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Proceedings Papers

Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR

Tamás Varju, Attila Kiss, Csenge Antók, Boglárka Babcsány, Ildikó Boros, Péter Mészáros, Zeno Bertesina, Szabolcs Czifrus
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135760
https://doi.org/10.1115/ICONE31-135760
View Paper titled, Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR
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Topics: Biomedical engineering, Supercritical water reactors, Design, Fuels, Physics, Circuits, Computational fluid dynamics, Computer software, Finite element analysis, Heat
Proceedings Papers

SAMPO-P Test Facility and Numerical Pretest

Pengya Guo, Peng Yu, Fengyang Quan, Wei Li, Jie Pei, Yidan Yuan, Jiyang Yu, Weimin Ma
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A091, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135932
https://doi.org/10.1115/ICONE31-135932
View Paper titled, SAMPO-P Test Facility and Numerical Pretest
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Topics: Accidents, Alloys, Computer simulation, Density, Engineering simulation, Flow (Dynamics), Heat flux, Heat transfer, Heating, Metals
Proceedings Papers

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

Study on the Remelting Process of the Debris Bed in the Lower Head of Reactor Pressure Vessel Based on Lattice Boltzmann Method

Shang Shi, Liangxing Li, Weimin Ma, Xiao Zeng, Yidan Yuan, Zhenxin Lei, Zutao Xiang, Xiangyang Xu
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136038
https://doi.org/10.1115/ICONE31-136038
View Paper titled, Study on the Remelting Process of the Debris Bed in the Lower Head of Reactor Pressure Vessel Based on Lattice Boltzmann Method
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Topics: Lattice Boltzmann methods, Reactor vessels
Proceedings Papers

Study on Application of the Single-Curvature Polyhedron Hydro-Bulging Technology in Metallic Reactor Containment

Jianling Dong, Xingcheng Huang, Ke Chen, Bohao Ning
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134806
https://doi.org/10.1115/ICONE31-134806
View Paper titled, Study on Application of the Single-Curvature Polyhedron Hydro-Bulging Technology in Metallic Reactor Containment
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Topics: Containment, Containment vessels, Nuclear reactors, Steel, Vessels, Manufacturing, Aircraft, Blanks, Boilers, High-pressure vessels
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

Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors

Jian Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A060, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135397
https://doi.org/10.1115/ICONE31-135397
View Paper titled, Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors
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Topics: Accidents, Flow (Dynamics), Numerical analysis, Sodium fast reactors, Transients (Dynamics), Reactor vessels, Pressure, Sodium, Cavities, Vapors
Proceedings Papers

Development of a Nonintrusive ROM for Parametric Study in the RPV Lower Plenum

He Shang, Minjun Peng, Genglei Xia, Shiqi Zhang, Shijie Zhu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A034, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134678
https://doi.org/10.1115/ICONE31-134678
View Paper titled, Development of a Nonintrusive ROM for Parametric Study in the RPV Lower Plenum
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Topics: Computation, Computational fluid dynamics, Coolants, Errors, Flow (Dynamics), Principal component analysis, Reactor vessels, Simulation, Steady state
Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91791
https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant

Yanming Shi, Zhenying Wang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92804
https://doi.org/10.1115/ICONE29-92804
View Paper titled, Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant
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Topics: Decision making, Emergencies, Nuclear power stations, Reactor vessels, Water
Proceedings Papers

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Lingmei Xiao, Bing Zhang, Ming Wang, Zhiwen Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92450
https://doi.org/10.1115/ICONE29-92450
View Paper titled, Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant
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Topics: Floods, Nuclear power stations, Reactor vessels, Risk, Vessels
Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92462
https://doi.org/10.1115/ICONE29-92462
View Paper titled, PSA Application in UK HPR1000 Numerical Targets Evaluation
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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety
Proceedings Papers

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Guanhui Xie, Runcheng Li, Tianyi Wei, Zhikang Lin, Dongyang Li, Sichao Tan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89228
https://doi.org/10.1115/ICONE29-89228
View Paper titled, Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions
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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics
Proceedings Papers

Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

Jun Pan, Chang Liu, Xihui Su
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93037
https://doi.org/10.1115/ICONE29-93037
View Paper titled, Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels
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Topics: Acceptance criteria, In-service inspection, Reactor vessels, Safety
Proceedings Papers

Study on Forging Technology of Integrated Topcover Forging for AP1000 Reactor Pressure Vessel

Zhaoyin Li, Kai Dong, Zhiyong Tao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A043, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92966
https://doi.org/10.1115/ICONE29-92966
View Paper titled, Study on Forging Technology of Integrated Topcover Forging for AP1000 Reactor Pressure Vessel
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Topics: Forging, Reactor vessels, Simulation
Proceedings Papers

Manufacturing Technology of Thick-Walled Integrated Cylinder With Large-Sized Side Nozzles for Nuclear Pressure Vessel

Shaofei Li
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A028, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92302
https://doi.org/10.1115/ICONE29-92302
View Paper titled, Manufacturing Technology of Thick-Walled Integrated Cylinder With Large-Sized Side Nozzles for Nuclear Pressure Vessel
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Topics: Cylinders, Forging, Manufacturing technology, Nozzles, Reactor vessels
Proceedings Papers

Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

Kexin Cai, Ping Huang, Wangjie Qian, Minyu Fan, Shuang Qi, Guodong Zhang, Yanwei Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A044, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92513
https://doi.org/10.1115/ICONE29-92513
View Paper titled, Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel
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Topics: Embrittlement, Radiation (Physics), Reactor vessels
Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89268
https://doi.org/10.1115/ICONE29-89268
View Paper titled, Nuclear Power Plant Design Optimization Based on Risk-Informed Method
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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage
Proceedings Papers

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89165
https://doi.org/10.1115/ICONE29-89165
View Paper titled, Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design
Proceedings Papers

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Jianbang Tang, Yukun Wu, Weiqiang Wang, Guanbing Ma, Chenming Zeng, Junlong Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A048, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92644
https://doi.org/10.1115/ICONE29-92644
View Paper titled, Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals
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Topics: Inspection, Nuclear power stations, Nondestructive evaluation, Design, High pressure (Physics), High temperature, In-service inspection, Irradiation (Radiation exposure), Nuclear fuels, Probes