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Proceedings Papers

The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant

Zilong Wang, Deyi Liu, Ming Zhao, Li Wang, Jie Xu

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, V003T13A004, August 4–6, 2021

Paper No: ICONE28-64423

DOI: https://doi.org/10.1115/ICONE28-64423

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Topics: Design, Heat shielding, Nuclear power stations, Nuclear reactor coolants, Pumps, Safety

Proceedings Papers

Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS

Yuan Yanli, Ye Xianhui, Li Lijuan, Yuan Feng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A002, August 4–5, 2020

Paper No: ICONE2020-16485

DOI: https://doi.org/10.1115/ICONE2020-16485

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Topics: Nuclear reactor coolants, Sensitivity analysis

Proceedings Papers

Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network

Pengpeng Sun, Yong Liu, Guohua Wu, Zhiyong Duan

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, V001T06A005, August 4–5, 2020

Paper No: ICONE2020-16138

DOI: https://doi.org/10.1115/ICONE2020-16138

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Topics: Accidents, Artificial neural networks, Fault diagnosis, Fuzzy logic, Fuzzy neural nets, Nuclear power stations, Nuclear reactor coolants, Safety

Proceedings Papers

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Antony M. Hurst, Pavitra Bansal

Paper No: ICONE2020-16474

DOI: https://doi.org/10.1115/ICONE2020-16474

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Topics: Finite element methods, Pipes, Underpinning, Hinges, Design, Finite element analysis, Light water reactors, Nuclear power stations, Nuclear reactor coolants, Stress

Proceedings Papers

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Cai Zhiyun, Ren Yun, Lai Jianyong, Zhang Yulong, Liu Hang, Liu Xianghong, Liu Minghao, Ye Zhu

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A007, August 4–5, 2020

Paper No: ICONE2020-16341

DOI: https://doi.org/10.1115/ICONE2020-16341

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Topics: Equilibrium (Physics), Simulation analysis, Transients (Dynamics), Flow (Dynamics), Nuclear reactor coolants, Pressure, Safety, Valves, Water, Boundary-value problems

Proceedings Papers

Study on the Shaking Dynamic Response of Steam Generator LOCA

Qian Huang, Xiaofei Yu, Huanhuan Qi, Naibin Jiang, Fengchun Cai, Zhipeng Feng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A009, July 22–26, 2018

Paper No: ICONE26-81278

DOI: https://doi.org/10.1115/ICONE26-81278

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Topics: Boilers, Dynamic response, Dynamic response analysis, Nuclear power stations, Nuclear reactor coolants, Stress, Accidents, China, Computational methods, Coolants

Proceedings Papers

Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator

Feng-chun Cai, Xian-hui Ye, Qian Huang, Wenzheng Zhang

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A010, July 22–26, 2018

Paper No: ICONE26-81279

DOI: https://doi.org/10.1115/ICONE26-81279

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Topics: Boilers, Failure, Probability, Stress, Nonlinear systems, Nuclear reactor coolants, Plasticity, Safety, Seismic analysis, Stress analysis (Engineering)

Proceedings Papers

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A011, July 22–26, 2018

Paper No: ICONE26-82074

DOI: https://doi.org/10.1115/ICONE26-82074

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Topics: Accidents, Sensitivity analysis, Nuclear fission, Pressure, Boilers, Feedwater, Flow (Dynamics), Valves, Accident management, Nuclear reactor coolants

Proceedings Papers

Design Optimization of PERCS in RELAP5 Using Parallel Processing and a Multi-Objective Non-Dominated Sorting Genetic Algorithm

Paul R. Wilding, Nathan R. Murray, Matthew J. Memmott

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A016, July 22–26, 2018

Paper No: ICONE26-82389

DOI: https://doi.org/10.1115/ICONE26-82389

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Topics: Design, Genetic algorithms, Optimization, Parallel processing, Shells, Light water reactors, Pareto optimization, Temperature, Coolants, Cooling systems

Proceedings Papers

Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2

Jeffrey R. Kobelak, Jun Liao, Katsuhiro Ohkawa

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A020, July 22–26, 2018

Paper No: ICONE26-82610

DOI: https://doi.org/10.1115/ICONE26-82610

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Topics: Simulation, Water, Superheating, Reactor vessels, Accidents, Pressurized water reactors, Test facilities, Transients (Dynamics), Boiling, Coolants

Proceedings Papers

Study on the Operating Strategy Optimization of Moving to Remote Shutdown Station When Main Control Room Is Un-Inhabitable

Li Li, Zhang Shengtao, Xu Zhao, Du Yu

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A006, July 22–26, 2018

Paper No: ICONE26-81480

DOI: https://doi.org/10.1115/ICONE26-81480

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Topics: Control rooms, Optimization, Nuclear power stations, Pressurized water reactors, Safety, Economics , Fire, Hardware, Heat, Nuclear reactor coolants

Proceedings Papers

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

Liu Qiaofen, Xiao Sanping, Liu Yu, Liu Xichao, Jiang Xulun

Paper No: ICONE26-81714

DOI: https://doi.org/10.1115/ICONE26-81714

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Topics: Algorithms, Nuclear power stations, Pressurized water reactors, Leakage flows, Computational methods, Leakage, Leak-before-break, Nuclear reactor coolants, Nuclear reactor safety

Proceedings Papers

“Begging the Question” in Licensing Basis Accident Analyses

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A010, July 22–26, 2018

Paper No: ICONE26-81902

DOI: https://doi.org/10.1115/ICONE26-81902

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Topics: Accidents, Licensing, Safety, Damage, Design, Fuels, Nuclear reactor coolants, Pressure, Valves

Proceedings Papers

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

Braedon Carr, Bengt Lydell, Jovica R. Riznic

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A001, July 22–26, 2018

Paper No: ICONE26-81001

DOI: https://doi.org/10.1115/ICONE26-81001

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Topics: Failure, Pipes, Water, Chemistry, Transients (Dynamics), Accidents, Boiling water reactors, Control systems, Corrosion, Corrosion resistance

Proceedings Papers

Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs

Mohammed Mahdi, Roman Popov, Igor Pioro

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A039, July 22–26, 2018

Paper No: ICONE26-81618

DOI: https://doi.org/10.1115/ICONE26-81618

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Topics: Thermal efficiency, Thermodynamic power cycles, Very high temperature reactors, Nuclear power stations, Helium, Cycles, Water, Combined cycles, Nitrogen, Gas turbines

Proceedings Papers

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

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

Paper No: ICONE26-82091

DOI: https://doi.org/10.1115/ICONE26-82091

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Topics: Flow (Dynamics), Optimization, Stability, Test facilities, Design, Electricity (Physics), Evaluation methods, Measurement systems, Nuclear power, Nuclear power stations

Proceedings Papers

Qualification Test of APR1400’s RCP Seal Under Extended SBO Condition

Seok Cho, Seok Kim, Byoung-Uhn Bae, Yun-Je Cho, Yeon-Sik Kim, Woo-Jin Jeon, Young-Jung Youn, Sung-Min Chu, Sang-Youn Bang

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A017, July 22–26, 2018

Paper No: ICONE26-82006

DOI: https://doi.org/10.1115/ICONE26-82006

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Topics: Construction, Engines, Fukushima nuclear disaster, Japan, 2011, High pressure (Physics), High temperature, Impellers, Leakage, Leakage flows, Low temperature, Manufacturing

Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018

Paper No: ICONE26-82267

DOI: https://doi.org/10.1115/ICONE26-82267

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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels

Proceedings Papers

Evaluation of IET Facility Applicability on Simulating SBLOCA in Large-Scale Passive PWR Plant

Haozheng Kong, Bo Kuang, Pengfei Liu, Xia Lu, Yi Yao, Lifang Liu, Bo Dong

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A070, July 22–26, 2018

Paper No: ICONE26-82630

DOI: https://doi.org/10.1115/ICONE26-82630

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Topics: Pressurized water reactors, Flow (Dynamics), Nuclear power stations, Accidents, Coolants, Nuclear reactor coolants, Power stations, Pressure, Steam, Valves

Proceedings Papers

Bleed and Feed Analysis for Loss of Secondary Heat Sink to Support the Development of EOPs

Changjiang Yang, Shuliang Huang, Jingxiang Zhan

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A013, July 22–26, 2018

Paper No: ICONE26-81933

DOI: https://doi.org/10.1115/ICONE26-81933

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Topics: Waste heat, Safety, Valves, Accidents, Cladding systems (Building), Fuels, Pressure, Temperature, Design, Emergencies

2 3 4 5

NARROW

The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant

Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS

Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Study on the Shaking Dynamic Response of Steam Generator LOCA

Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

Design Optimization of PERCS in RELAP5 Using Parallel Processing and a Multi-Objective Non-Dominated Sorting Genetic Algorithm

Simulation of JAERI Downcomer Effective Water Head Experiments With W COBRA/TRAC-TF2

Study on the Operating Strategy Optimization of Moving to Remote Shutdown Station When Main Control Room Is Un-Inhabitable

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

“Begging the Question” in Licensing Basis Accident Analyses

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs

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

Qualification Test of APR1400’s RCP Seal Under Extended SBO Condition

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Evaluation of IET Facility Applicability on Simulating SBLOCA in Large-Scale Passive PWR Plant

Bleed and Feed Analysis for Loss of Secondary Heat Sink to Support the Development of EOPs

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