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Proceedings Papers

Research on Operation Life Extension Time Limited Aging Analysis Key Method for Electrical Penetration Assembly of Nuclear Power Plants

Binfeng Wang, Zhilin Chen, Ping Huang, Zhenhao Shi, Yanwei Zhang, Tao Liu

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A025, August 8–12, 2022

Paper No: ICONE29-91884

DOI: https://doi.org/10.1115/ICONE29-91884

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Topics: Licensing, Life extension, Manufacturing, Nuclear power stations

Proceedings Papers

Review of Operating License Extension of Nuclear Power Plants

Zhilin Chen, Xiaowei Li, Ping Huang, Chunhui Wang, Jun Wang, Zhiyuan Chi, Kuiyuan Fang, Yinghui An, Yanwei Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A082, August 8–12, 2022

Paper No: ICONE29-93427

DOI: https://doi.org/10.1115/ICONE29-93427

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Topics: Licensing, Nuclear power stations

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

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

Dongyuan Li, Shi Qing, Haiying Luo, Jinkai Wang, Jiaoshen Xu

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A009, August 8–12, 2022

Paper No: ICONE29-92241

DOI: https://doi.org/10.1115/ICONE29-92241

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Topics: Design, Nuclear design, Risk, Licensing, Safety, Economics , Nuclear power stations, Plant design, Regulations, Self-evaluation

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

Paper No: ICONE29-90343

DOI: https://doi.org/10.1115/ICONE29-90343

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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback

Proceedings Papers

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

Baoquan Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A010, August 8–12, 2022

Paper No: ICONE29-90277

DOI: https://doi.org/10.1115/ICONE29-90277

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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction

Proceedings Papers

Case Study on Significance Determination Process for NPPs Abnormal Events at Power

Shijun Chen, Xiang Zou, Lihui Chen, Wenbo Luo

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A057, August 8–12, 2022

Paper No: ICONE29-93590

DOI: https://doi.org/10.1115/ICONE29-93590

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Topics: Licensing, Nuclear power stations, China

Proceedings Papers

Applicability Assessment of Accident Analysis Codes and Determination of Testing Facility for Validation of the CAP1400

Xiaoyu Cai, Guobao Shi, Jinquan Yan, Pu Fan, Dongjian Zhao

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A040, August 4–6, 2021

Paper No: ICONE28-66257

DOI: https://doi.org/10.1115/ICONE28-66257

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Topics: Accidents, Design, Licensing, Safety, Test facilities

Proceedings Papers

Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

Hongbin Zhang, Cole Blakely, Jianguo Yu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A005, August 4–5, 2020

Paper No: ICONE2020-16098

DOI: https://doi.org/10.1115/ICONE2020-16098

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Topics: Fuel rods, Physics, Probability, Accidents, Cycles, Light water reactors, Coolants, Design, Fuels, Pressurized water reactors

Proceedings Papers

Development of Design Support System for Piping Route and Differential Pressure Flowmeter by Three-Dimensional Fluid Analysis

Takatsugu Miura, Kingo Igarashi, Tomoyuki Hosaka, Takumi Kitagawa, Tatsurou Yashiki, Yuki Itabayashi, Hirotsugu Suzuki, Takashi Nakahara, Junichi Kitamura, Tadashi Sano

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, V001T06A022, August 4–5, 2020

Paper No: ICONE2020-16745

DOI: https://doi.org/10.1115/ICONE2020-16745

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Topics: Design, Flowmeters, Fluids, Pipes, Pressure, Flow (Dynamics), Flow measurement, Computer-aided design, Visualization, Engineers

Proceedings Papers

Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update

Sarah Morgan, Sama Bilbao y Leon, Matthew Bucknor, Mark Anderson, Emilio Baglietto, James Schneider, Matthew Weathered, Liangyu Xu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A078, July 22–26, 2018

Paper No: ICONE26-82364

DOI: https://doi.org/10.1115/ICONE26-82364

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Topics: Modeling, Sodium fast reactors, Thermal stratification, Computational fluid dynamics, Accidents, Design, Licensing, Power stations, Uncertainty

Proceedings Papers

RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility

Mohammad A. Hawila, Karen Vierow Kirkland

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A008, July 22–26, 2018

Paper No: ICONE26-81119

DOI: https://doi.org/10.1115/ICONE26-81119

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Topics: Computational fluid dynamics, Pumps, Testing, Turbochargers, Test facilities, Design, Engineering simulation, Nuclear power stations, Simulation, Turbines

Proceedings Papers

Assessment of Control Room Radiological Habitability of High-Temperature Reactor Pebble-Bed Module in Shidao Bay Multi-Reactor Nuclear Power Site

Xinpeng Li, Sheng Fang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A042, July 22–26, 2018

Paper No: ICONE26-82448

DOI: https://doi.org/10.1115/ICONE26-82448

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Topics: Control rooms, High temperature, Nuclear power, Design, Accidents, China, Computational methods, Coolants, Licensing, Meteorology

Proceedings Papers

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

Zhen-Yu Hung, Pei-Hsun Huang, Chao-Jen Li

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A004, July 22–26, 2018

Paper No: ICONE26-81074

DOI: https://doi.org/10.1115/ICONE26-81074

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Topics: Safety, Transportation systems, Computer software, Containment, Corrective actions, Design, Emergency core cooling systems, Experimental analysis, Licensing, Nuclear power plant operations

Proceedings Papers

Proposed License Structure of Small Modular Reactor in China

Zheng Hua, Wei Shuhong

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, V001T13A016, July 22–26, 2018

Paper No: ICONE26-81985

DOI: https://doi.org/10.1115/ICONE26-81985

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Topics: China, Licensing, Small modular reactors, Design, Construction, Light water reactors, Nuclear power stations, Safety

Proceedings Papers

The Canadian Nuclear Safety Commission: Readiness Activities to Regulate Small Modular Reactors

Kevin Lee

Paper No: ICONE26-82620

DOI: https://doi.org/10.1115/ICONE26-82620

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Topics: Safety, Small modular reactors, Licensing, Nuclear power stations, Design, Feedback

Proceedings Papers

European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

Peter Chappell, Guillaume Jacquart, Giovanni Ferraro, Olli Kymäläinen

Paper No: ICONE26-82343

DOI: https://doi.org/10.1115/ICONE26-82343

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Topics: Light water reactors, Nuclear power stations, Design, Safety, Performance, Public utilities, Construction, Engineering standards, Feedback, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

What Is a “Known and Established” Standard?

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A009, July 22–26, 2018

Paper No: ICONE26-81901

DOI: https://doi.org/10.1115/ICONE26-81901

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Topics: Licensing, Regulations

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

The Role of the NRC in License Renewals

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A011, July 22–26, 2018

Paper No: ICONE26-81904

DOI: https://doi.org/10.1115/ICONE26-81904

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Topics: Licensing, Damage, Design, Fuels, Safety, Acceptance criteria, Health and safety, Regulations

2 3 4 5

NARROW

Research on Operation Life Extension Time Limited Aging Analysis Key Method for Electrical Penetration Assembly of Nuclear Power Plants

Review of Operating License Extension of Nuclear Power Plants

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

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

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

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

Case Study on Significance Determination Process for NPPs Abnormal Events at Power

Applicability Assessment of Accident Analysis Codes and Determination of Testing Facility for Validation of the CAP1400

Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

Development of Design Support System for Piping Route and Differential Pressure Flowmeter by Three-Dimensional Fluid Analysis

Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update

RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility

Assessment of Control Room Radiological Habitability of High-Temperature Reactor Pebble-Bed Module in Shidao Bay Multi-Reactor Nuclear Power Site

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

Proposed License Structure of Small Modular Reactor in China

The Canadian Nuclear Safety Commission: Readiness Activities to Regulate Small Modular Reactors

European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

What Is a “Known and Established” Standard?

“Begging the Question” in Licensing Basis Accident Analyses

The Role of the NRC in License Renewals

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