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Featured researches published by Kilyoo Kim.


Journal of the Korean Society of Safety | 2014

Fire Simulations for the Abandonment Risk Assessment of Main Control Room Fire in Domestic Nuclear Power Plant

Dae Il Kang; Kilyoo Kim; Seung-Cheol Jang; Seong Yeon Yoo

In this paper, to systematically assess the abandonment risk of main control room (MCR) fire, fire simulations with Fire Dynamics Simulator were performed and abandonment probabilities were estimated for the MCR bench-board fire of domestic reference nuclear power plant. The fire simulation scenarios performed in this study included propagating and non-propagating fires of the MCR bench-board, and the availability and unavailability of heating, ventilation, and air conditioning system (HVACS). The following results were obtained. First, temperature was the major abandonment impact factor for the MCR bench-board fire if the HVACS was available and optical density was that if the HVACS was unavailable. Second, the fire scenario contributing the MCR bench-board fire abandonment risk was identified to be only the propagating fire. Third, it was confirmed that the abandonment probability of the MCR bench-board fire for domestic reference nuclear power plant could be reduced by using the fire modeling.


10th International Conference on Nuclear Engineering, Volume 4 | 2002

Importance Analysis of In-Service Testing Components for Ulchin Unit 3

Dae-Il Kang; Kilyoo Kim; Jaejoo Ha

We performed an importance analysis of In-Service Testing (157) components for Ulchin Unit 3 using the integrated evaluation method for categorizing component safety significance developed in this study. The developed method is basically aimed at having a PSA expert perform an importance analysis using PSA and its related information. The importance analysis using the developed method is initiated by ranking the component importance using quantitative PSA information. The importance analysis of the IST components not modeled in the PSA is performed through the engineering judgment, based on the expertise of PSA, and the quantitative and qualitative information for the 157 components. The PSA scope for importance analysis includes not only Level 1 and 2 internal PSA but also Level 1 external and shutdown/low power operation PSA. The importance analysis results of valves show that 167 (26.55%) of the 629 IST valves are HSSCs and 462 (73.45%) are LSSCs. Those of pumps also show that 28 (70%)of the 40157 pumps are HSSCs and 12 (30%) are LSSCs.


12th International Conference on Nuclear Engineering, Volume 3 | 2004

A Balancing Method for Calculating a Component RAW Including CCF

Kilyoo Kim; Dae Il Kang; Joon-Eon Yang

In this paper, a method called the ‘Balancing Method’ to derive a component RAW with basic event RAWs including a CCF (Common Cause Failure) RAW is summarized, and compared with the NEI proposed method by mathematically checking the background on which the two methods are based. It is proved that the Balancing Method has a strong mathematically background.Copyright


Nuclear Engineering and Design | 2007

A web-based nuclear simulator using RELAP5 and LabVIEW

Kilyoo Kim; Rizwan-uddin


Nuclear Engineering and Design | 2009

An approach to the construction of a one top fire event PSA model

Dae Il Kang; Sang Hoon Han; Kilyoo Kim


Nuclear Engineering and Technology | 2002

Importance Analysis of In-Service Testing Components for Ulchin Unit 3 Using Risk-Informed In-Service Testing Approach

Dae-Il Kang; Kilyoo Kim; Jaejoo Ha


Nuclear Engineering and Design | 2015

FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

Seung-Hoon Ahn; N. Aksan; H. Austregesilo; D. Bestion; B.D. Chung; Francesco D’Auria; P. Emonot; J.L. Gandrille; Markku Hänninen; I. Horvatović; Kilyoo Kim; A. Kovtonyuk; A. Petruzzi


Nuclear Engineering and Design | 2017

Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of view

Seung-Hoon Ahn; N. Aksan; H. Austregesilo; D. Bestion; B.D. Chung; E. Coscarelli; Francesco Saverio D'Auria; P. Emonot; J.L. Gandrille; J.Y. Sauvage; Markku Hänninen; I. Horvatović; Kilyoo Kim; A. Kovtonyuk; S. Lutsanych; A. Petruzzi


Nuclear Engineering and Design | 2015

Risk assessment of main control board fire using fire dynamics simulator

Dae Il Kang; Kilyoo Kim; Seung-Cheol Jang; Seong Yeon Yoo


Archive | 2003

A Pilot Study of RI-IST Applications to IST Check Valves for Ulchin Unit 3 (M140)

Dae-Il Kang; Kilyoo Kim; Joon-Eon Yang

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Seong Yeon Yoo

Chungnam National University

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Seung-Hoon Ahn

Korea Institute of Nuclear Safety

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