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Proceedings Papers

Application of Self-Developed Advanced Three-Dimensional Simulation Software in Internal Flooding of Nuclear Power Plant

Chenhui Wang, Ran Zhang, Xiaoyun Huang, Chao Wang, Meng Zhao
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93264
https://doi.org/10.1115/ICONE29-93264
View Paper titled, Application of Self-Developed Advanced Three-Dimensional Simulation Software in Internal Flooding of Nuclear Power Plant
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Topics: Computer software, Floods, Nuclear power stations, Safety, Simulation
Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91669
https://doi.org/10.1115/ICONE29-91669
View Paper titled, Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains
Proceedings Papers

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Lingmei Xiao, Bing Zhang, Ming Wang, Zhiwen Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92450
https://doi.org/10.1115/ICONE29-92450
View Paper titled, Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant
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Topics: Floods, Nuclear power stations, Reactor vessels, Risk, Vessels
Proceedings Papers

Comparative Study on Internal Flooding Prevention Design of Several Types of NPPs and Improvement Suggestions

Yang Yinghao, Li Zhaohua, Xu Xiaoyan
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91895
https://doi.org/10.1115/ICONE29-91895
View Paper titled, Comparative Study on Internal Flooding Prevention Design of Several Types of NPPs and Improvement Suggestions
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Topics: Design, Floods, Nuclear power stations, Probabilistic safety assessment
Proceedings Papers

PSA Application for UK HPR1000 ALARP Demonstration

Zhiwen Wang, Chunju Yang, Bing Zhang, Jinkai Wang, Huina Sang, Lingmei Xiao, Fei Wang, Ming Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A043, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93109
https://doi.org/10.1115/ICONE29-93109
View Paper titled, PSA Application for UK HPR1000 ALARP Demonstration
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Topics: China, Design, Fire, Floods, Hazards, Nuclear power, Probabilistic safety assessment, Risk, Safety, Spent nuclear fuels
Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92462
https://doi.org/10.1115/ICONE29-92462
View Paper titled, PSA Application in UK HPR1000 Numerical Targets Evaluation
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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety
Proceedings Papers

Margin Analysis of Conventional Island Under Beyond Design Basis External Flooding Scenario for NPP

Xingbing Lv, Shuangyang Liu, Hongyang Zhang, Run Lin
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92151
https://doi.org/10.1115/ICONE29-92151
View Paper titled, Margin Analysis of Conventional Island Under Beyond Design Basis External Flooding Scenario for NPP
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Topics: Design, Floods, Nuclear power stations
Proceedings Papers

Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3

Ikken Sato, Akifumi Yamaji, Xin Li, Hiroshi Madokoro
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, V003T12A016, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64246
https://doi.org/10.1115/ICONE28-64246
View Paper titled, Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3
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Topics: Cooling, Floods, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Vessels, Water
Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64739
https://doi.org/10.1115/ICONE28-64739
View Paper titled, Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments
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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux
Proceedings Papers

Analysis of the Reflooding Process in Degraded Particle Beds by Simulations of the Debris Test Facility With the Severe Accident Analysis Code ASTEC V2.1 and COCOMO Code

Jan M. Peschel, Christoph Bratfisch, Marco K. Koch
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, V003T12A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-60964
https://doi.org/10.1115/ICONE28-60964
View Paper titled, Analysis of the Reflooding Process in Degraded Particle Beds by Simulations of the Debris Test Facility With the Severe Accident Analysis Code ASTEC V2.1 and COCOMO Code
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Topics: Accidents, Particulate matter, Simulation, Test facilities, Temperature, Cooling, Design, Floods, Flow (Dynamics), Gravity (Force)
Proceedings Papers

Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

Arièle Défossez, Eric Dupont, Laurence Grammosenis, Hervé Cordier, Tiphaine Le Morvan
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16136
https://doi.org/10.1115/ICONE2020-16136
View Paper titled, Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider
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Topics: Computational fluid dynamics, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Safety, Wind velocity, Structures, Wind, Power stations, Storms
Proceedings Papers

Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China

Liu Yu, Li Wenjing, Yu Yun
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16076
https://doi.org/10.1115/ICONE2020-16076
View Paper titled, Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China
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Topics: China, Floods, Pressurized water reactors
Proceedings Papers

An Experimental Study of Liquid Flooding in Vertical Large Scale Rectangular Channel With the Counter-Current Flow of Air and Water Film

Kashuai Du, Po Hu, Shuwei Zhai, Xiaojie Yang, Weibo Wang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A060, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82478
https://doi.org/10.1115/ICONE26-82478
View Paper titled, An Experimental Study of Liquid Flooding in Vertical Large Scale Rectangular Channel With the Counter-Current Flow of Air and Water Film
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Topics: Floods, Flow (Dynamics), Water, Temperature, Steel, Drops, Evaporation, Film flow, Flat plates, Glass
Proceedings Papers

Study on PRA Procedure Considering Combination of Multiple Events Using DQFM Methodology

Hirohisa Yamakawa, Hitoshi Muta
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82086
https://doi.org/10.1115/ICONE26-82086
View Paper titled, Study on PRA Procedure Considering Combination of Multiple Events Using DQFM Methodology
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Topics: Accidents, Earthquakes, Failure, Fire, Floods, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pipes, Safety, Simulation
Proceedings Papers

Measurement of Dry-Out Heat Flux (DHF) of Debris Beds Using a Non-Heating Experimental Methodology

Je-Young Moon, Bum-Jin Chung
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82028
https://doi.org/10.1115/ICONE26-82028
View Paper titled, Measurement of Dry-Out Heat Flux (DHF) of Debris Beds Using a Non-Heating Experimental Methodology
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Topics: Heat flux, Heating, Copper, Anodes, Cylinders, Data acquisition systems, Electroplating, Floods, Heat transfer, Hydrogen
Proceedings Papers

Evaluation of Explosivity From Fuel Coolant Interaction Experiments in the TROI Facility

Seong-Wan Hong, Rae-Joon Park
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82029
https://doi.org/10.1115/ICONE26-82029
View Paper titled, Evaluation of Explosivity From Fuel Coolant Interaction Experiments in the TROI Facility
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Topics: Coolants, Fuels, Cavities, Floods, Pressure, Shapes, Water temperature
Proceedings Papers

Study on Protection Against Large Commercial Aircraft Crash of HPR1000

Xueshuang Zhang, Li Fan, Lijian Cai, Qianwen Liu
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81397
https://doi.org/10.1115/ICONE26-81397
View Paper titled, Study on Protection Against Large Commercial Aircraft Crash of HPR1000
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Topics: Aircraft, Safety, Design, Shells, Acceptance criteria, Damage, Fire, Hazards, Spent nuclear fuels, Concretes
Proceedings Papers

Establishment of “Technical Guidelines for Watertight Facilities (JEAG4630-2016)”

Koji Yamada, Kyoichi Chuda, Akihiko Masu, Shoichi Goto, Isamu Nakazuka, Yohei Komiyama, Tatsumi Horiuchi, Tomokazu Iwata, Yasuhiro Tsumura, Shizuo Noda
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81208
https://doi.org/10.1115/ICONE26-81208
View Paper titled, Establishment of “Technical Guidelines for Watertight Facilities (JEAG4630-2016)”
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Topics: Design, Floods, In-service inspection, Nuclear power, Nuclear power stations, Public utilities, Tsunamis
Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong
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, V001T13A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81159
https://doi.org/10.1115/ICONE26-81159
View Paper titled, Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions
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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers
Proceedings Papers

Injectable Sacrificial Material System to Contain Ex-Vessel Molten Corium in Nuclear Accidents

David L. Y. Louie, Yifeng Wang, Rekha Rao, Alec Kucala, Jessica Kruichak
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81440
https://doi.org/10.1115/ICONE26-81440
View Paper titled, Injectable Sacrificial Material System to Contain Ex-Vessel Molten Corium in Nuclear Accidents
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Topics: Accidents, Vessels, Light water reactors, Modeling, Water, Cavities, Conceptual design, Concretes, Containment, Cooling