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Proceedings Papers

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

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

Paper No: ICONE29-92239

DOI: https://doi.org/10.1115/ICONE29-92239

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Topics: Design, Feedback, Vessels, Nuclear power stations, Safety, Accident management, Accidents, Construction, Control panels, Control rooms

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

Paper No: ICONE29-91849

DOI: https://doi.org/10.1115/ICONE29-91849

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Topics: Accident management, Nuclear power stations

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

Paper No: ICONE29-93157

DOI: https://doi.org/10.1115/ICONE29-93157

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Topics: Boiling, Coating processes, Coatings, Concretes, Critical heat flux, Glass reinforced plastics, Water, Coolants, Accidents, Construction

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

Paper No: ICONE28-64294

DOI: https://doi.org/10.1115/ICONE28-64294

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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

Paper No: ICONE28-63285

DOI: https://doi.org/10.1115/ICONE28-63285

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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

Paper No: ICONE2020-16547

DOI: https://doi.org/10.1115/ICONE2020-16547

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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

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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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

Paper No: ICONE2020-16182

DOI: https://doi.org/10.1115/ICONE2020-16182

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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

Paper No: ICONE2020-16235

DOI: https://doi.org/10.1115/ICONE2020-16235

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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

Paper No: ICONE26-81032

DOI: https://doi.org/10.1115/ICONE26-81032

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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

Paper No: ICONE26-81928

DOI: https://doi.org/10.1115/ICONE26-81928

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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

Paper No: ICONE26-82074

DOI: https://doi.org/10.1115/ICONE26-82074

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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

Paper No: ICONE26-82243

DOI: https://doi.org/10.1115/ICONE26-82243

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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

Paper No: ICONE26-82248

DOI: https://doi.org/10.1115/ICONE26-82248

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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

Development of Hydrogen Treatment System in Severe Accident: Part 4 — Study of Fission Products and Steam Effect on Hydrogen Treatment Characteristics

Akira Yamada, Motoshige Yagyu, Chikako Iwaki, Tsukasa Sugita, Yoshiko Haruguchi, Masashi Tanabe

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A024, July 22–26, 2018

Paper No: ICONE26-81759

DOI: https://doi.org/10.1115/ICONE26-81759

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Topics: Accidents, Hydrogen, Nuclear fission, Steam, Vents, Boiling water reactors, Pressure, Manganese dioxide, Metals, Oxidation

Proceedings Papers

Development and Validation of a Correlation for Wet Resuspension Simulation

Tobias Jankowski, Marco K. Koch

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A005, July 22–26, 2018

Paper No: ICONE26-81286

DOI: https://doi.org/10.1115/ICONE26-81286

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Topics: Accident management, Accidents, Aerosols, Boiling, Bubbles, Circuits, Condensed matter, Containment, Coolants, Cooling

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

Paper No: ICONE26-82037

DOI: https://doi.org/10.1115/ICONE26-82037

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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

Paper No: ICONE26-82254

DOI: https://doi.org/10.1115/ICONE26-82254

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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

Paper No: ICONE26-81458

DOI: https://doi.org/10.1115/ICONE26-81458

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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

Paper No: ICONE26-81920

DOI: https://doi.org/10.1115/ICONE26-81920

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Topics: Boilers, Pressurized water reactors, Uncertainty analysis, Uncertainty, Accidents, Accident management, Coolants, High pressure (Physics), Reliability, System failures

2 3 4 5

NARROW

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

Research on Severe Accident Management Guidelines for HPR1000 NPP

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

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

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

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

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

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

Classification Analysis of Communication System of Nuclear Power Plant

Probabilistic Analysis of Creep-Induced SGTR for NPP

Incorporation of the Radioactive Interinfluence in Multi-Unit Seismic PRA

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

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

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

Development of Hydrogen Treatment System in Severe Accident: Part 4 — Study of Fission Products and Steam Effect on Hydrogen Treatment Characteristics

Development and Validation of a Correlation for Wet Resuspension Simulation

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

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

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

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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