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Proceedings Papers

The Study on Risk Assessment Method of Severe Accident Management Strategies in Nuclear Power Plants

Shipeng Niu, Yun Yu, Gaopeng Wang, Xinli Yu, Yang Liu, Jiarui Zhang, Yapei Zhang
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-127856
https://doi.org/10.1115/ICONE31-127856
View Paper titled, The Study on Risk Assessment Method of Severe Accident Management Strategies in Nuclear Power Plants
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Topics: Accident management, Artificial neural networks, Nuclear power stations, Risk assessment
Proceedings Papers

The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface

Bo Lin, Xiangyu Yun, Junying Xu, Dongshan Wei, Huiyong Zhang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A055, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93157
https://doi.org/10.1115/ICONE29-93157
View Paper titled, The Influence of Impurity Water for CHF on the Downward Facing Boiling Surface
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Topics: Boiling, Coating processes, Coatings, Concretes, Critical heat flux, Glass reinforced plastics, Water, Coolants, Accidents, Construction
Proceedings Papers

Research on Severe Accident Management Guidelines for HPR1000 NPP

Jiang Pingting, Chen Peng
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91849
https://doi.org/10.1115/ICONE29-91849
View Paper titled, Research on Severe Accident Management Guidelines for HPR1000 NPP
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Topics: Accident management, Nuclear power stations
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

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
Proceedings Papers

Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2

Ayato Takashima, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu
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, V003T12A006, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63285
https://doi.org/10.1115/ICONE28-63285
View Paper titled, Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2
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Topics: Accident management, Accidents, Boiling water reactors, Cavities
Proceedings Papers

Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions

Lindsay N. Gilkey, Nathan Andrews, Kyle Ross, Matthew Solom
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16547
https://doi.org/10.1115/ICONE2020-16547
View Paper titled, Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions
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Topics: Air flow, Computer simulation, Design, Testing, Turbines, Modeling, Batteries, Accidents, Safety, Water
Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16633
https://doi.org/10.1115/ICONE2020-16633
View Paper titled, Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents
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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids
Proceedings Papers

Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2

Kento Matsubara, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A020, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16182
https://doi.org/10.1115/ICONE2020-16182
View Paper titled, Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2
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Topics: Accident management, Accidents, Boiling water reactors
Proceedings Papers

Classification Analysis of Communication System of Nuclear Power Plant

Yu Yun, Zheng Shen, Liu Jing
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16235
https://doi.org/10.1115/ICONE2020-16235
View Paper titled, Classification Analysis of Communication System of Nuclear Power Plant
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Topics: Nuclear power stations, Pressurized water reactors, Reliability, Accidents, China, Design, Emergencies, Safety, Accident management, Emergency response
Proceedings Papers

Probabilistic Analysis of Creep-Induced SGTR for NPP

Wenjing Li, Wentao Zhu, Xinli Yu, Wei Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81032
https://doi.org/10.1115/ICONE26-81032
View Paper titled, Probabilistic Analysis of Creep-Induced SGTR for NPP
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Topics: Creep, Nuclear power stations, Accidents, Probability, Accident management, Boilers, Failure, Pipes, Pressure, Probabilistic safety assessment
Proceedings Papers

Incorporation of the Radioactive Interinfluence in Multi-Unit Seismic PRA

Shuhei Matsunaka, Chikahiro Sato, Manabu Watanabe
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81928
https://doi.org/10.1115/ICONE26-81928
View Paper titled, Incorporation of the Radioactive Interinfluence in Multi-Unit Seismic PRA
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Topics: Accident management, Accidents, Containment, Containment vessels, Damage, Earthquakes, Evaluation methods, Fukushima nuclear disaster, Japan, 2011, Hazards, Nuclear power stations
Proceedings Papers

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82074
https://doi.org/10.1115/ICONE26-82074
View Paper titled, Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000
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Topics: Accidents, Sensitivity analysis, Nuclear fission, Pressure, Boilers, Feedwater, Flow (Dynamics), Valves, Accident management, Nuclear reactor coolants
Proceedings Papers

Evaluation of the Kinetics of Molten Pool Stratification in Case of In-Vessel Melt Retention Strategy

L. Carénini, F. Fichot
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82243
https://doi.org/10.1115/ICONE26-82243
View Paper titled, Evaluation of the Kinetics of Molten Pool Stratification in Case of In-Vessel Melt Retention Strategy
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Topics: Vessels, Transients (Dynamics), Light water reactors, Chemistry, Pressurized water reactors, Accidents, Flux (Metallurgy), Heat, Heat flux, Metals
Proceedings Papers

A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors

F. Fichot, L. Carénini, W. Villanueva, S. Bechta
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82248
https://doi.org/10.1115/ICONE26-82248
View Paper titled, A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors
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Topics: Vessels, Safety, Transients (Dynamics), Flux (Metallurgy), Heat, Metals, Light water reactors, Critical heat flux, Heat flux, Steady state
Proceedings Papers

Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method

Xin Li, Ikken Sato, Akifumi Yamaji, Guangtao Duan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A023, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82037
https://doi.org/10.1115/ICONE26-82037
View Paper titled, Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method
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Topics: Concretes, Ablation (Vaporization technology), Particulate matter, Modeling, Containment, Metals, Accident management, Accidents, Cavities, Computer simulation
Proceedings Papers

Experimental Investigation on Boiling Flow Characteristics Under Passive IVR-ERVC Conditions

Fan Wang, Bo Kuang, Pengfei Liu, Longkun He
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A045, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82254
https://doi.org/10.1115/ICONE26-82254
View Paper titled, Experimental Investigation on Boiling Flow Characteristics Under Passive IVR-ERVC Conditions
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Topics: Boiling, Flow (Dynamics), Cooling, Reactor vessels, Oscillations, Accidents, Critical heat flux, Heat, Pressurized water reactors, Test facilities
Proceedings Papers

Experimental Study on the Steam Line Break (SLB) Accident With the Steam Generator Tube Rupture (SGTR)

Yusun Park, Byoung Uhn Bae, Jongrok Kim, Jae Bong Lee, Hae Min Park, Nam Hyun Choi, Kyoung Ho Kang, Kyung Doo Kim
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A041, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81458
https://doi.org/10.1115/ICONE26-81458
View Paper titled, Experimental Study on the Steam Line Break (SLB) Accident With the Steam Generator Tube Rupture (SGTR)
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Topics: Accidents, Boilers, Rupture, Steam, Failure, Simulation, Water, Accident management, Flow (Dynamics), Fluids
Proceedings Papers

Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR

Ikuo Kinoshita
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81920
https://doi.org/10.1115/ICONE26-81920
View Paper titled, Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR
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Topics: Boilers, Pressurized water reactors, Uncertainty analysis, Uncertainty, Accidents, Accident management, Coolants, High pressure (Physics), Reliability, System failures
Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82267
https://doi.org/10.1115/ICONE26-82267
View Paper titled, Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors
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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels