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Results 11-20 of 44 (Search time: 0.007 seconds).
| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
| A steam generator model identification and robust H-infinity controller design with nu-gap metric for a feedwater control system Sohn, Jong Joo; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.37, no.2, pp.180 - 195, 2010-02 | |
| Quantification of unavailability caused by random failures and maintenance human errors in nuclear power plants Khalaquzzman, Mohammad; Kang, Hyun-Gook; Kim, Man-Cheol; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.240, no.6, pp.1606 - 1613, 2010-06 | |
| STATE TOKEN PETRI NET MODELING METHOD FOR FORMAL VERIFICATION OF COMPUTERIZED PROCEDURE INCLUDING OPERATOR'S INTERRUPTIONS OF PROCEDURE EXECUTION FLOW Kim, Yun Goo; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.44, no.8, pp.929 - 938, 2012-12 | |
| Optimization of periodic testing frequency of a reactor protection system based on a risk-cost model and public risk perception Khalaquzzman, Mohammad; Kang, Hyun-Gook; Kim, Man-Cheol; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.241, no.5, pp.1538 - 1547, 2011-05 | |
| A quantitative assessment method for safety-critical signal generation failures in nuclear power plants considering dynamic dependencies Shin, Seung-Ki; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.38, no.2-3, pp.269 - 278, 2011-02 | |
| Heuristic guidelines and experimental evaluation of effective augmented-reality based instructions for maintenance in nuclear power plants Yim, Ho Bin; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.240, no.12, pp.4096 - 4102, 2010-12 | |
| CREAM-based communication error analysis method (CEAM) for nuclear power plant operators communication Lee, Seung Min; Ha, Jun Su; Seong, Poong-Hyun, JOURNAL OF LOSS PREVENTION IN THE PROCESS INDUSTRIES, v.24, no.1, pp.90 - 97, 2011-01 | |
| An Abstraction Hierarchy based mobile PC display design in NPP maintenance considering the level of expertise Bin Yim, Ho; Kim, In; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.241, no.5, pp.1881 - 1888, 2011-05 | |
| FBDVerifier: Interactive and Visual Analysis of Counter-example in Formal Verification of Function Block Diagram Jee, Eunk Young; Jeon, Seungjae; Cha, Sungdeok; Koh, Kwangyong; Yoo, Junbeom; Park, Geeyong; Seong, Poong-Hyun, JOURNAL OF RESEARCH AND PRACTICE IN INFORMATION TECHNOLOGY, v.42, no.3, pp.171 - 188, 2010-08 | |
| A model for estimation of reactor spurious shutdown rate considering maintenance human errors in reactor protection system of nuclear power plants Khalaquzzman, Mohammad; Kang, Hyun-Gook; Kim, Man-Cheol; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.2963 - 2971, 2010-10 |
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