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Proceedings Papers

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A015, August 8–12, 2022
Paper No: ICONE29-93561
DOI: https://doi.org/10.1115/ICONE29-93561
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Topics: China, Vessels, Bullets, Computational methods, Computer software, Evaluation methods, Fatigue, Fatigue analysis, Geometry, Nozzles
Proceedings Papers

Study on High Frequency Flow Induced Vibration Mechanism and Evaluation Method of PWR Fuel Assembly Grid

Jie Ding, Chaozhu Zhang, Jingya Sun, Fujun Gan, Shuhe Gong
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A046, August 8–12, 2022
Paper No: ICONE29-91604
DOI: https://doi.org/10.1115/ICONE29-91604
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Topics: Evaluation methods, Flow (Dynamics), Flow-induced vibrations, Fuels, Manufacturing, Pressurized water reactors
Proceedings Papers

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A012, August 8–12, 2022
Paper No: ICONE29-89360
DOI: https://doi.org/10.1115/ICONE29-89360
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Topics: Evaluation methods, Manufacturing, Pressurized water reactors, Safety, Accidents, Computer programming, Design, Engineers, Steam
Proceedings Papers

Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example

Baoquan Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A010, August 8–12, 2022
Paper No: ICONE29-90277
DOI: https://doi.org/10.1115/ICONE29-90277
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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction
Proceedings Papers

Development of Evaluation Method of Gas Entrainment on the Free Surface in the Reactor Vessel in Pool-Type Sodium-Cooled Fast Reactors -Gas Entrainment Judgment Based on Three-Dimensional Evaluation of Vortex Center Line and Distribution of Pressure Decrease

Kentarou Matsushita, Toshiki Ezure, Yasutomo Imai, Tatsuya Fujisaki, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A007, August 8–12, 2022
Paper No: ICONE29-90288
DOI: https://doi.org/10.1115/ICONE29-90288
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Topics: Evaluation methods, Pressure, Reactor vessels, Sodium fast reactors, Vortices
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
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, V001T02A009, August 4–6, 2021
Paper No: ICONE28-64300
DOI: https://doi.org/10.1115/ICONE28-64300
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Zhipeng Feng, Huanhuan Qi, Xuan Huang, Guo Chen, Shuai Liu, Yixiong Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A003, August 4–6, 2021
Paper No: ICONE28-62135
DOI: https://doi.org/10.1115/ICONE28-62135
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Topics: Flow-induced vibrations, Fuel rods, Wear, Fuels, Manufacturing, Design, Fluid density, Pressurized water reactors, Evaluation methods, Excitation
Proceedings Papers

Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems

Yukihiko Okuda, Akemi Nishida, Michiya Sakai, Yuzo Shiogama, Yinsheng Li
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, V001T02A023, August 4–6, 2021
Paper No: ICONE28-64586
DOI: https://doi.org/10.1115/ICONE28-64586
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Topics: Dynamic response, Piping systems, Pipes, Evaluation methods, Design, Mechanical behavior, Nuclear power stations, Probabilistic risk assessment, Structures
Proceedings Papers

Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Masaaki Tanaka, Hidemasa Yamano, Kennichi Igawa
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, V003T09A001, August 4–6, 2021
Paper No: ICONE28-62354
DOI: https://doi.org/10.1115/ICONE28-62354
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Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors
Proceedings Papers

Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor

Yanzhu Chen, Zhichao Yang
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, V003T13A009, August 4–6, 2021
Paper No: ICONE28-65152
DOI: https://doi.org/10.1115/ICONE28-65152
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Topics: Fire, Ignition, Probability, Safety, Design, Evaluation methods, Innovation, Sensitivity analysis
Proceedings Papers

A New Safety Margin Evaluation Method: Quality Margin Method

Zhao Minfu, Duan Minghui, Lv Yufeng
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A003, August 4–5, 2020
Paper No: ICONE2020-16031
DOI: https://doi.org/10.1115/ICONE2020-16031
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Topics: Critical heat flux, Evaluation methods, Safety, Design, Heat, Nucleate boiling, Accidents, Computational methods, Flux (Metallurgy), Heating
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
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

Application of AHP - Fuzzy Evaluation Method in Nuclear Power Plant Site Selection

Yujie Sun, Changzhi Chen
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, V001T06A021, August 4–5, 2020
Paper No: ICONE2020-16691
DOI: https://doi.org/10.1115/ICONE2020-16691
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Topics: Evaluation methods, Nuclear power stations
Proceedings Papers

Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field

Mao Uchida, Moe Hirakawa, Aaru Sano, Keisuke Inoue, Takaaki Sakai, Toshiki Ezure, Masaaki Tanaka
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A009, August 4–5, 2020
Paper No: ICONE2020-16418
DOI: https://doi.org/10.1115/ICONE2020-16418
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Topics: Design, Flow (Dynamics), Sodium fast reactors, Vortices, Computational fluid dynamics, Reactor vessels, Water, Coolants, Evaluation methods, Particulate matter
Proceedings Papers

Study on Gas Entrainment From Unstable Drifting Vortexes on Liquid Surface

Moe Hirakawa, Yuichiro Kikuchi, Takaaki Sakai, Masaaki Tanaka, Hiroyuki Ohshima
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A091, July 22–26, 2018
Paper No: ICONE26-82477
DOI: https://doi.org/10.1115/ICONE26-82477
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Topics: Vortices, Flow (Dynamics), Computational fluid dynamics, Water, Reactor vessels, Sodium fast reactors, Coolants, Design, Design methodology, Evaluation methods
Proceedings Papers

Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method

Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A032, July 22–26, 2018
Paper No: ICONE26-82568
DOI: https://doi.org/10.1115/ICONE26-82568
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Topics: Creep, Damage, Evaluation methods, Pipes, Accidents, Constitutive equations, Failure, Failure analysis, Finite element analysis, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Demonstrative HEAF (High Energy Arcing Fault) Fire Tests of High and Low Voltage Switchgears of Nuclear Power Plants

Koji Shirai, Tsukasa Miyagi, Mikimasa Iwata, Koji Tasaka, Junghoon Ji
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A028, July 22–26, 2018
Paper No: ICONE26-82177
DOI: https://doi.org/10.1115/ICONE26-82177
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Topics: Fire testing, Nuclear power stations, Fire, Damage, Cables, Circuit breakers, Circuits, Copper, Design, Earthquakes
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

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018
Paper No: ICONE26-82619
DOI: https://doi.org/10.1115/ICONE26-82619
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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants
Proceedings Papers

The Development of the Advanced Method for the Source Term Evaluation Applicable to the Dynamic PRA

Koichi Nakamura, Sunghyon Jang, Akira Yamaguchi
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A045, July 22–26, 2018
Paper No: ICONE26-82523
DOI: https://doi.org/10.1115/ICONE26-82523
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Topics: Accidents, Containment, Evaluation methods, Nuclear fission, Nuclear power stations, Probabilistic risk assessment, Risk, Safety, Stress