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Results 1-10 of 12 (Search time: 0.006 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| A Neural Networks Based Operation Guidance System for Procedure Presentation and Validation Mo, Kun; Lee, Seung Jun; Seong, Poong-Hyun, 한국원자력학회 2006 춘계학술발표대회, 한국원자력학회, 2006-05-26 | |
| A neural networks based operation guidance system for procedure presentation and validation Mo, K.; Lee, S.J.; Seong, Poong-Hyun, 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006), pp.1202 - 1208, 2006-11-12 | |
| Human-centered HMI design to support cognitive process of operators in nuclear power plants Lee, S.J.; Seong, Poong-Hyun, 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006), pp.1191 - 1198, 2006-11-12 | |
| Integrated Human Machine Interface for Advanced Main Control Room in Nuclear Power Plants Lee, SJ; Seong, Poong-Hyun, IYNC 2006, 2006-06-20 | |
| Fault tree synthesis for software design analysis of PLC based safety-critical systems Koo, S.-R.; Cho, C.-H.; Seong, Poong-Hyun, 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006), pp.148 - 153, 2006-11-12 | |
| Preliminary Risk Assessments for On-site Spent Nuclear Fuel(SNF) Transportation in Wolsong NPPs Kim, Jae San; Ha, Jun Su; Seong, Poong-Hyun, 한국원자력학회 2006 춘계학술발표대회, 한국원자력학회, 2006-05-25 | |
| SMV model-based safety analysis of software requirements Koh, K.Y.; Seong, Poong-Hyun, 2006 Annual Meeting - American Nuclear Society, pp.189 - 190, 2006-06-04 | |
| Investigation of the Relation between Information Process Capacity and Workload in Diagnosis Tasks Kim, Ji Tae; Lee, Seung Jun; Seong, Poong-Hyun, 한국원자력학회 2006 춘계학술발표대회, 한국원자력학회, 2006-05-25 | |
| A New Curve Smoothing Method for Trend Curves Seo, Kyung Ho; Seong, Poong-Hyun, 한국원자력학회 2006 춘계학술발표대회, 한국원자력학회, 2006-05-25 | |
| 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 |
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