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Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022

Paper No: ICONE29-89568

DOI: https://doi.org/10.1115/ICONE29-89568

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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability

Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022

Paper No: ICONE29-89241

DOI: https://doi.org/10.1115/ICONE29-89241

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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density

Proceedings Papers

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Susumu Yamashita, Shinichiro Uesawa, Hiroyuki Yoshida

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A006, August 8–12, 2022

Paper No: ICONE29-89345

DOI: https://doi.org/10.1115/ICONE29-89345

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Topics: Computer simulation, Cooling, Fuels, Natural convection, Porous materials, Temperature, Accidents, Boiling water reactors, Computational fluid dynamics, Containment vessels

Proceedings Papers

Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR

Taisei Matsumoto, Akifumi Yamaji, Daisuke Fujiwara

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A005, August 8–12, 2022

Paper No: ICONE29-90648

DOI: https://doi.org/10.1115/ICONE29-90648

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Topics: Accidents, Boiling water reactors, Containment vessels, Nuclear fission, Thermal loads

Proceedings Papers

Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor

Masaki Shimizu, Hiroki Shishido, Hidetoshi Hashizume

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A014, August 4–6, 2021

Paper No: ICONE28-65139

DOI: https://doi.org/10.1115/ICONE28-65139

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Topics: Boiling water reactors, Fuels, Fusion reactors, Light water reactors

Proceedings Papers

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

Sheng-Dih Hwang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A029, August 4–6, 2021

Paper No: ICONE28-65413

DOI: https://doi.org/10.1115/ICONE28-65413

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Topics: Boiling water reactors, Temperature, Accidents, Control rooms, Engineering simulation, Nuclear reactors, Probability, Simulation

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

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata

Paper No: ICONE28-65129

DOI: https://doi.org/10.1115/ICONE28-65129

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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons

Proceedings Papers

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi

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, V001T06A013, August 4–5, 2020

Paper No: ICONE2020-16405

DOI: https://doi.org/10.1115/ICONE2020-16405

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Topics: Reactor vessels, Stress corrosion cracking, Titanium dioxide, Water, Flow (Dynamics), Computational fluid dynamics, Resolution (Optics), Risk, Boiling water reactors, Catalysts

Proceedings Papers

Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor

Ying Yue, Walter Villanueva, Hongdi Wang, Dingqu Wang

Paper No: ICONE2020-16236

DOI: https://doi.org/10.1115/ICONE2020-16236

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Topics: Accidents, Boiling water reactors, Failure, Failure mechanisms, Instrumentation, Thermomechanics

Proceedings Papers

Development of New Organic Iodine Filter for FCVS

Kazuo Tominaga, Sohei Fukui, Motoi Tanaka, Tomoharu Hashimoto, Ryuichi Tayama

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A039, August 4–5, 2020

Paper No: ICONE2020-16416

DOI: https://doi.org/10.1115/ICONE2020-16416

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Topics: Filters, Silver, Water, Aerosols, Accidents, Aerosol containers, Boiling water reactors, Bonding, Containment, Electromagnetic scattering

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

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

Identify the Broken Loop and Break Sizes of Recirculation Line LOCA for a BWR6/MarkIII Plant

Sheng-Dih Hwang, Te-Chuan Wang

Paper No: ICONE2020-16089

DOI: https://doi.org/10.1115/ICONE2020-16089

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Topics: Boiling water reactors, Control rooms, Nuclear power stations, Probability, Steady state, Temperature

Proceedings Papers

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

Hironobu Iwanami, Tomoharu Hashimoto, Motoi Tanaka, Ryuichi Tayama, Satoshi Mizuno, Takashi Uemura

Paper No: ICONE2020-16721

DOI: https://doi.org/10.1115/ICONE2020-16721

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Topics: Boiling water reactors, Accidents, Evaluation methods, Pipes, Nuclear fission, Water, Coolants, Design, Evacuations, Pressure

Proceedings Papers

A New Data Driven Method for Monitoring a Large Number of Process Values and Detecting Anomaly Signs With a Two-Stage Model Composed of a Time Window Autoencoder and a Deviation Autoencoder

Susumu Naito, Yasunori Taguchi, Yuichi Kato, Kouta Nakata, Ryota Miyake, Isaku Nagura, Shinya Tominaga, Toshio Aoki

Paper No: ICONE2020-16150

DOI: https://doi.org/10.1115/ICONE2020-16150

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Topics: Boiling water reactors, Machine learning, Noise (Sound), Nuclear power stations, Temperature, Time series, Transients (Dynamics)

Proceedings Papers

Multi-Group Staggered Tests for Highly Redundant Systems

Shota Soga

Paper No: ICONE2020-16172

DOI: https://doi.org/10.1115/ICONE2020-16172

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Topics: Boiling water reactors, Failure, Notch testing, Reactor protection systems, Redundancy (Engineering), Reliability, Risk, Rods, Safety

Proceedings Papers

CFD Modelling of Flashing Instability in Natural Circulation Cooling Systems

Yixiang Liao, Christoph Schuster, Suqing Hu, Dirk Lucas

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A026, July 22–26, 2018

Paper No: ICONE26-81787

DOI: https://doi.org/10.1115/ICONE26-81787

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Topics: Computational fluid dynamics, Cooling systems, Flashing, Modeling, Flow (Dynamics), Fluids, Pipeline risers, Risers (Casting), Turbulence, Boiling

Proceedings Papers

CFD Modeling of Annular Flow With a Three-Field Approach

Salvatore Raddino, Tobias Strömgren, Yann Le Moigne, Jean-Marie Le Corre

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A040, July 22–26, 2018

Paper No: ICONE26-82351

DOI: https://doi.org/10.1115/ICONE26-82351

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Topics: Computational fluid dynamics, Flow (Dynamics), Modeling, Drops, Liquid films, Steam, Boiling water reactors, Critical heat flux, Momentum

Proceedings Papers

Unsteady CFD Analyses of the Thermal Mixing of the Feedwater in the Downcomer of a BWR

Yann Le Moigne

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A035, July 22–26, 2018

Paper No: ICONE26-82179

DOI: https://doi.org/10.1115/ICONE26-82179

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Topics: Boiling water reactors, Computational fluid dynamics, Feedwater, Water, Design, Fluctuations (Physics), Reactor vessels, Temperature, Transients (Dynamics), High temperature

Proceedings Papers

Overview of PSA for the UK ABWR Generic Design Assessment

Naoki Hirokawa, Yuki Ishiwatari, Daisuke Taniguchi, Kohei Hisamochi

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A023, July 22–26, 2018

Paper No: ICONE26-82553

DOI: https://doi.org/10.1115/ICONE26-82553

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Topics: Design, Risk, Safety, Boiling water reactors, Damage, Model development, Probabilistic safety assessment

2 3 4 5

NARROW

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR

Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

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

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor

Development of New Organic Iodine Filter for FCVS

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

Identify the Broken Loop and Break Sizes of Recirculation Line LOCA for a BWR6/MarkIII Plant

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

A New Data Driven Method for Monitoring a Large Number of Process Values and Detecting Anomaly Signs With a Two-Stage Model Composed of a Time Window Autoencoder and a Deviation Autoencoder

Multi-Group Staggered Tests for Highly Redundant Systems

CFD Modelling of Flashing Instability in Natural Circulation Cooling Systems

CFD Modeling of Annular Flow With a Three-Field Approach

Unsteady CFD Analyses of the Thermal Mixing of the Feedwater in the Downcomer of a BWR

Overview of PSA for the UK ABWR Generic Design Assessment

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