Jung Sung Kang

Ji Hyeon Shin

Hyung Jun Kim

Junyong Bae

Jeonghun Choi

Yunyeong Heo

Jeeyea Ahn

Jae Min Kim

Jong Woo Park

Geunhe Kim

Jeongil Seo

Nuclear Safety Assessment and Plant HMI Evolution (NuSAPHE) Lab. NuSAPHE Lab.은 원자력발전소의 안전한 운영을 위한 리스크 평가 방법론, 혁신적인 인간-기계 상호작용, 그리고 이를 위한 인공지능 기술의 적용을 연구합니다. We are performing the researches for ENHANCING THE ACCURACY OF RISK ASSESSMENT and DESIGNING SAFER NUCLEAR POWER PLANT.

NuSAPHE Lab.은 원자력발전소의 안전한 운영을 위한 리스크 평가 방법론, 혁신적인 인간-기계 상호작용, 그리고 이를 위한 인공지능 기술의 적용을 연구합니다.

Concept of understandable diagnostic cause visualization with explainable AI and multilevel flow modeling

Robust diagnosis of abnormal events using fuzzy-based feature extraction in nuclear power plants

Current Progress in the Application of Artificial Intelligence for Nuclear Power Plant Operation

Exhaustive Test Case Generation for Nuclear Safety Software Based on the Software Logic Model

Radiation safety assessments for radioactive concrete recycling workers and residents

Approach to diagnosing multiple abnormal events with single-event training data

Human reliability evaluation method covering operator action timing for dynamic probabilistic safety assessment

Deep reinforcement learning for a multi-objective operation in a nuclear power plant

Strategy to coordinate actions through a plant parameter prediction model during startup operation of a nuclear power plant

RNN-based integrated system for real-time sensor fault detection and fault-informed accident diagnosis in nuclear power plant accidents

Radiological safety evaluation of a recycling facility for dismantled concrete waste

An interpretable convolutional neural network for nuclear power plant abnormal events

Bayesian belief network-based human reliability analysis methodology for start-up and shutdown operations in nuclear power plants

Operation validation system to prevent human errors in nuclear power plants

Consistency check algorithm for validation and re-diagnosis to improve the accuracy of abnormality diagnosis in nuclear power plants

Concept of an Intelligent Operator Support System for Initial Emergency Responses in Nuclear Power Plants

Graded approach to determine the frequency and difficulty of safety culture attributes: The F-D matrix

Limit surface/states searching algorithm with a deep neural network and Monte Carlo dropout for nuclear power plant safety assessment

Simulation Optimization Framework for Dynamic Probabilistic Safety Assessment

Framework for the development of guidelines for nuclear power plant decommissioning workers based on risk information

Real-time Prediction of Nuclear Power Plant Parameter Trends following Operator Actions

Abnormal state diagnosis model tolerant to noise in plant data

Development of a multi-unit seismic conditional core damage probability model with uncertainty analysis

A convolutional neural network model for abnormality diagnosis in a nuclear power plant

Deep learning-based procedure compliance check system for nuclear power plant emergency operation

A Sensor Fault-Tolerant Accident Diagnosis System

Abnormality Diagnosis Model for Nuclear Power Plants Using Two-Stage Gated Recurrent Units

External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea

Occupational internal exposure calculation during dismantling of bio-shield of Kori nuclear power plant unit#1

Comparison of Multilayer Perceptron and Long Short-Term Memory for Plant Parameter Trend Prediction

A Quantitative Assessment Framework for Cyber-attack Scenarios on Nuclear Power Plants Using Relative Difficulty and Consequence

Experimental approach to evaluate software reliability in hardware-software integrated environment

The effect of communication quality on team performance in digital main control room operations

Consistency Index-Based Sensor Fault Detection System for Nuclear Power Plant Emergency Situations Using an LSTM Network

Optimization of software development life cycle quality for NPP safety software based on a risk-cost model

Exhaustive testing of safety-critical software for reactor protection system

Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plants

Analysis of interface management tasks in a digital main control room

Evaluation of effectiveness of fault-tolerant techniques in a digital instrumentation and control system with a fault injection experiment

Safety Assessment Framework for Nuclear Power Plant Decommissioning Workers

Probabilistic safety assessment-based importance analysis of cyber-attacks on nuclear power plants

Development of a Bayesian belief network model for software reliability quantification of digital protection systems in nuclear power plants

Bayesian Belief Network Model Quantification Using Distribution-Based Node Probability and Experienced Data Updates for Software Reliability Assessment

Development of simulation-based testing environment for safety-critical software

Fault-Weighted Quantification of Fault Detection Coverage through Fault Mode and Effect Analysis Method in Digital I&C Systems

Reactor protection system software test-case selection based on input-profile considering concurrent events and uncertainties

PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems

Reliability modeling of safety-critical network communication in a digitalized nuclear power plant

Estimation of reactor protection system software failure probability considering undetected faults

Important Factors Affecting Fault Detection Coverage in Probabilistic Safety Assessment of Digital Instrumentation and Control Systems

Reliability modeling of digital component in plant protection system with various fault-tolerant techniques

Design-related influencing factors of the computerized procedure system for inclusion into human reliability analysis for the advanced control room

Quantitative Estimation of the Human Error Probability during Soft Control Operations

An empirical study on the basic human error probabilities for NPP advanced main control room operation using soft control

Fault Detection Coverage Quantification of Automatic Test Functions of Digital I&C Systems in NPPs

Human Error Mode Identification for NPP Main Control Room Operations using Soft Controls

Reliability Assessment Method for NPP Digital I&C Systems Considering the Effect of Automatic Periodic Tests

Modeling of a Dependence between Human Operators in Advanced Main Control Rooms

Experimental Investigation into the Effects of Decision Support Systems on Operator Performance

An Overview of Risk Quantification Issues of Digitalized Nuclear Power Plants using Static Fault Tree

An Analytic Approach to Quantitative Effect Estimation of Operation Advisory System based on Human Cognitive Process using the Bayesian Belief Network

Development of an integrated decision support system to aid cognitive activities of operators

A Dynamic Neural Network Aggregation Model for Transient Diagnosis in Nuclear Power Plants

A Neural Network based Operation Guidance System for Procedure Presentation and Operation Validation in Nuclear Power Plants

Investigation on Relationship Between Information Flow Rate and Mental Workload of Accident Diagnosis Tasks in NPPs

A Dynamic Neural Network based Accident Diagnosis Advisory System for Nuclear Power Plants

Development of an Automated Operating Procedure System using Fuzzy Colored Petri Nets for Nuclear Power Plants

Investigation on applicability of Information Theory to Prediction of Operator Performance in Diagnosis Tasks at Nuclear Power Plants

Multi-Abnormality Attention Diagnosis Model Using One-vs-Rest Classifier in a Nuclear Power Plant

Reliability Assessment of NPP Safety Class Equipment Considering the Manufacturing Quality Assurance Process

Effect Analysis of Faults in Digital I&C Systems of Nuclear Power Plants

Human Reliability Analysis of Soft Control Operations in Nuclear Power Plants: Issues and Perspectives

Design of an Integrated Operator Support System for Advanced NPP MCRs: Issues and Perspectives

Conceptual Design of a Remote Monitoring and Control System for Nuclear Power Plants

NuSAPHE LAB

교수님 소개

이승준

연구실 소개

연구실 키워드

알럼나이가 간 회사

연구실 지원 방법

대우 조건

연도별 논문 인용수

저널 & 학회 논문 출판 수

연구실 논문 목록

Concept of understandable diagnostic cause visualization with explainable AI and multilevel flow modeling

Robust diagnosis of abnormal events using fuzzy-based feature extraction in nuclear power plants

Current Progress in the Application of Artificial Intelligence for Nuclear Power Plant Operation

연구실 보유 특허

대학별 입시끈

우리 연구실 모집

교수님 소개

이승준

연구실 키워드

알럼나이가 간 회사

연구실 지원 방법

대우 조건

연도별 논문 인용수

저널 & 학회 논문 출판 수

연구실 논문 목록

Concept of understandable diagnostic cause visualization with explainable AI and multilevel flow modeling

Robust diagnosis of abnormal events using fuzzy-based feature extraction in nuclear power plants

Current Progress in the Application of Artificial Intelligence for Nuclear Power Plant Operation

연구실 보유 특허

최근 3년간 연구실적 높은 연구실

대학별 입시끈

우리 연구실 모집