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Proceedings Papers

Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned

Tiphaine Le Morvan, Arièle Défossez, Mickaël Kreitz
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90907
https://doi.org/10.1115/ICONE29-90907
View Paper titled, Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned
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Topics: Hazards, Meteorology, Nuclear power stations, Safety, Wind, Collaboration, Modeling, Natural phenomena, Nuclear engineers, Nuclear power
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92872
https://doi.org/10.1115/ICONE29-92872
View Paper titled, Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)
Proceedings Papers

Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions

Rong Liu, Liwen Yang, Shengyu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A069, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91981
https://doi.org/10.1115/ICONE29-91981
View Paper titled, Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions
Open the PDF for Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions in another window
Topics: Cladding systems (Building), Fuels, Pressurized water reactors, Transients (Dynamics)
Proceedings Papers

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference

Ruicheng Zhong, Yugao Ma, Qingzhu Zhao, Jian Deng, Yu Liu, Shuhua Ding
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A085, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92202
https://doi.org/10.1115/ICONE29-92202
View Paper titled, A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference
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Topics: Condensation, Evaporation, Flow (Dynamics), Heat pipes, Sodium, Temperature, Thermal resistance, Transients (Dynamics), Steady state, Heat transfer
Proceedings Papers

Propulsion Control of Marine Nuclear Reactor by Hardware-in-the-Loop Simulation (HILS)

Ao Zhang, Xiang Wang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A046, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91544
https://doi.org/10.1115/ICONE29-91544
View Paper titled, Propulsion Control of Marine Nuclear Reactor by Hardware-in-the-Loop Simulation (HILS)
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Topics: Hardware, Nuclear power, Nuclear reactors, Propulsion, Simulation, Feedback, Computer software, Simulation models, Steady state, Transients (Dynamics)
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
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

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

Optimization of Transient Control Method for RCV System

Yong Qiang Huang, Zhi Lin Chen, Xin Chen, Zheng Gu, Han Min Chen, Run Ze Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93279
https://doi.org/10.1115/ICONE29-93279
View Paper titled, Optimization of Transient Control Method for RCV System
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Topics: Optimization, Transients (Dynamics)
Proceedings Papers

Quality Analysis and Abnormal Repair of Transient Monitoring Data of CPR1000 Unit

Wangjie Qian, Zhilin Chen, Feng Lv, Yanwei Zhang, Zheng Gu, Xin Chen, Hanming Chen, Nianqing Fan
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A085, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93587
https://doi.org/10.1115/ICONE29-93587
View Paper titled, Quality Analysis and Abnormal Repair of Transient Monitoring Data of CPR1000 Unit
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Topics: Maintenance, Nuclear power stations, Statistics, Transients (Dynamics)
Proceedings Papers

Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube

Xifeng Lu, Furui Xiong, Xinjun Wang, Honglei Ai, Bingjin Li, Xuejiao Shao, Kang Yang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90677
https://doi.org/10.1115/ICONE29-90677
View Paper titled, Study on Analysis Method of LOCA Dynamic Response for Steam Generator Heat Transfer Tube
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Topics: Boilers, Dynamic response, Heat transfer, Time-domain analysis, Stress, Modal analysis, Dynamic response analysis, Emission spectroscopy, Finite element model, Frequency-domain analysis
Proceedings Papers

Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant

Run Ze Zhang, Zhi Lin Chen, Yong Qiang Huang, Xin Chen
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A058, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92874
https://doi.org/10.1115/ICONE29-92874
View Paper titled, Research on Intelligent Classification Method of Primary Loop Transient in Nuclear Power Plant
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Topics: Machine learning, Nuclear power stations, Transients (Dynamics)
Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94534
https://doi.org/10.1115/ICONE29-94534
View Paper titled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core
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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization
Proceedings Papers

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Xiaolin Chen, Simon Li, Songbai Cheng
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92109
https://doi.org/10.1115/ICONE29-92109
View Paper titled, Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code
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Topics: Accidents, Flow (Dynamics), Sodium fast reactors, Three-dimensional models, Transients (Dynamics)
Proceedings Papers

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91761
https://doi.org/10.1115/ICONE29-91761
View Paper titled, Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR
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Topics: Hydrogen production, Thermal loads, Transients (Dynamics), Very high temperature reactors, Coolants, Temperature, Control systems, Simulation, Carbon, Heat
Proceedings Papers

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Satoshi Okajima, Takero Mori, Norihiro Kikuchi, Masaaki Tanaka, Masashi Miyazaki
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88933
https://doi.org/10.1115/ICONE29-88933
View Paper titled, Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter
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Topics: Design, Failure, Optimization, Probability, Transients (Dynamics)
Proceedings Papers

A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94327
https://doi.org/10.1115/ICONE29-94327
View Paper titled, A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients
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Topics: Fatigue damage, Nuclear power stations, Transients (Dynamics)
Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis
Proceedings Papers

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Xiaoyan Yang, Hongyi Yang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A072, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92214
https://doi.org/10.1115/ICONE29-92214
View Paper titled, Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter
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Topics: Kalman filters, Design, Nuclear reactors, Porosity, Safety, Simulation, Transients (Dynamics)
Proceedings Papers

Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient

Haidong Liu, Deqi Chen, Jiang Qin, Peigang Yan
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A060, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92044
https://doi.org/10.1115/ICONE29-92044
View Paper titled, Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient
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Topics: Boiling, Critical heat flux, Flow (Dynamics), Transients (Dynamics), Vapors
Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Xiao Ke
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90343
https://doi.org/10.1115/ICONE29-90343
View Paper titled, The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident
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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback