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Proceedings Papers

Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands

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Guang Du, Danfeng Zhao, Daping Lin, Xiaoxia Chen
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135047
https://doi.org/10.1115/ICONE31-135047
View Paper titled, Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands
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Topics: Floods, Nuclear power stations, Design, Hazards, Safety, Water, Computational methods, Engineering design, Evaluation methods, Nuclear power
Proceedings Papers

JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data From HTGR Type Fuel Irradiation Tests

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Shoichiro Okita, Takeshi Aoki, Yuji Fukaya, Yukio Tachibana
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131748
https://doi.org/10.1115/ICONE31-131748
View Paper titled, JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data From HTGR Type Fuel Irradiation Tests
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Topics: Fuels, Irradiation (Radiation exposure), Very high temperature reactors, Heat, Nuclides, Accuracy and precision, Errors, Evaluation methods, Nuclear power, Power density
Proceedings Papers

Study on Evaluation Method of Radial Power Reference Distribution of PWR

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Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89360
https://doi.org/10.1115/ICONE29-89360
View Paper titled, Study on Evaluation Method of Radial Power Reference Distribution of PWR
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Topics: Evaluation methods, Manufacturing, Pressurized water reactors, Safety, Accidents, Computer programming, Design, Engineers, Steam
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90288
https://doi.org/10.1115/ICONE29-90288
View Paper titled, 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
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Topics: Evaluation methods, Pressure, Reactor vessels, Sodium fast reactors, Vortices
Proceedings Papers

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

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Baoquan Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90277
https://doi.org/10.1115/ICONE29-90277
View Paper titled, Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example
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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93561
https://doi.org/10.1115/ICONE29-93561
View Paper titled, Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91604
https://doi.org/10.1115/ICONE29-91604
View Paper titled, Study on High Frequency Flow Induced Vibration Mechanism and Evaluation Method of PWR Fuel Assembly Grid
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Topics: Evaluation methods, Flow (Dynamics), Flow-induced vibrations, Fuels, Manufacturing, Pressurized water reactors
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64300
https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62354
https://doi.org/10.1115/ICONE28-62354
View Paper titled, Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65152
https://doi.org/10.1115/ICONE28-65152
View Paper titled, Research on Internal Fire Ignition Frequency of Fire Probability Safety Analysis in Small Module Reactor
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Topics: Fire, Ignition, Probability, Safety, Design, Evaluation methods, Innovation, Sensitivity analysis
Proceedings Papers

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62135
https://doi.org/10.1115/ICONE28-62135
View Paper titled, Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64586
https://doi.org/10.1115/ICONE28-64586
View Paper titled, Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems
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Topics: Dynamic response, Piping systems, Pipes, Evaluation methods, Design, Mechanical behavior, Nuclear power stations, Probabilistic risk assessment, Structures
Proceedings Papers

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

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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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16691
https://doi.org/10.1115/ICONE2020-16691
View Paper titled, Application of AHP - Fuzzy Evaluation Method in Nuclear Power Plant Site Selection
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16418
https://doi.org/10.1115/ICONE2020-16418
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Design, Flow (Dynamics), Sodium fast reactors, Vortices, Computational fluid dynamics, Reactor vessels, Water, Coolants, Evaluation methods, Particulate matter
Proceedings Papers

A New Safety Margin Evaluation Method: Quality Margin Method

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Zhao Minfu, Duan Minghui, Lv Yufeng
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16031
https://doi.org/10.1115/ICONE2020-16031
View Paper titled, A New Safety Margin Evaluation Method: Quality Margin Method
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Topics: Critical heat flux, Evaluation methods, Safety, Design, Heat, Nucleate boiling, Accidents, Computational methods, Flux (Metallurgy), Heating
Proceedings Papers

Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force

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Hisashi Koike, Masaji Mori, Daisuke Fujiwara, Takashi Shimomura
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81468
https://doi.org/10.1115/ICONE26-81468
View Paper titled, Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force
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Topics: ASME Standards, Compression, Earthquakes, Evaluation methods, Fuels, Manufacturing, Plasticity, Plastics, Pressurized water reactors, Stress
Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

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Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81143
https://doi.org/10.1115/ICONE26-81143
View Paper titled, Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results
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Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles
Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

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Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81144
https://doi.org/10.1115/ICONE26-81144
View Paper titled, Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method
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Topics: Cavity flows, Evaluation methods, Modeling, Pipes, Thermal stratification, Fatigue, High temperature, Temperature, Water, Cycles
Proceedings Papers

Development of Techniques for RCP Performance Verification Test and Optimization of Flow Stability

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Seok Kim, Byoung-Uhn Bae, Yun-Je Cho, Woo-Jin Jeon, Yeon-Sik Kim, Seok Cho
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A030, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82091
https://doi.org/10.1115/ICONE26-82091
View Paper titled, Development of Techniques for RCP Performance Verification Test and Optimization of Flow Stability
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Topics: Flow (Dynamics), Optimization, Stability, Test facilities, Design, Electricity (Physics), Evaluation methods, Measurement systems, Nuclear power, Nuclear power stations