ScholarWorks@Hanyang University: Jae, Moo sung

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Jae, Moo sung (제무성)

COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)

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Tel 02-2220-1346
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Level 3 PSA:5||PSA:3||MACCS:3||Severe accident:3||MELCOR:3||Operational Events:2||Large early release frequency:2||PRA:2||Conditional Core Damage Probability:2||Risk:2||Early fatality:2||Evacuation:2||CDF:2||Probabilistic Risk Assessment:2||Incremental Core Damage Probability:2||Probabilistic safety assessment:2||Site core damage frequency:2||MACCS2:2||Site risk assessment:2||Multiunit probabilistic safety assessment:2||MACSTOR/KN400:2||Accident Sequence Precursor:2||Emergency Operating Procedures:1||Emergency Response Model:1||Emergency preparedness plan:1||Emergency response:1||Evacuation Time Estimate:1||Evacuation time estimate (ETE):1||FAULT TREE ANALYSIS:1||FUZZY LOGIC:1||Fission product release:1||Full power operation:1||Functional failure:1||GM counter:1||Human errors:1||ISLOCA:1||Impact index:1||Ingestion chain model:1||Ingestion dose:1||Inter unit dependency:1||Interunit common cause failure:1||Interunit dependency:1||LOSS OF COOLANT:1||Large Early Release Frequency:1||Level 2 Probabilistic Safety Assessment (PSA):1||Level 2 multiunit probabilistic safety assessment uncertainty analysis:1||Level 2 probabilistic safety assessment code:1||Level 2 probabilistic safety assessment uncertainty analysis:1||Logic tree:1||MSPARSITE:1||Mid loop operation:1||Minimal Cut Sets (MCSs):1||Minimal Cutset Upper Bound (MCUB):1||Minimal cut sets:1||Monte Carlo Simulation Allocation Method (MCSAM):1||Multi unit probabilistic safety assessment:1||Multiunit PSA:1||Multiunit accident:1||Multiunit loss of offsite power:1||Nuclear power plants:1||Nuclear safety:1||OPR1000:1||PMR200:1||PROBABILITY:1||Passive safety system:1||Pixelated detectors and associated VLSI electronics:1||Power operated relief valve (PORV):1||Pressure loss coefficient:1||Probabilistic Safety Assessment (PSA):1||Probabilistic risk assessment:1||Protective action recommendations:1||Public Protection Measure:1||Public protection measure:1||RIR decisionmaking:1||Radiation release frequency:1||Radioecology:1||Rare Events Approximation (REA):1||Release location:1||Release pathway:1||Reliability:1||Riskinformed Regulations:1||Riskinformed regulations:1||SFR:1||Safety culture:1||Seismic Probabilistic Safety Assessment (SPSA):1||Sensitivity analysis:1||Severe Accident:1||Severe Accident Phenomena:1||Severe accident management strategy (SAMG):1||Site risk indicator:1||Source Term Category (STC):1||Source term:1||Steam Generator Tube Rupture (SGTR) without fission product release:1||Steam generator tube rupture (SGTR):1||Swain&apos:1||System dynamics:1||TSISCORSIM:1||Uncertainty:1||Uncertainty Analysis:1||Uncertainty propagation:1||VHTR:1||VLSI circuits:1||Westinghouse 2loop PWR:1||Xray radiography and digital radiography (DR):1||Yongbyon:1||accident diagnosis:1||alternate AC diesel generator:1||basket failure:1||bayesian theorem:1||containment failure:1||containment integrity:1||containmentfiltered venting system:1||dead time:1||distance(거리):1||dynamic:1||emergency operating procedures:1||event tree analysis:1||high temperature gas cooled reactor(고온가스냉각로):1||hybrid model:1||hydrogen explosion(수소폭발):1||hydrogen production facility(수소생산시설):1||influence diagrams:1||ingestion chain model:1||initiating events identification:1||internal event:1||iodinesulfur process:1||level 2 probabilistic risk assessment:1||master logic diagram:1||minimal cutsets:1||multiunit loss of offsite power:1||multiunit probabilistic risk assessment:1||nuclear power plant:1||offsite Consequence:1||probabilistic safety assessment:1||probability(확률):1||quantitative safety impact:1||radiation release frequency:1||radioecology:1||reactor:1||release consequence:1||risk:1||risk assessment:1||s dependency model:1||safety:1||safety culture:1||safety culture impact assessment model:1||safety culture impact index:1||severe accident:1||shared equipment:1||system dynamics:1||단기호흡률:1||생활시간:1||Accident Management:1||장기호흡률:1||Accidents diagnose:1||Basket failure:1||Binary Decision Diagram (BDD):1||Bypass flow:1||CFD:1||COMIDA2:1||COMPUTER CALCULATIONS:1||Cesium behavior:1||Commoncause initiator:1||Consequence analysis:1||Containment filtered venting system (CFVS):1||Containment performance analysis:1||Core Damage Frequency (CDF):1||Cross flow:1||DAMAGE:1||Decomposition Event Tree (DET):1||Dynamic:1||Dynamic model:1||EPZ:1||ERRORS:1||Early Fatality:1||

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