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Results 131-140 of 270 (Search time: 0.006 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| Preliminary Risk Assessments for Spent Nuclear Fuel (SNF) Transportation From Kori-site To The Hypothetical SNF Storage Facility Kim, Jae San; Ha, Jun Su; Seong, Poong-Hyun, 한국원자력학회 2006 추계학술발표대회, 한국원자력학회, 2006-11-02 | |
| A Quantitative Approach to the Information Processing Capacity of Main Control Room Operators in Nuclear Power Plant Kim, Ji Tae; Seong, Poong-Hyun, 대한인간공학회 2006 춘계학술대회, 대한인간공학회, 2006-05-25 | |
| Fault tolerance evaluation of digital plant protection system in nuclear power plants Lee, J.S.; Kim, M.C.; Seong, Poong-Hyun; Kang, H.G.; Jang, S.C., 2005 Annual Meeting - American Nuclear Society, v.92, pp.411 - 412, 2005-06-05 | |
| Fault tree-based software safety analysis of function block diagrams Koh, K.Y.; Seong, Poong-Hyun, ISSNP 2007, 2007-07 | |
| A Systematic Approach to Safety Verification of Function Block Diagrams Koh, KY; Seong, Poong-Hyun; Jee, EK; Cha, SD; Park, GY, ISSNP2008, 2008-09-20 | |
| A method for risk-informed safety significance categorization using the AHP and BBN Ha, Jun Su; Seong, Poong-Hyun, Proceedings of CUP Workshop on Advanced I&C Systems for NPP Operation & Maintenance, pp.1 - 10, 2003-11 | |
| Adding Dynamic Nodes to Reliability Graph with General Gate Shin, Seung Ki; Seong, Poong-Hyun, HCII 2007, 2007-07-23 | |
| A quantitative impact analysis of sensor failures on nuclear power plant operators in accident situations Kim, M.C.; Seong, Poong-Hyun, 2005 Annual Meeting - American Nuclear Society, v.92, pp.451 -, 2005-06-05 | |
| A Study on a Systematic Approach of Verification and Validation of a Computerized Procedure System: ImPRO Qin, Wei; Seong, Poong-Hyun, 한국원자력학회 2003 추계학술발표회, pp.198 - 198, 한국원자력학회, 2003-10 | |
| Strategy-Based Evaluation of Information Aids for the Diagnosis of Nuclear Power Plants Kim, Jong Hyun; Seong, Poong-Hyun, 한국원자력학회 2003 추계학술발표회, pp.218 - 218, 한국원자력학회, 2003-10 |
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