| 81 | A leakage correction with burnup-dependent GPS method in two-step core depletion analysis Jeong, Hae Sun; Oh, Taesuk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.183, 2023-04 |
| 82 | A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses Yu, Hwan Yeal; Kim, Woosong; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.129, pp.30 - 55, 2019-07 |
| 83 | A linear multiple balance method with high order accuracy for discrete ordinates neutron transport equations Park, CJ; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.28, no.15, pp.1499 - 1517, 2001-10 |
| 84 | A Mass Conservative Numerical Solution of Vertical Water Flow and Mass Transport Equations in Unsaturated Porous Media seung cheol lim; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.20, no.2, pp.91 - 99, 1993 |
| 85 | A MEASURE OF THE DIFFICULTY OF SYSTEM DIAGNOSIS AND ITS RELATIONSHIP TO COMPLEXITY GOLAY, MW; Seong, Poong-Hyun; MANNO, VP, INTERNATIONAL JOURNAL OF GENERAL SYSTEMS, v.16, no.1, pp.1 - 23, 1989 |
| 86 | A Mechanistic Critical Heat Flux Model for High-Subcooling, High-Mass-Flux, and Small-Tube Diameter Conditions Kwon, Young Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.32, no.1, pp.17 - 33, 2000-02 |
| 87 | A mechanistic critical heat flux model for wide range of subcooled and low quality flow boiling Kwon, YM; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.188, no.1, pp.27 - 47, 1999-04 |
| 88 | A method for evaluating fault coverage using simulated fault injection for digitalized systems in nuclear power plants Kim, SJ; Seong, Poong-Hyun; Lee, JS; Kim, MC; Kang, Hyun Gook; Jang, SC, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.5, pp.614 - 623, 2006-05 |
| 89 | A method for identifying instrument faults in nuclear power plants possibly leading to wrong situation assessment Kim, Man Cheol; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.93, no.2, pp.316 - 324, 2008-02 |
| 90 | A method for risk-informed safety significance categorization using the analytic hierarchy process and bayesian belief networks Ha, JS; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.83, no.1, pp.1 - 15, 2004-01 |
| 91 | A method for selection of spent nuclear fuel (SNF) transportation route considering socioeconomical cost based on contingent valuation method (CVM) Kim, Young Sik; Kim, Ar Ryum; Shin, Seung Ki; Ha, Jung Su; Seong, Poong-Hyun, Nuclear Safety and Simulation, v.4, no.1, pp.34 - 43, 2013-03 |
| 92 | A method of formal requirement analysis for NPP I & C systems based on UML modeling with software cost reduction Koo, SR; Son, HS; Seong, Poong-Hyun, JOURNAL OF SYSTEMS AND SOFTWARE, v.67, no.3, pp.213 - 224, 2003-09 |
| 93 | A Method of Knowledge Base Verification for Nuclear Power Plant Expert System Using Extended Petri Nets Kwon, Il Won; Seong, Poong Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.28, no.6, pp.522 - 531, 1996-12 |
| 94 | A methodology for a quantitative assessment of safety culture in NPPs based on Bayesian networks Kim, Younggab; Lee, Seungmin; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.102, pp.23 - 36, 2017-04 |
| 95 | A methodology for benefit assessment of using in-core neutron detector signals in core protection calculator system (CPCS) for Korea standard nuclear power plants (KSNPP) Han, S; Kim, US; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.26, no.6, pp.471 - 488, 1999-04 |
| 96 | A methodology for determining optimal durations for the use of contaminated crops as fodder following a nuclear accident using a dynamic food-chain model Hwang, WT; Han, MH; Cho, Gyuseong, ANNALS OF NUCLEAR ENERGY, v.27, no.12, pp.1071 - 1086, 2000-08 |
| 97 | A methodology for diagnosing FAC induced pipe thinning using accelerometers and deep learning models Chae, Young Ho; Kim, Seung Geun; Kim, Hyeonmin; Kim, Jung Taek; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.143, 2020-08 |
| 98 | A methodology for evaluating alarm-processing systems using informational entropy-based measure and the analytic hierarchy process Kang, Hyun Gook; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.46, no.6, pp.2269 - 2280, 1999-12 |
| 99 | A methodology for optimisation of countermeasures for animal products after a nuclear accident and its application Hwang, WT; Cho, Gyuseong; Han, MH, ANNALS OF NUCLEAR ENERGY, v.26, no.17, pp.1537 - 1550, 1999-11 |
| 100 | A methodology for the quantitative evaluation of NPP fault diagnostic systems dynamic aspects Kim, JongHyun; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.27, no.16, pp.1459 - 1481, 2000-11 |
