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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
Paper No: ICONE29-91544
DOI: 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

Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

Guilian Shi, Huang Xiaojin, Mo Changyu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A007, August 8–12, 2022
Paper No: ICONE29-89387
DOI: https://doi.org/10.1115/ICONE29-89387
View Paper titled, Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology
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Topics: Circuits, Failure, Physics, Electronic equipment, Hardware, Design, Failure mechanisms, Nuclear power, Nuclear power stations, Time series
Proceedings Papers

Load Match-Oriented Coordinated Control for Modular High Temperature Gas-Cooled Reactor Based on Dynamic Matrix Control

Di Jiang, Zhe Dong, Bowen Li, Xiaojin Huang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A013, August 4–6, 2021
Paper No: ICONE28-64572
DOI: https://doi.org/10.1115/ICONE28-64572
View Paper titled, Load Match-Oriented Coordinated Control for Modular High Temperature Gas-Cooled Reactor Based on Dynamic Matrix Control
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Topics: Hardware, Simulation, Stress, Very high temperature reactors
Proceedings Papers

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Arttu Meriläinen, Olli Viljakainen, Karri Honkoila, Ari Lahtela
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T01A004, August 4–6, 2021
Paper No: ICONE28-64294
DOI: https://doi.org/10.1115/ICONE28-64294
View Paper titled, Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model
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Topics: Engineering models, Nuclear power stations, Accidents, Circuits, Accident management, Computer software, Containment, Design, Diesel generators, Electronic systems
Proceedings Papers

An Original Distributed Simulation Method Applied to the Advanced Nuclear Power Plant Control Technology Hardware-in-the-Loop Simulation Verification Platform

Li Bowen, Dong Zhe, Jiang Di
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A044, August 4–6, 2021
Paper No: ICONE28-64464
DOI: https://doi.org/10.1115/ICONE28-64464
View Paper titled, An Original Distributed Simulation Method Applied to the Advanced Nuclear Power Plant Control Technology Hardware-in-the-Loop Simulation Verification Platform
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Topics: Control systems, Hardware, Machinery, Nuclear power stations, Simulation
Proceedings Papers

Challenge to Investigation of Fuel Debris in RPV by an Advanced Super Dragon Articulated Robot Arm: Design and Prototyping of a Lightweight Super Long Reach Articulated Manipulator

Gen Endo, Hideharu Takahashi, Hiroshige Kikura
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, V001T04A013, August 4–5, 2020
Paper No: ICONE2020-16834
DOI: https://doi.org/10.1115/ICONE2020-16834
View Paper titled, Challenge to Investigation of Fuel Debris in RPV by an Advanced Super Dragon Articulated Robot Arm: Design and Prototyping of a Lightweight Super Long Reach Articulated Manipulator
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Topics: Design, Fuels, Manipulators, Robots, Actuators, Gravity (Force), Tendons, Engineering prototypes, Fukushima nuclear disaster, Japan, 2011, Hardware
Proceedings Papers

Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

Meghan Galiardi, Amanda Gonzales, Jamie Thorpe, Eric Vugrin, Raymond Fasano, Christopher Lamb
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A003, August 4–5, 2020
Paper No: ICONE2020-16071
DOI: https://doi.org/10.1115/ICONE2020-16071
View Paper titled, Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants
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Topics: Nuclear power stations, Resilience, Supervisory Control and Data Acquisition systems, Control systems, Architecture, Design, Security, Computer security, Computer software, Hardware
Proceedings Papers

Unmet Challenges to Successfully Mitigating Severe Accidents in Multi Unit CANDU Reactors

Sunil Nijhawan
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, V001T01A011, August 4–5, 2020
Paper No: ICONE2020-16517
DOI: https://doi.org/10.1115/ICONE2020-16517
View Paper titled, Unmet Challenges to Successfully Mitigating Severe Accidents in Multi Unit CANDU Reactors
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Topics: Accidents, Safety, Fukushima nuclear disaster, Japan, 2011, Design, Disasters, Hardware, Public utilities, Risk reduction
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
View Paper titled, Study on the Operating Strategy Optimization of Moving to Remote Shutdown Station When Main Control Room Is Un-Inhabitable
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Topics: Control rooms, Optimization, Nuclear power stations, Pressurized water reactors, Safety, Economics , Fire, Hardware, Heat, Nuclear reactor coolants
Proceedings Papers

Multi-Diversity for FPGA Platform Based NPP I&C Systems: New Possibilities and Assessment Technique

Vyacheslav Kharchenko, Andriy Kovalenko, Kostiantyn Leontiiev, Artem Panarin, Vyacheslav Duzhy
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, V001T04A018, July 22–26, 2018
Paper No: ICONE26-82377
DOI: https://doi.org/10.1115/ICONE26-82377
View Paper titled, Multi-Diversity for FPGA Platform Based NPP I&C Systems: New Possibilities and Assessment Technique
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Topics: Nuclear power stations, Algorithms, Maintenance, Redundancy (Engineering), Risk, Buses, Control systems, Cycles, Failure, Hardware
Proceedings Papers

FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko
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, V001T04A014, July 22–26, 2018
Paper No: ICONE26-82048
DOI: https://doi.org/10.1115/ICONE26-82048
View Paper titled, FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty
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Topics: Nuclear power stations, Safety, Uncertainty, Computer software, Reliability, Failure mechanisms, Testing, Aerospace industry, Errors, Failure data
Proceedings Papers

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk
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, V001T04A016, July 22–26, 2018
Paper No: ICONE26-82270
DOI: https://doi.org/10.1115/ICONE26-82270
View Paper titled, NPP I&C Safety Assessment by Aggregation of Formal Techniques
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Topics: Nuclear power stations, Safety, Computer software, Failure mode and effects analysis, Computers, Control systems, Design, Failure mechanisms, Flow (Dynamics), Hardware
Proceedings Papers

Dynamic Modeling of the NSSS Based on NHR200-II Nuclear Heating Reactor

Zhe Dong, Yifei Pan, Miao Liu, Xiaojin 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, V001T13A026, July 22–26, 2018
Paper No: ICONE26-82579
DOI: https://doi.org/10.1115/ICONE26-82579
View Paper titled, Dynamic Modeling of the NSSS Based on NHR200-II Nuclear Heating Reactor
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Topics: Dynamic modeling, Heating, Control systems, Design, Circuits, Coolants, Hardware, Model validation, Momentum, Physics
Proceedings Papers

The Design of Nuclear Noise Frequency Spectrum Analysis System and Helium Bubble Movement Behavior Computation for Narrow Channel Core

Herong Zeng, Baoxin Yuan
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A007, July 22–26, 2018
Paper No: ICONE26-81170
DOI: https://doi.org/10.1115/ICONE26-81170
View Paper titled, The Design of Nuclear Noise Frequency Spectrum Analysis System and Helium Bubble Movement Behavior Computation for Narrow Channel Core
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Topics: Bubbles, Computation, Design, Emission spectroscopy, Helium, Noise (Sound), Spectroscopy, Data acquisition, Data acquisition systems, Fault diagnosis
Proceedings Papers

The Safety Analysis of Multiple Method Fusion on Reactor Scram Subsystem

Hua Liu, Zhaohui Liu, Xiaohua Yang, Shiyu Yan, Zhi Chen
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A059, July 22–26, 2018
Paper No: ICONE26-82453
DOI: https://doi.org/10.1115/ICONE26-82453
View Paper titled, The Safety Analysis of Multiple Method Fusion on Reactor Scram Subsystem
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Topics: Safety, Scram, Failure mode and effects analysis, Failure, Computer software, Design, Hardware, Accidents, Chain, Complex systems
Proceedings Papers

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Shanfang Huang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, Kan Wang
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A002, July 22–26, 2018
Paper No: ICONE26-81042
DOI: https://doi.org/10.1115/ICONE26-81042
View Paper titled, Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”
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Topics: Computer simulation, Education, Nuclear engineering, Nuclear reactors, Thermal analysis, Nuclear power, China, Computer software, Computers, Experimental design
Proceedings Papers

Research on the Reliability of Digital Instrumentation and Control System of Nuclear Power Plant Based on Dynamic Flowgraph Methodology

Chen Zhuo, Zhao Bo, Yang Jian, Sun Jin-long
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A034, July 2–6, 2017
Paper No: ICONE25-67719
DOI: https://doi.org/10.1115/ICONE25-67719
View Paper titled, Research on the Reliability of Digital Instrumentation and Control System of Nuclear Power Plant Based on Dynamic Flowgraph Methodology
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Topics: Control systems, Instrumentation, Nuclear power stations, Reliability, Design for Manufacturing, Modeling, Computer software, Failure, Hardware, Probability
Proceedings Papers

A Quantitative Approach for Reliability Evaluation of Safety I&C Systems in Nuclear Power Plants

Liu Dongxu, Xu Dongling, Zhang Shuhui, Hu Xiaoying
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, V001T04A013, July 2–6, 2017
Paper No: ICONE25-66483
DOI: https://doi.org/10.1115/ICONE25-66483
View Paper titled, A Quantitative Approach for Reliability Evaluation of Safety I&C Systems in Nuclear Power Plants
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Topics: Nuclear power stations, Reliability, Safety, Probability, Modeling, Algebra, Databases, Hardware, Risk-based design
Proceedings Papers

Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique

Ilona Zelinko, Vyacheslav Kharchenko, Konstantin Leontiev
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A034, July 2–6, 2017
Paper No: ICONE25-67120
DOI: https://doi.org/10.1115/ICONE25-67120
View Paper titled, Cyber Security Assessment of Component Off-the-Shelf Based NPP I&C System Using IMECA Technique
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Topics: Computer security, Nuclear power stations, Safety, Computer software, Countermeasures, Databases, Failure, Joining, Security, Decision making
Proceedings Papers

Design and Optimization of Temperature Acquisition System for Determination of Effective Thermal Conductivity of Pebble Bed

Pengxin Cheng, Cheng Ren, Yongyong Wu, Rui Li
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A008, July 2–6, 2017
Paper No: ICONE25-66148
DOI: https://doi.org/10.1115/ICONE25-66148
View Paper titled, Design and Optimization of Temperature Acquisition System for Determination of Effective Thermal Conductivity of Pebble Bed
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Topics: Design, Optimization, Temperature, Thermal conductivity, Data acquisition systems, Heat transfer, Computer software, Errors, Hardware, Measurement systems