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Auto-tuned PID controller using a model predictive control method for the steam generator water level

IEEE transactions on nuclear science, 2001-10, Vol.48 (5), p.1664-1671

Na, Man Gyun

2001

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Prediction of small-scale leak flow rate in LOCA situations using bidirectional GRU

Nuclear Engineering and Technology, 2024, 56(9), , pp.3594-3601

2024

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Development of an AI-based remaining trip time prediction system for nuclear power plants

Nuclear Engineering and Technology, 2024, 56(8), , pp.3167-3179

2024

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A reliable intelligent diagnostic assistant for nuclear power plants using explainable artificial intelligence of GRU-AE, LightGBM and SHAP

Nuclear engineering and technology, 2022-04, Vol.54 (4), p.1271-1287

2022

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Identification of LOCA and Estimation of Its Break Size by Multiconnected Support Vector Machines

IEEE transactions on nuclear science, 2017-10, Vol.64 (10), p.2610-2617

2017

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Power Reconstruction of Fuel Rods by Support Vector Regression for CANDU Reactors

IEEE transactions on nuclear science, 2007-08, Vol.54 (4), p.1302-1310

Yang, Heon Young

2007

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Leak flow prediction during loss of coolant accidents using deep fuzzy neural networks

Nuclear Engineering and Technology, 2021, 53(8), , pp.2547-2555

2021

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Nuclear reactor vessel water level prediction during severe accidents using deep neural networks

Nuclear Engineering and Technology, 2019, 51(3), , pp.723-730

2019

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Estimation of Minimum DNBR Using Cascaded Fuzzy Neural Networks

IEEE transactions on nuclear science, 2015-08, Vol.62 (4), p.1849-1856

2015

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Prediction of hydrogen concentration in nuclear power plant containment under severe accidents using cascaded fuzzy neural networks

Nuclear engineering and design, 2016-04, Vol.300, p.393-402

2016

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Smart support system for diagnosing severe accidents in nuclear power plants

Nuclear Engineering and Technology, 2018, 50(4), , pp.562-569

2018

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Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks

Nuclear Engineering and Technology, 2017, 49(3), , pp.495-503

2017

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Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression

Nuclear Engineering and Technology, 2017, 49(4), , pp.817-824

2017

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Prediction of golden time using SVR for recovering SIS under severe accidents

Annals of nuclear energy, 2016-08, Vol.94, p.102-108

2016

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Prediction of golden time for recovering SISs using deep fuzzy neural networks with rule-dropout

Nuclear Engineering and Technology, 2021, 53(12), , pp.4014-4021

2021

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Prediction of major transient scenarios for severe accidents of nuclear power plants

IEEE transactions on nuclear science, 2004-04, Vol.51 (2), p.313-321

2004

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Detection and Diagnostics of Loss of Coolant Accidents Using Support Vector Machines

IEEE transactions on nuclear science, 2008-02, Vol.55 (1), p.628-636

2008

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Prediction of Leak Flow Rate Using Fuzzy Neural Networks in Severe Post-LOCA Circumstances

IEEE transactions on nuclear science, 2014-12, Vol.61 (6), p.3644-3652

2014

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Prediction of Axial DNBR Distribution in a Hot Fuel Rod Using Support Vector Regression Models

IEEE transactions on nuclear science, 2011-08, Vol.58 (4), p.2084-2090

2011

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Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks

Nuclear Engineering and Technology, 2016, 48(3), , pp.702-710

2016

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Design of a fuzzy model predictive power controller for pressurized water reactors

IEEE transactions on nuclear science, 2006-06, Vol.53 (3), p.1504-1514

2006

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Prediction of DNBR Using Fuzzy Support Vector Regression and Uncertainty Analysis

IEEE transactions on nuclear science, 2010-06, Vol.57 (3), p.1595-1601

2010

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Design of an adaptive predictive controller for steam generators

IEEE transactions on nuclear science, 2003-02, Vol.50 (1), p.186-193

2003

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A smart software sensor for feedwater flow measurement monitoring

IEEE transactions on nuclear science, 2005-12, Vol.52 (6), p.3026-3034

2005

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Effect of local wall thinning on the collapse behavior of pipe elbows subjected to a combined internal pressure and in-plane bending load

Nuclear engineering and design, 2008-06, Vol.238 (6), p.1275-1285

2008

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Auto-tuned PID controller using a model predictive control method for the steam generator water level

Prediction of small-scale leak flow rate in LOCA situations using bidirectional GRU

Development of an AI-based remaining trip time prediction system for nuclear power plants

A reliable intelligent diagnostic assistant for nuclear power plants using explainable artificial intelligence of GRU-AE, LightGBM and SHAP

Identification of LOCA and Estimation of Its Break Size by Multiconnected Support Vector Machines

Power Reconstruction of Fuel Rods by Support Vector Regression for CANDU Reactors

Leak flow prediction during loss of coolant accidents using deep fuzzy neural networks

Nuclear reactor vessel water level prediction during severe accidents using deep neural networks

Estimation of Minimum DNBR Using Cascaded Fuzzy Neural Networks

Prediction of hydrogen concentration in nuclear power plant containment under severe accidents using cascaded fuzzy neural networks

Smart support system for diagnosing severe accidents in nuclear power plants

Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks

Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression

Prediction of golden time using SVR for recovering SIS under severe accidents

Prediction of golden time for recovering SISs using deep fuzzy neural networks with rule-dropout

Prediction of major transient scenarios for severe accidents of nuclear power plants

Detection and Diagnostics of Loss of Coolant Accidents Using Support Vector Machines

Prediction of Leak Flow Rate Using Fuzzy Neural Networks in Severe Post-LOCA Circumstances

Prediction of Axial DNBR Distribution in a Hot Fuel Rod Using Support Vector Regression Models

Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks

Design of a fuzzy model predictive power controller for pressurized water reactors

Prediction of DNBR Using Fuzzy Support Vector Regression and Uncertainty Analysis

Design of an adaptive predictive controller for steam generators

A smart software sensor for feedwater flow measurement monitoring

Effect of local wall thinning on the collapse behavior of pipe elbows subjected to a combined internal pressure and in-plane bending load

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