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Showing results 14 to 43 of 55

Issue DateTitleAuthor(s)
2019-10Development of a Bayesian Analysis Program, MUDAP제무성
2020-07Development of A Consequence Analysis Computer Code, HYRISK제무성
2016-05Development of A Framework For Assessing Accident Sequence Precursor and Its Application제무성
2016-05Development of A Methodology for Assessong Various Accident Management Strategies Using Decision Tree Models제무성
2016-05Development of a Methodology for VHTR Accident Consequence Assessment제무성
2017-01Development of a New Methodology for Quantifying, Nuclear Safety Culture제무성
2017-03Development of an Accident Sequence Precursor Methodology and its Application to Significant Accident Precursors제무성
2016-10Development of ASP Methodology and its Application to the Significant Accident Precursors제무성
2019-05A Development of Database Management Application for Level 1 Multi-unit PSA제무성
2020-05A development of methodology for assessing the inter-unit common cause failure in multi-unit PSA model제무성
2016-10An Estimation of Human Error Probability of Filtered Containment Venting System Using Dynamic HRA Method제무성
2019-05An Evaluation of Severe Accident Management Strategy Using PORVs in SGTR Accident제무성
2015-04Experimental investigation and CFD analysis on cross flow in the core of PMR200제무성
2014-08Fast signal transfer in a large-area X-ray CMOS image sensor제무성
2016-10Gap Analysis Between Single-unit and Multi-unit PSAs for Korean NPPs제무성
2019-05Identification of Factors Affecting Evacuation Time Estimates in Seismic Events제무성
2016-10Identification of Initiating Events for PGSFR제무성
2018-05Ingestion Dose Evaluation of Korean Based on Dynamic Model in a Severe Accident제무성
2015-10An Internal Dose Assessment Associated with Personal Food Intake제무성
2019-10Lessons at the Fukushima Daiichi Accident제무성
2014-06A Methodology for Safety Culture Index Assessment Using Minimal Cut Sets제무성
2015-10A Methodology To Incorporate The Safety Culture Into Probabilistic Safety Assessments제무성
2019-09Preliminary Evacuation Time Estimate in Korea and Its Application into Level 3 PSA제무성
2019-05A Preliminary Site Risk Assessment for Multi-unit Nuclear Power Plants제무성
2019-10A Preliminary Site Risk Assessment for the Reference Site in Korea제무성
2017-03A Probabilistic Consequence Assessment for a Very High Temperature Reactor제무성
2015-10A Probabilistic Methodology for Assessing the Effectiveness of the Containment Filtered Venting Systems제무성
2015-10A Qualitative Accident Scenario Analysis for a Very High Temperature Reactor제무성
2016-05A Quantitative Accident Sequence Analysis for a VHTR제무성
2018-01Quantitative assessment of severe accident management strategies in a nuclear power plant제무성

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