulation, Design, Very high temperature reactors, Coolants, Engineering standards, High pressure (Physics), Magnetic bearings
Proceedings Papers

Electric Field Simulation of Ionization Chamber Used in Tritium Measurement in Tail Gas of Molten Salt Reactor

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Nan Qian, Guanghua Wang, Huang Yu, Youshi Zeng, Guangliang Bao, Shengwei Wu, Wei Liu
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82026
https://doi.org/10.1115/ICONE26-82026
View Paper titled, Electric Field Simulation of Ionization Chamber Used in Tritium Measurement in Tail Gas of Molten Salt Reactor
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Topics: Electric fields, Ionization chambers, Molten salt reactors, Simulation, Electrodes, Wire, Electrons, Computer software, Contamination, Engineering standards
Proceedings Papers

Validation of a CFD Code for the Analysis of Hydrogen Behaviors and Thermal Hydraulics in Containments

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Meilan Chen, Zeming Zheng
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A036, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82192
https://doi.org/10.1115/ICONE26-82192
View Paper titled, Validation of a CFD Code for the Analysis of Hydrogen Behaviors and Thermal Hydraulics in Containments
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Topics: Computational fluid dynamics, Hydrogen, Thermal hydraulics, Containment, Nuclear power stations, China, Accidents, Buoyancy, Condensation, Convection
Proceedings Papers

European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

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Peter Chappell, Guillaume Jacquart, Giovanni Ferraro, Olli Kymäläinen
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, V001T13A022, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82343
https://doi.org/10.1115/ICONE26-82343
View Paper titled, European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments
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Topics: Light water reactors, Nuclear power stations, Design, Safety, Performance, Public utilities, Construction, Engineering standards, Feedback, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve

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Jun Wu, Fan Bai, Yong Liu, Xingsheng Lao, Chunhui Dai
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82137
https://doi.org/10.1115/ICONE26-82137
View Paper titled, Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve
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Topics: Power stations, Safety, Ships, Shock (Mechanics), Valves, Stress, Modal analysis, Stress concentration, ASME Standards, Emission spectroscopy
Proceedings Papers

An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component

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Xiaoming Bai, Liangang Zheng, Xinjun Wang, Xi Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A047, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66441
https://doi.org/10.1115/ICONE25-66441
View Paper titled, An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component
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Topics: Fracture (Materials), Fracture (Process), Microscale devices, Pipes, Finite element analysis, Boundary-value problems, Damping, Engineering standards, Materials properties, Mechanical properties
Proceedings Papers

Structural Integrity Test of Steel Containment Vessel at the First AP1000 Unit of China

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Li Kai, Zhong Zhimin, Ma Xianhong
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A018, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66188
https://doi.org/10.1115/ICONE25-66188
View Paper titled, Structural Integrity Test of Steel Containment Vessel at the First AP1000 Unit of China
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Topics: China, Containment vessels, Steel, Testing, Leakage, Design, Engineering standards, Fracture (Materials), Manufacturing, Pressure
Proceedings Papers

The European Utility Requirements for Advanced Light Water Reactors (EUR): Recent Achievements and New Challenges

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Guillaume Jacquart, Olli Kymäläinen, Jean-François Vivier, Giovanni Ferraro, Emmanuel Vieilletoile
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67141
https://doi.org/10.1115/ICONE25-67141
View Paper titled, The European Utility Requirements for Advanced Light Water Reactors (EUR): Recent Achievements and New Challenges
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Topics: Light water reactors, Design, Nuclear power stations, Safety, Engineering standards, Fukushima nuclear disaster, Japan, 2011, Hazards, Instrumentation, Public utilities
Proceedings Papers

Development, Distribution and Maintenance of Application Security Controls for Nuclear

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Karl Waedt, Yongjian Ding, Antonio Ciriello, Xinxin Lou
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A029, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67499
https://doi.org/10.1115/ICONE25-67499
View Paper titled, Development, Distribution and Maintenance of Application Security Controls for Nuclear
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Topics: Maintenance, Security, Computer security, Countermeasures, Teams, Engineering standards, National Institute of Standards and Technology, Risk, Safety
Proceedings Papers

The Study on High Efficiency Solidification Technology of Radioactive Liquid Waste Containing Boron

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Yaguang Wang, Jinsong Zhang, Yunming Chen, Bing Li, Qi Cao
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A031, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67665
https://doi.org/10.1115/ICONE25-67665
View Paper titled, The Study on High Efficiency Solidification Technology of Radioactive Liquid Waste Containing Boron
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Topics: Boron, Solidification, Cements (Adhesives), Compressive strength, Containment, Engineering standards, Radioactive waste disposal
Proceedings Papers

Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool

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Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67065
https://doi.org/10.1115/ICONE25-67065
View Paper titled, Verification of FPGA Based NPP I&C Systems Considering Multiple Faults: Technique and Automation Tool
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Topics: Nuclear power stations, Safety, Failure mechanisms, Reliability, Engineering standards, Failure, Failure mode and effects analysis, Gates (Closures), Instrumentation, Integrated circuits