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Prognostics for integrity of steam generator tubes using the general path model
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Heo, Gyunyoung
Kim, Jung Taek
Kim, Hyeonmin
Korean Nuclear Society[2018]
Google Scholar네이버 전문정보
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Cyber Security Risk Evaluation of a Nuclear I&C Using BN and ET
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Heo, Gyunyoung
Son, Hanseong
Shin, Jinsoo
Korean Nuclear Society[2017]
Google Scholar네이버 전문정보
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Application of Dynamic Probabilistic Safety Assessment Approach for Accident Sequence Precursor Analysis: Case Study for Steam Generator Tube Rupture
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Heo, Gyunyoung
Lee, Hansul
Kim, Taewan
Korean Nuclear Society[2017]
Google Scholar네이버 전문정보
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Study on Quantification Method Based on Monte Carlo Sampling for Multiunit Probabilistic Safety Assessment Models
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Han, Sang Hoon
Yang, Joon Eon
Park, Jin Hee
Oh, Kyemin
Lim, Ho-Gon
Heo, Gyunyoung
Korean Nuclear Society[2017]
Google Scholar네이버 전문정보
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Analysis of the technical status of multiunit risk assessment in nuclear power plants
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Baek, Sejin
Yoon, Ji Woong
Seong, Changkyung
Kim, Man Cheol
Heo, Gyunyoung
Korean Nuclear Society[2018]
Google Scholar네이버 전문정보
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Modified parity space averaging approaches for online cross-calibration of redundant sensors in nuclear reactors
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Heo, Gyunyoung
Kassim, Moath
Korean Nuclear Society[2018]
Google Scholar네이버 전문정보
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Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
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Ahmed, Ibrahim
Zio, Enrico
Heo, Gyunyoung
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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Cyber attack taxonomy for digital environment in nuclear power plants
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Heo, Gyunyoung
Zio, Enrico
Song, Jae-gu
Shin, Jinsoo
Kim, Seungmin
Korean Nuclear Society[2020]
Google Scholar네이버 전문정보
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