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Proceedings Papers

Design, Simulation and SFF Techniques for Functional Components

Noshir Langrana, Dan Qiu, Guohua Wu, Kathryn Higgins, Cheng Tiao Hsieh
Proc. ASME. IDETC-CIE2000, Volume 7B: 26th Biennial Mechanisms and Robotics Conference, 1381-1386, September 10–13, 2000
Paper No: DETC2000/MECH-14205
https://doi.org/10.1115/DETC2000/MECH-14205
View Paper titled, Design, Simulation and SFF Techniques for Functional Components
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Topics: Design, Rapid prototyping, Simulation, Stereolithography
Proceedings Papers

A Fault Diagnosis Method Based on Signed Directed Graph and Correlation Analysis for Nuclear Power Plants

Chongchong Liu, Guohua Wu, Congsong Yang, Yunwen Li, Qian Wu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A009, August 4–5, 2020
Paper No: ICONE2020-16120
https://doi.org/10.1115/ICONE2020-16120
View Paper titled, A Fault Diagnosis Method Based on Signed Directed Graph and Correlation Analysis for Nuclear Power Plants
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Topics: Expert systems, Fault diagnosis, Nuclear power stations
Proceedings Papers

Discussion of Water Quality Factors Affecting 137 C s Adsorption and the Relationship Between 137 C s - K d and Flow Rate in Freshwater

Jiaxin Wang, Liuguo Zhang, Jingyuan Qu, Guohua Wu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A029, August 4–5, 2020
Paper No: ICONE2020-16248
https://doi.org/10.1115/ICONE2020-16248
View Paper titled, Discussion of Water Quality Factors Affecting 137 C s Adsorption and the Relationship Between 137 C s - K d and Flow Rate in Freshwater
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Topics: Flow (Dynamics), Nuclear power stations, Particulate matter, Water pollution
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
https://doi.org/10.1115/ICONE2020-16138
View Paper titled, Research on Fault Diagnosis of Reactor Coolant Accident in Nuclear Power Plant Based on Radial Basis Function and Fuzzy Neural Network
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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

Diffusion Law and Simulation Analysis of Radon in Uranium Tailings Based on Multiple Gauss Plume Model

Jiaxin Wang, Guohua Wu, Liguo Zhang, Jingyuan Qu, Jiejuan Tong
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A008, July 22–26, 2018
Paper No: ICONE26-81189
https://doi.org/10.1115/ICONE26-81189
View Paper titled, Diffusion Law and Simulation Analysis of Radon in Uranium Tailings Based on Multiple Gauss Plume Model
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Topics: Diffusion (Physics), Plumes (Fluid dynamics), Simulation analysis, Uranium, Wind velocity, Hazards, Pollution, Radiation (Physics), Stability
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
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