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Proceedings Papers

Finite Element Analysis of Rupture Pressure of Alloy 690 Stream Generator Tubes With Defects

Bin Zhang, Nai-Bin Jiang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134269
https://doi.org/10.1115/ICONE31-134269
View Paper titled, Finite Element Analysis of Rupture Pressure of Alloy 690 Stream Generator Tubes With Defects
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Topics: Alloys, Damage, Finite element analysis, Generators, Pressure, Rupture
Proceedings Papers

Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation

Wen Yin, Tiejun Zu, Liangzhi Cao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135163
https://doi.org/10.1115/ICONE31-135163
View Paper titled, Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation
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Topics: Damage, Displacement, Electrons, Neutrons, Particulate matter
Proceedings Papers

Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method

Baoxin Yuan, Huiyi Lv, Herong Zeng, Jie Zheng, Zihan Chen, Huan Huang, Songbao Zhang, Dazhi Qian
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132052
https://doi.org/10.1115/ICONE31-132052
View Paper titled, Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method
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Topics: Damage, Failure, Finite element methods, Fuels, Neutrons, Noise (Sound)
Proceedings Papers

A Nonlocal Meso-Scale Damage Model for Nuclear Graphite

Yan Ma, Yue Qian, Yuchen Hao, Musen Lin, Yue Li, Jinhua Wang, Haitao Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134775
https://doi.org/10.1115/ICONE31-134775
View Paper titled, A Nonlocal Meso-Scale Damage Model for Nuclear Graphite
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Topics: Damage, Failure, Graphite
Proceedings Papers

Monte Carlo Simulation of Response of Beta-Delayed Neutron Inspection System for Fuel Cladding Damage

Weihua Zhang, Liguo Zhang, Jianzhu Cao
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134218
https://doi.org/10.1115/ICONE31-134218
View Paper titled, Monte Carlo Simulation of Response of Beta-Delayed Neutron Inspection System for Fuel Cladding Damage
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Topics: Cladding systems (Building), Damage, Fuels, Inspection, Neutrons, Simulation
Proceedings Papers

C-14 in Geological Repositories: Source Terms and Transport Models

Zhengzhe Qu, Jingni Guo, Qi Zhang, Yu Wang, Mengjie Wu, Feng Xie, Liqiang Wei, Jianzhu Cao
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134283
https://doi.org/10.1115/ICONE31-134283
View Paper titled, C-14 in Geological Repositories: Source Terms and Transport Models
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Topics: Biological tissues, Carbon, Chain, China, Computer simulation, Damage, Diffusion (Physics), Food products, Groundwater, Hazards
Proceedings Papers

Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method

Churan Feng, Jingxiang Zhan, Lin Yan, Yiming Wang, Jinghua Zhou
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135096
https://doi.org/10.1115/ICONE31-135096
View Paper titled, Typical Sequence Analysis of SLOCA Accidents in a Third Generation Nuclear Power Plant Based on RISMC Method
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Topics: Accidents, Nuclear power stations, Safety, Failure, Damage, Design, Feedwater, Probability, Risk, Uncertainty
Proceedings Papers

The Mission Time Analysis in Level 2 Probabilistic Safety Assessment of the Third-Generation Nuclear Power Plant

Shujie Guo, Jing Liu, Yubao Zhong
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135680
https://doi.org/10.1115/ICONE31-135680
View Paper titled, The Mission Time Analysis in Level 2 Probabilistic Safety Assessment of the Third-Generation Nuclear Power Plant
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Topics: Accidents, Nuclear power stations, Probabilistic safety assessment, Containment, Concretes, Damage, Delays, Failure analysis, Modeling
Proceedings Papers

An Effect of Damage Rate on Mechanical Property Change and Microstructural Evolution in Proton-Irradiated Fe-Cu Alloys

Yusuke Noshi, Ken-Ichi Fukumoto, Ryoya Ishigami, Kinji Uda
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A031, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134568
https://doi.org/10.1115/ICONE31-134568
View Paper titled, An Effect of Damage Rate on Mechanical Property Change and Microstructural Evolution in Proton-Irradiated Fe-Cu Alloys
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Topics: Alloys, Damage, Dislocations, Hardening, Irradiation (Radiation exposure), Mechanical properties, Nanoindentation, Protons, Reactor vessels, Transmission electron microscopy
Proceedings Papers

Study on Stabilization Technology of Base Isolation Layer Using Air Floating Technology by Shaking Table Test

Aramaki Takuto, Osamu Furuya, Yoshiro Hiyama, Koji Yamazaki
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A072, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136046
https://doi.org/10.1115/ICONE31-136046
View Paper titled, Study on Stabilization Technology of Base Isolation Layer Using Air Floating Technology by Shaking Table Test
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Topics: Damage, Downtime, Earthquakes, Levitation, Performance evaluation, Springs, Stability, Stress, Vibration, Vibration isolation
Proceedings Papers

Research on Liability Insurance for Radioactive Sources and Suggestions to China

Xiao Ding Li, Yu Gong, Guang Hui Li, Gang Bai, Jie Ying Zheng, Yun Huan Qu, Zhe Li
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93505
https://doi.org/10.1115/ICONE29-93505
View Paper titled, Research on Liability Insurance for Radioactive Sources and Suggestions to China
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Topics: China, Damage, Insurance, Liabilities
Proceedings Papers

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Saifeng Wu, Wenguang Liu, Wenfu He
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92541
https://doi.org/10.1115/ICONE29-92541
View Paper titled, Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators
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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness
Proceedings Papers

Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite

Tianchen Zeng, Yuewen Sun, Peng Cong
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92295
https://doi.org/10.1115/ICONE29-92295
View Paper titled, Monte Carlo Simulation of In-Situ Multi-Scale Damage Detection of AGR Graphite
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Topics: Damage, Graphite, Simulation
Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90521
https://doi.org/10.1115/ICONE29-90521
View Paper titled, Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition
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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors
Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90146
https://doi.org/10.1115/ICONE29-90146
View Paper titled, Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)
Proceedings Papers

Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident

Fenglong Wang, Xuanlan Mei, Liang Zhang, Yong Yang, Qiang Zhang, Shixi Wang, Mingyu Wu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91511
https://doi.org/10.1115/ICONE29-91511
View Paper titled, Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident
Open the PDF for Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident in another window
Topics: Accidents, Central heating, Damage, Fuels, China, Design, Background radiation, Emergency management, Hazard analysis, Radioactive substances
Proceedings Papers

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Guogang Bao, Changdong Lu, Weiwei Wang, Ren Liang, Zhikang Lin, Yong Ouyang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89383
https://doi.org/10.1115/ICONE29-89383
View Paper titled, Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions
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Topics: Accidents, Cladding systems (Building), Coolants, Damage, Fuel rods, Heat, Pressure, Resonance ionization spectroscopy, Safety, Leakage
Proceedings Papers

Investigation the Fuel Damage Fraction of IB-LOCA

Zhidong Yue, Ting Wei, Wei Cai, Xiao Ke, Ying Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A055, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91811
https://doi.org/10.1115/ICONE29-91811
View Paper titled, Investigation the Fuel Damage Fraction of IB-LOCA
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Topics: Cladding systems (Building), Damage, Fuels
Proceedings Papers

Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Zhuang Shao, Ziqi Cai, Qingmin Zhang
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92600
https://doi.org/10.1115/ICONE29-92600
View Paper titled, Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3
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Topics: Damage, Displacement, Energy gap, Irradiation (Radiation exposure), Neutrons, Protons, Semiconductors (Materials), Simulation
Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92978
https://doi.org/10.1115/ICONE29-92978
View Paper titled, Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage
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Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints