Search Results - "Ho-gon Lim"
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Multi-unit Level 1 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
Published in Nuclear engineering and technology (01-12-2018)“…Following a surge of interest in multi-unit risk in the last few years, many recent studies have suggested methods for multi-unit probabilistic safety…”
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AIMS-MUPSA software package for multi-unit PSA
Published in Nuclear engineering and technology (01-12-2018)“…The need for a PSA (Probabilistic Safety Assessment) for a multi-unit at a site is growing after the Fukushima accident. Many countries have been studying…”
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Multi-unit Level 2 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
Published in Nuclear engineering and technology (01-12-2018)“…The risk of multi-unit nuclear power plants (NPPs) at a site has received considerable critical attention recently. However, current probabilistic safety…”
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Development of logical structure for multi-unit probabilistic safety assessment
Published in Nuclear engineering and technology (01-12-2018)“…Site or multi-unit (MU) risk assessment has been a major issue in the field of nuclear safety study since the Fukushima accident in 2011. There have been few…”
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Multi-unit PSA based risk evaluation framework for utilizing cross-tie systems for nuclear power plants
Published in Nuclear engineering and technology (2024)“…The Fukushima accident showed that the safety of multiple nuclear power plants (NPPs) at the same site could be jeopardized simultaneously. Since then, many…”
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Technical note: Estimation of Korean industry-average initiating event frequencies for use in probabilistic safety assessment
Published in Nuclear engineering and technology (01-01-2020)“…One fundamental element of probabilistic safety assessment (PSA) is the initiating event (IE) analysis. Since IE frequencies can change over time, time-trend…”
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Multi-unit Level 3 probabilistic safety assessment: Approaches and their application to a six-unit nuclear power plant site
Published in Nuclear engineering and technology (01-12-2018)“…The importance of performing Level 3 probabilistic safety assessments (PSA) along with a general interest in assessing multi-unit risk has been sharply…”
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Study on Quantification Method Based on Monte Carlo Sampling for Multiunit Probabilistic Safety Assessment Models
Published in Nuclear engineering and technology (01-06-2017)“…In Korea, many nuclear power plants operate at a single site based on geographical characteristics, but the population density near the sites is higher than…”
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A pragmatic approach to modeling common cause failures in multi-unit PSA for nuclear power plant sites with a large number of units
Published in Reliability engineering & system safety (01-03-2020)“…•A pragmatic approach to model common cause failures in multi-unit PSA is provided.•This approach is applicable to nuclear power plant sites with a large…”
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Multi-unit PSA based risk evaluation framework for utilizing cross-tie systems for nuclear power plants
Published in Nuclear engineering and technology (01-10-2024)“…The Fukushima accident showed that the safety of multiple nuclear power plants (NPPs) at the same site could be jeopardized simultaneously. Since then, many…”
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Quantification of LOCA core damage frequency based on thermal-hydraulics analysis
Published in Nuclear engineering and design (15-04-2017)“…•We quantified the LOCA core damage frequency based on the best-estimated success criteria analysis.•The thermal-hydraulic analysis using MARS code has been…”
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Top event probability evaluation of a fault tree having circular logics by using Monte Carlo method
Published in Nuclear engineering and design (01-02-2012)“…The current quantification method using minimal cut set generation in a PSA (Probabilistic Safety Assessment) uses several approximations for practical…”
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MOSAIQUE – A network based software for probabilistic uncertainty analysis of computerized simulation models
Published in Nuclear engineering and design (01-05-2011)“…► We developed network-based software for uncertainty analysis named as MOSAIQUE. ► MOSAIQUE can automatically generate sample input of a computer simulation…”
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Systematic treatment of circular logics in a fault tree analysis
Published in Nuclear engineering and design (01-04-2012)“…► We developed a new treatment method of a circular logic in a fault tree. ► The main idea to treat a circular logic is to use the initial condition of a…”
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An analytic solution for a fault tree with circular logics in which the systems are linearly interrelated
Published in Reliability engineering & system safety (01-06-2007)“…A circular logic or a logical loop is defined as the infinite circulation of supporting relations due to their mutual dependencies among the systems in the…”
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Fault tree conditioning methods to trace system configuration changes for the application to low-power/shutdown PSA
Published in Reliability engineering & system safety (01-10-2009)“…There have been few Probabilistic Safety Assessments (PSAs) for a whole low power and shutdown (LPSD) period since the difficulties and the cost for these…”
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Effect of uncertainties in best-estimate thermal hydraulic analysis on core damage frequency for PSA
Published in Nuclear engineering and design (01-12-2010)“…Generally, thermal hydraulic (TH) analyses have been performed as part of a probabilistic safety assessment (PSA) to construct event trees and to evaluate…”
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Journal Article Conference Proceeding -
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A quantitative analysis of a risk impact due to a starting time extension of the emergency diesel generator in optimized power reactor-1000
Published in Reliability engineering & system safety (01-07-2007)“…An emergency diesel generator (EDG) is the ultimate electric power supply source for the operation of emergency engineered safety features when a nuclear power…”
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An estimation of an operator's action time by using the MARS code in a small break LOCA without a HPSI for a PWR
Published in Nuclear engineering and design (01-04-2007)“…To estimate the success criteria of an operator's action time for a probabilistic safety/risk assessment (PSA/PRA) of a nuclear power plant, the information…”
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Input-profile-based software failure probability quantification for safety signal generation systems
Published in Reliability engineering & system safety (01-10-2009)“…The approaches for software failure probability estimation are mainly based on the results of testing. Test cases represent the inputs, which are encountered…”
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