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Proceedings Papers

Design and Evaluation of Mitigation Measures for Tsinghua High Flux Reactor Loss-of-Coolant Accidents

Zhuang Wang, Heng Xie, Gan Zhu, Szu-En Yeh
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134999
https://doi.org/10.1115/ICONE31-134999
View Paper titled, Design and Evaluation of Mitigation Measures for Tsinghua High Flux Reactor Loss-of-Coolant Accidents
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Topics: Cooling, Design, Emergencies, Loss of coolant accidents
Proceedings Papers

Numerical Simulation on the Thermal Hydraulic Characteristics in Pool-Type Fast Reactor Based on the New-Designed Passive Dynamic Residual Heat Removal Valve

Yuanshu Qu, Yuhao Zhang, Haiqi Zhao, Daogang Lu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A073, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135327
https://doi.org/10.1115/ICONE31-135327
View Paper titled, Numerical Simulation on the Thermal Hydraulic Characteristics in Pool-Type Fast Reactor Based on the New-Designed Passive Dynamic Residual Heat Removal Valve
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Topics: Computer simulation, Emergencies, Fast neutron reactors, Heat, Sodium fast reactors, Valves
Proceedings Papers

Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant

Yanming Shi, Zhenying Wang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92804
https://doi.org/10.1115/ICONE29-92804
View Paper titled, Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant
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Topics: Decision making, Emergencies, Nuclear power stations, Reactor vessels, Water
Proceedings Papers

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Jie Zhang, Jing Wang, Peiying Zhang, Kun Tan, Minxue Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91837
https://doi.org/10.1115/ICONE29-91837
View Paper titled, Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant
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Topics: China, Construction, Nuclear power stations, Water, Safety, Risk, Accidents, Maintenance, Pressurized water reactors, Cooling
Proceedings Papers

Application of Risk-Informed Technology in Emergency Operating Procedure Development

Liu Liu, Zhiyun Liu, Zongqiang Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A047, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93180
https://doi.org/10.1115/ICONE29-93180
View Paper titled, Application of Risk-Informed Technology in Emergency Operating Procedure Development
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Topics: Emergencies, Risk
Proceedings Papers

Application of Risk-Informed Approach in Emergency Compressor Emergency Backup Function Test

Deyi Liu, Sixing Zha, Jian Wu, Yong Cao, Zilong Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91480
https://doi.org/10.1115/ICONE29-91480
View Paper titled, Application of Risk-Informed Approach in Emergency Compressor Emergency Backup Function Test
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Topics: Compressors, Emergencies, Risk
Proceedings Papers

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Guanhui Xie, Runcheng Li, Tianyi Wei, Zhikang Lin, Dongyang Li, Sichao Tan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89228
https://doi.org/10.1115/ICONE29-89228
View Paper titled, Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions
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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics
Proceedings Papers

Research on Operational Intervention Levels for the “Ground” Scenario in High Temperature Gas-Cooled Reactor

Ao Liu, Tao Liu, Liguo Zhang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A084, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92197
https://doi.org/10.1115/ICONE29-92197
View Paper titled, Research on Operational Intervention Levels for the “Ground” Scenario in High Temperature Gas-Cooled Reactor
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Topics: Emergencies, Very high temperature reactors
Proceedings Papers

Experimental Investigation on Natural Circulation Characteristics of Core Make-Up Tank Under Rolling Conditions

Shuguang Wang, Jinlei Zhang, Ya'ou Shen, Xiaobo Liu, Shuhua Ding, Yusheng Liu, Dongyang Li, Jilin Tang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A087, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92254
https://doi.org/10.1115/ICONE29-92254
View Paper titled, Experimental Investigation on Natural Circulation Characteristics of Core Make-Up Tank Under Rolling Conditions
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Topics: Emergencies, Flow (Dynamics), Nuclear engineering, Nuclear power stations, Safety, Temperature, Temperature gradient, Thermal stratification, Thermocouples, Vessels
Proceedings Papers

Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment

Li Yang, Xinpeng Li, Yixue Chen, Boxin Wang, Sheng Fang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90806
https://doi.org/10.1115/ICONE29-90806
View Paper titled, Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment
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Topics: Interpolation, Optimization, Computational methods, Databases, Emergencies
Proceedings Papers

Analysis of Single-Line Fast Starting Technology for Emergency Diesel Generators in Nuclear Power Plants

Hongzhou Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92194
https://doi.org/10.1115/ICONE29-92194
View Paper titled, Analysis of Single-Line Fast Starting Technology for Emergency Diesel Generators in Nuclear Power Plants
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Topics: Diesel generators, Emergencies, Nuclear power stations
Proceedings Papers

Reliability Analysis of Off-Plant Power for Multi-Units

Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91870
https://doi.org/10.1115/ICONE29-91870
View Paper titled, Reliability Analysis of Off-Plant Power for Multi-Units
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Topics: Accidents, Emergencies, Event history analysis, Failure, Modeling, Nuclear power, Nuclear power stations, Power grids, Probabilistic safety assessment, Reliability
Proceedings Papers

Research and Treatment of Pressure Regulation Defects in Fuel Circuit of Emergency Diesel Engine of One Nuclear Power Plant

Guo Feng
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A049, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92726
https://doi.org/10.1115/ICONE29-92726
View Paper titled, Research and Treatment of Pressure Regulation Defects in Fuel Circuit of Emergency Diesel Engine of One Nuclear Power Plant
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Topics: Circuits, Diesel engines, Emergencies, Fuels, Nuclear power stations, Pressure, Valves
Proceedings Papers

Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention

Hua Zheng, Shuhong Wei
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92239
https://doi.org/10.1115/ICONE29-92239
View Paper titled, Reactor Pit Injection Isolation Design Modification and Experience Feedback of UK HPR1000 In-Vessel Retention
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Topics: Design, Feedback, Vessels, Nuclear power stations, Safety, Accident management, Accidents, Construction, Control panels, Control rooms
Proceedings Papers

HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration

Zhaohua Tian, Qiang Li
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89471
https://doi.org/10.1115/ICONE29-89471
View Paper titled, HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration
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Topics: Design, Emergencies, Nuclear power stations
Proceedings Papers

Simulation of MSLB+SBO Nuclear Accident Drill Sequence of 3rd-Generation Passive Nuclear Power Plant Based on Severe Accident Simulator

Yongyong Yang, Xiong Huang, Wei Wei, Yinyong Tao, Zhengquan Xie, Guoyang Ma
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90732
https://doi.org/10.1115/ICONE29-90732
View Paper titled, Simulation of MSLB+SBO Nuclear Accident Drill Sequence of 3rd-Generation Passive Nuclear Power Plant Based on Severe Accident Simulator
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Topics: Accidents, Drills (Tools), Emergencies, Nuclear power stations, Sensitivity analysis, Simulation
Proceedings Papers

Simulation Research on Real-Time Offsite Dose Radiation of Nuclear Power Plant

Pingwen Ou, Zhenghui Wang, Dongyu He, Pingting Jiang
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91568
https://doi.org/10.1115/ICONE29-91568
View Paper titled, Simulation Research on Real-Time Offsite Dose Radiation of Nuclear Power Plant
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Topics: Emergencies, Nuclear power stations, Radiation (Physics), Simulation, Safety, Accidents, Plumes (Fluid dynamics), Diffusion (Physics), Economics , Emergency response
Proceedings Papers

The Radioactivity Monitoring of Environmental Samples in Zhejiang During the Events of Nuclear Leakage in Japan

Gongye Liu, Jia Yang, Xiaoyan Hu, Fei Hu, Yuanyi Xiang
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, V003T12A018, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64262
https://doi.org/10.1115/ICONE28-64262
View Paper titled, The Radioactivity Monitoring of Environmental Samples in Zhejiang During the Events of Nuclear Leakage in Japan
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Topics: Emergencies, Leakage, Radioactivity, Radioisotopes, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release

Yamato Sugitatsu, Shripad T. Revankar
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62097
https://doi.org/10.1115/ICONE28-62097
View Paper titled, Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release
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Topics: Accidents, Emergency management, Evacuations, Small modular reactors, Computer software, Coolants, Emergencies, Emergency response, Monte Carlo methods, Protective actions
Proceedings Papers

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Arttu Meriläinen, Olli Viljakainen, Karri Honkoila, Ari Lahtela
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, V001T01A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64294
https://doi.org/10.1115/ICONE28-64294
View Paper titled, Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model
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Topics: Engineering models, Nuclear power stations, Accidents, Circuits, Accident management, Computer software, Containment, Design, Diesel generators, Electronic systems