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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89345
https://doi.org/10.1115/ICONE29-89345
View Paper titled, Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90648
https://doi.org/10.1115/ICONE29-90648
View Paper titled, Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR
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Topics: Accidents, Boiling water reactors, Containment vessels, Nuclear fission, Thermal loads
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89568
https://doi.org/10.1115/ICONE29-89568
View Paper titled, The Investigation on Geysering in Scaling Analyses of Natural Circulation
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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65139
https://doi.org/10.1115/ICONE28-65139
View Paper titled, Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65413
https://doi.org/10.1115/ICONE28-65413
View Paper titled, The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR
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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
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

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

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata
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, V003T11A012, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65129
https://doi.org/10.1115/ICONE28-65129
View Paper titled, Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test
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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons
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
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, V001T01A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16236
https://doi.org/10.1115/ICONE2020-16236
View Paper titled, Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16416
https://doi.org/10.1115/ICONE2020-16416
View Paper titled, Development of New Organic Iodine Filter for FCVS
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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
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

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

Sheng-Dih Hwang, Te-Chuan Wang
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16089
https://doi.org/10.1115/ICONE2020-16089
View Paper titled, Identify the Broken Loop and Break Sizes of Recirculation Line LOCA for a BWR6/MarkIII Plant
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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
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A049, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16721
https://doi.org/10.1115/ICONE2020-16721
View Paper titled, Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant
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Topics: Boiling water reactors, Accidents, Evaluation methods, Pipes, Nuclear fission, Water, Coolants, Design, Evacuations, Pressure
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16405
https://doi.org/10.1115/ICONE2020-16405
View Paper titled, Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel
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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

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
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16150
https://doi.org/10.1115/ICONE2020-16150
View Paper titled, 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
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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
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16172
https://doi.org/10.1115/ICONE2020-16172
View Paper titled, Multi-Group Staggered Tests for Highly Redundant Systems
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Topics: Boiling water reactors, Failure, Notch testing, Reactor protection systems, Redundancy (Engineering), Reliability, Risk, Rods, Safety
Proceedings Papers

A Core Design of Innovative Breeder BWR

Guo Rui, Akifumi Yamaji, Yun Cai, Xingjie Peng
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, V001T13A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82079
https://doi.org/10.1115/ICONE26-82079
View Paper titled, A Core Design of Innovative Breeder BWR
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Topics: Boiling water reactors, Design, Manufacturing, Water, Atoms, Cooling, Fuels, Neutrons, Economics , Heavy metals
Proceedings Papers

iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350

Tanaka Go, Sato Takashi, Komori Yuji, Matsumoto Keiji
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, V001T13A025, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82552
https://doi.org/10.1115/ICONE26-82552
View Paper titled, iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350
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Topics: Optimization, Safety, Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Heat, Boiling water reactors, Condensers (steam plant), Cooling systems, Cylinders
Proceedings Papers

iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)

Takashi Sato, Keiji Matsumoto, Kenji Hosomi, Keisuke Taguchi
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, V001T13A023, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82428
https://doi.org/10.1115/ICONE26-82428
View Paper titled, iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)
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Topics: Defense industry, Safety, Containment, Containment buildings, Boiling water reactors, Condensers (steam plant), Containment systems, Cooling systems, Design, Domes (Structural elements)
Proceedings Papers

Analysis of Vibrations due to the Steam Condensation at Sub-Atmospheric Condition

G. Giambartolomei, R. Lo Frano, D. Mazed, D. Del Serra, D. Aquaro
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A026, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82378
https://doi.org/10.1115/ICONE26-82378
View Paper titled, Analysis of Vibrations due to the Steam Condensation at Sub-Atmospheric Condition
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Topics: Condensation, Steam, Vibration, Oscillations, Flow (Dynamics), Pressure, Water, Boiling water reactors, Cooling systems, Damage