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Proceedings Papers

Prediction of Sensor Data Accuracy in Thermal Experimental Benches Using GRU-GCN Neural Network Model

Linjun Yang, Tong Li, Yongchao Liu, Bo Wang, Jiangkuan Li, Jiming Wen, Sichao Tan, Ruifeng Tian
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A049, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134843
https://doi.org/10.1115/ICONE31-134843
View Paper titled, Prediction of Sensor Data Accuracy in Thermal Experimental Benches Using GRU-GCN Neural Network Model
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Topics: Complex systems, Cycles, Deep learning, Energy efficiency, Neural network models, Nuclear power stations, Safety, Sensors, Time series
Proceedings Papers

Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator

Pietro Cioli Puviani, Ivan Di Piazza, Ranieri Marinari, Roberto Zanino, Mariano Tarantino
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93457
https://doi.org/10.1115/ICONE29-93457
View Paper titled, Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator
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Topics: Complex systems, Computational fluid dynamics, Design, Fuels, Heating, Manufacturing, Porous materials, Safety, Simulation, Steady state
Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91669
https://doi.org/10.1115/ICONE29-91669
View Paper titled, Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90277
https://doi.org/10.1115/ICONE29-90277
View Paper titled, Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example
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Topics: Nuclear engineering, Risk assessment, Risk management, Nuclear power, Risk, Risk control, Carbon, Carbon neutrality, Complex systems, Construction
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82453
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

Application of Monte Carlo Methods in Reactor Protection System Reliability Research

Duo Li, Zhaojun Hao, Shuqiao Zhou, Chao Guo
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, V001T04A006, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81300
https://doi.org/10.1115/ICONE26-81300
View Paper titled, Application of Monte Carlo Methods in Reactor Protection System Reliability Research
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Topics: Monte Carlo methods, Reactor protection systems, Reliability, Event history analysis, Simulation, Nuclear power stations, Chain, Complex systems, Control systems, Instrumentation
Proceedings Papers

The Cloud Model Theory of Intelligent Control Method for Non-Minimum-Phase and Non-Self-Balancing System in Nuclear Power

Mo Tao, Ruotong Qu, Zhiwu Ke, Zhaoxu Chen, Xianling Li, Yi Feng
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, V001T04A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81829
https://doi.org/10.1115/ICONE26-81829
View Paper titled, The Cloud Model Theory of Intelligent Control Method for Non-Minimum-Phase and Non-Self-Balancing System in Nuclear Power
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Topics: Nuclear power, Water, Uncertainty, Control systems, Ambiguity, Boilers, Chaos, Gaussian distribution, Stability, Artificial intelligence
Proceedings Papers

Systems Engineering Approach for Pre-Conceptual Design of DEMO Divertor

Domenico Marzullo, Danilo N. Dongiovanni, Jeong Ha You
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82421
https://doi.org/10.1115/ICONE26-82421
View Paper titled, Systems Engineering Approach for Pre-Conceptual Design of DEMO Divertor
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Topics: Design, Systems engineering, Conceptual design, Power stations, Change management, Modeling, Tokamaks, Complex systems, Cycles, Exhaust systems
Proceedings Papers

RELAP5 STH and Fluent CFD Coupled Calculations of a PLOHS + LOF Transient in the HLM Experimental Facility CIRCE

M. Angelucci, D. Martelli, N. Forgione, M. Tarantino
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A045, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67278
https://doi.org/10.1115/ICONE25-67278
View Paper titled, RELAP5 STH and Fluent CFD Coupled Calculations of a PLOHS + LOF Transient in the HLM Experimental Facility CIRCE
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Topics: Computational fluid dynamics, Transients (Dynamics), Heat, Heat exchangers, Boundary-value problems, Complex systems, Computer software, Flow (Dynamics), Heat sinks, Matlab
Proceedings Papers

Online Fault Diagnosis of Nuclear Power Plants Using Signed Directed Graph and Fuzzy Theory

Guohua Wu, Liguo Zhang, Jiejuan Tong
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66367
https://doi.org/10.1115/ICONE25-66367
View Paper titled, Online Fault Diagnosis of Nuclear Power Plants Using Signed Directed Graph and Fuzzy Theory
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Topics: Fault diagnosis, Nuclear power stations, Modeling, Simulation experiments, Complex systems, Flaw detection, Radioactivity, Safety, Signal processing
Proceedings Papers

A Development of Human-System Interaction in Digital NPPs

Jiachuan Lu, Longtao Liao, Bo Feng, Yifen Chen, Junwei Hao, Kai Ye, Jianxiang Zheng
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, V001T04A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67212
https://doi.org/10.1115/ICONE25-67212
View Paper titled, A Development of Human-System Interaction in Digital NPPs
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Topics: Nuclear power stations, Design, Control systems, Instrumentation, China, Complex systems, Computer software, Computers, Data acquisition, Nuclear power
Proceedings Papers

The Reliability Model for the FPGA-Based Instrument and Control System Using Colored Petri Net

Zhanguo Ma, Hidekazu Yoshikawa, Ming Yang
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, V001T04A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66440
https://doi.org/10.1115/ICONE25-66440
View Paper titled, The Reliability Model for the FPGA-Based Instrument and Control System Using Colored Petri Net
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Topics: Control systems, Instrumentation, Reliability, Failure, Hardware, Complex systems, Computer software, Delays, Design, Fault tolerance
Proceedings Papers

Research on Rolling-Sliding Integrated Auxiliary Bearing and its Application in High Temperature Reactor

Chen Jianqiang, Sun Zhe, Yang Guojun, Liu Xingnan, Shi Zhengang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A103, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67544
https://doi.org/10.1115/ICONE25-67544
View Paper titled, Research on Rolling-Sliding Integrated Auxiliary Bearing and its Application in High Temperature Reactor
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Topics: Bearings, High temperature, Stress, Friction, Rolling bearings, Rotors, Helium, Magnetic bearings, Plain bearings, Heat
Proceedings Papers

Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies

George L. Mesina, Nolan Anderson
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A084, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61040
https://doi.org/10.1115/ICONE24-61040
View Paper titled, Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies
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Topics: Complex systems, Computer software, Computers, Nuclear power stations, Physics, Quality control
Proceedings Papers

Exergy Analysis for Small Modular Reactor Hybrid Energy System

Lauren Boldon, Piyush Sabharwall, Li (Emily) Liu
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T01A002, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49083
https://doi.org/10.1115/NUCLRF2015-49083
View Paper titled, Exergy Analysis for Small Modular Reactor Hybrid Energy System
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Topics: Exergy analysis, Small modular reactors, Thermoeconomics, Energy / power systems, Exergy, System efficiency, Carbon, Complex systems, Economics , Heat
Proceedings Papers

Implementation of an Approach for Characterisation of Radiological Inventory for Decommissioning at Chinon A2 NPP

A. Traichel, F. Tardy, M. Mummert
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A041, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30977
https://doi.org/10.1115/ICONE22-30977
View Paper titled, Implementation of an Approach for Characterisation of Radiological Inventory for Decommissioning at Chinon A2 NPP
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Topics: Nuclear decommissioning, Nuclear power stations, Circuits, Carbon dioxide, Complex systems, Contamination, Errors, Graphite, Measurement systems, Radiological characterization
Proceedings Papers

Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop

Daniele Cerroni, Antonio Cervone, Paride Meloni, Massimiliano Polidori, Sandro Manservisi
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A046, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31052
https://doi.org/10.1115/ICONE22-31052
View Paper titled, Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop
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Topics: Fast neutron reactors, Accidents, Circuits, Complex systems, Finite element methods, Finite element model, Heat, Simulation
Proceedings Papers

Investigation on Coupling Behaviors of Thermal-Hydraulics/Neutronics Under Asymmetrical Inlet Conditions

Yong Zheng, Min-jun Peng, Geng-lei Xia, Ren Li
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A067, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30522
https://doi.org/10.1115/ICONE22-30522
View Paper titled, Investigation on Coupling Behaviors of Thermal-Hydraulics/Neutronics Under Asymmetrical Inlet Conditions
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Topics: Thermal hydraulics, Transients (Dynamics), Nuclear power stations, Steady state, Accidents, Neutrons, Safety, Simulation, Temperature, Complex systems
Proceedings Papers

Automated, Highly Accurate Verification of RELAP5-3D

George L. Mesina, David L. Aumiller, Francis X. Buschman
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A054, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31153
https://doi.org/10.1115/ICONE22-31153
View Paper titled, Automated, Highly Accurate Verification of RELAP5-3D
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Topics: Algorithms, Complex systems, Computer software, Design, Light water reactors, Mathematical analysis, Physics, Quality control, Safety
Proceedings Papers

Uncertainties in Predictions by System Thermal-Hydraulic Codes: The CASUALIDAD Method

A. Petruzzi, F. D’Auria
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A066, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31274
https://doi.org/10.1115/ICONE22-31274
View Paper titled, Uncertainties in Predictions by System Thermal-Hydraulic Codes: The CASUALIDAD Method
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Topics: Uncertainty, Complex systems, Computers, Density, Probability, Uncertainty analysis