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Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89360
https://doi.org/10.1115/ICONE29-89360
View Paper titled, Study on Evaluation Method of Radial Power Reference Distribution of PWR
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Topics: Evaluation methods, Manufacturing, Pressurized water reactors, Safety, Accidents, Computer programming, Design, Engineers, Steam
Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst
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, V001T06A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16426
https://doi.org/10.1115/ICONE2020-16426
View Paper titled, Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings
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Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16745
https://doi.org/10.1115/ICONE2020-16745
View Paper titled, Development of Design Support System for Piping Route and Differential Pressure Flowmeter by Three-Dimensional Fluid Analysis
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Topics: Design, Flowmeters, Fluids, Pipes, Pressure, Flow (Dynamics), Flow measurement, Computer-aided design, Visualization, Engineers
Proceedings Papers

Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building

Byunghyun Choi, Akemi Nishida, Yinsheng Li, Ken Muramatsu, Tsuyoshi Takada
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82034
https://doi.org/10.1115/ICONE26-82034
View Paper titled, Epistemic Uncertainty Quantification of Floor Responses for a Nuclear Reactor Building
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Topics: Nuclear reactors, Uncertainty quantification, Uncertainty, Modeling, Accidents, Countermeasures, Design, Engineers, Finite element model, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Design and Development of DeRisk: A Fault Tree Analysis Program Package

Zhenxu Zhou, Hao Nie, Qin Zhang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81291
https://doi.org/10.1115/ICONE26-81291
View Paper titled, Design and Development of DeRisk: A Fault Tree Analysis Program Package
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Topics: Design, Fourier transform spectroscopy, Graphical user interfaces, Reliability, Algorithms, Computer software, Cycles, Dynamics (Mechanics), Engineers, Military systems
Proceedings Papers

Design Optimization of Modernization of I&C System Using Digital Technology in NPPs

Longqiang Zhang, Jiahong Yan, Weining Zhao, Weijun Huang
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, V001T04A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82498
https://doi.org/10.1115/ICONE26-82498
View Paper titled, Design Optimization of Modernization of I&C System Using Digital Technology in NPPs
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Topics: Design, Nuclear power stations, Optimization, Control systems, Construction, Assembly lines, Economics , Engineers, Instrumentation, Nuclear power
Proceedings Papers

AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants

Bernard Gautier, Mickael Cesbron, Richard Tulinski
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81893
https://doi.org/10.1115/ICONE26-81893
View Paper titled, AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants
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Topics: Design, Fire, Nuclear power stations, Water, Pressurized water reactors, Hazards, Regulations, Safety, China, Construction
Proceedings Papers

Study on Supervision Mode of Floating Nuclear Power Plant With Small Modular Reactor

Lei Wan, Guiyong Li, Min Rui, Yongkang Liu, Jue Yang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82138
https://doi.org/10.1115/ICONE26-82138
View Paper titled, Study on Supervision Mode of Floating Nuclear Power Plant With Small Modular Reactor
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Topics: Nuclear power stations, Small modular reactors, Ships, Safety, Construction, Governments, China, Engineering drawings, FPSO, Licensing
Proceedings Papers

Multi-Fluid Gas Turbine Components Scaling for a Generation IV Nuclear Power Plant Performance Simulation

Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A080, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82373
https://doi.org/10.1115/ICONE26-82373
View Paper titled, Multi-Fluid Gas Turbine Components Scaling for a Generation IV Nuclear Power Plant Performance Simulation
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Topics: Fluids, Gas turbines, Nuclear power stations, Simulation, Closed-cycle gas turbines, Design, Computer simulation, Engineers, Engines
Proceedings Papers

The Application of Task Analysis and Task Support Verification in HPR1000 Main Control Room Human System Interface Design

Deng Shiguang, Ming Xiaoyang, Gao Yuan
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A052, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67891
https://doi.org/10.1115/ICONE25-67891
View Paper titled, The Application of Task Analysis and Task Support Verification in HPR1000 Main Control Room Human System Interface Design
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Topics: Control rooms, Design, Task analysis, Accidents, Human factors, Nuclear power stations, Integrated systems, Safety, Brain, Engineers
Proceedings Papers

The Movement Process Simulation of CRDM

Guangji Wang, Gang Liu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A029, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66857
https://doi.org/10.1115/ICONE25-66857
View Paper titled, The Movement Process Simulation of CRDM
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Topics: Computational fluid dynamics, Control algorithms, Control systems, Displacement, Drag (Fluid dynamics), Electric current, Electromagnetic force, Engineers, Errors, Geomagnetic poles
Proceedings Papers

CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB

Hong Xu, Yiban Xu, Liping Cao, Yixing Sung, Vefa N. Kucukboyaci, Richard F. Wright
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A048, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67345
https://doi.org/10.1115/ICONE25-67345
View Paper titled, CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB
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Topics: Computational fluid dynamics, Pressurized water reactors, Flow (Dynamics), Simulation, Nuclear reactor coolants, Reactor vessels, Coolants, Design, Fuels, Modeling
Proceedings Papers

The Need for Integrated Cybersecurity and Safety Training

Deeksha Gupta, Edita Bajramovic, Holger Hoppe, Antonio Ciriello
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T12A009, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67330
https://doi.org/10.1115/ICONE25-67330
View Paper titled, The Need for Integrated Cybersecurity and Safety Training
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Topics: Computer security, Safety, Security, Nuclear power stations, Design, Engineering disciplines, Public utilities, Construction, Defense industry, Engineering education
Proceedings Papers

Research on Simulation Technology for Supervisory Control Software in NPP DCS

Hanjun Gao, Ming Qu, CaiKe Zhang, Kui Xu, PeiBang Liu, Chenglong Xie
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A004, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66064
https://doi.org/10.1115/ICONE25-66064
View Paper titled, Research on Simulation Technology for Supervisory Control Software in NPP DCS
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Topics: Computer software, Nuclear power stations, Simulation, Reliability, Engineers, Innovation, Licensing, Process control
Proceedings Papers

Design Investigation on Flow Diffuser With Code_Saturne : CFD Simulation Analysis

Tingting Xu, Jiesheng Min, Serge Bellet, Richard Howard, Dominique Alvarez, Guofei Chen
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A053, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67767
https://doi.org/10.1115/ICONE25-67767
View Paper titled, Design Investigation on Flow Diffuser With Code_Saturne : CFD Simulation Analysis
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Topics: Computational fluid dynamics, Design, Diffusers, Flow (Dynamics), Simulation analysis, Simulation, Engineering simulation, Algorithms, Computers, Coolants
Proceedings Papers

Comparison and Reference Between RSE-M and ASME Section XI Regulations on In-Service Inspection for China Nuclear Power Plant

Sun Haitao, Zhang Qinghua, Jia Panpan, Ling Ligong, Wang Chen, Lv Yunhe
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A021, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66195
https://doi.org/10.1115/ICONE25-66195
View Paper titled, Comparison and Reference Between RSE-M and ASME Section XI Regulations on In-Service Inspection for China Nuclear Power Plant
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Topics: China, In-service inspection, Nuclear power stations, Regulations, Design, Inspection, Acceptance criteria, Engineers, Feedback, Maintenance
Proceedings Papers

SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe

Jozef Molnar, Marek Pecka, Jaroslav Kment
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A034, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66867
https://doi.org/10.1115/ICONE25-66867
View Paper titled, SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe
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Topics: Surveillance, Fuels, Construction, Monitoring systems, Nuclear power stations, Computation, Computers, Design, Education, Engineers
Proceedings Papers

Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies

Sunil Nijhawan
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60689
https://doi.org/10.1115/ICONE24-60689
View Paper titled, Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies
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Topics: Accidents, Design, Boilers, Pressure, Containment, Heat, Safety, Accident management, Analytical methods, Leakage
Proceedings Papers

Vortexing and Air Withdrawal Evaluations for Storage Tanks Using Physical Hydraulic Model Studies

Amie Humphrey Facendola, Ludwig Haber, Andrew Johansson
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60768
https://doi.org/10.1115/ICONE24-60768
View Paper titled, Vortexing and Air Withdrawal Evaluations for Storage Tanks Using Physical Hydraulic Model Studies
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Topics: Storage tanks, Flow (Dynamics), Pumps, Water, Density, Design, Emergencies, Engineers, Fluids, Nozzles