Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 241 to 260 of 10276
| 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 |
| 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 |
| A Mechanistic Model of Onset of Flow Instability Due to Mergence of Bubble Layers in a Vertical Narrow Rectangular Channel Lee, Juhyung; Jeong, Yong Hoon; Chang, Soon Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-12 |
| A Mechanistic Model to Predict the CHF on a Downward Facing Curved Surface Park, Hae Min; Jeong, Yong-Hoon, The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), American Nuclear Society, 2014-12-15 |
| A Method for Determining Deposition Rates in an Electrorefiner Using Electrode Potentials Devin. S. Rappleye; Riley. M. Cumberland; Yim, Man-Sung, 2012 International Pyroprocessing Research Conference, Argonne National Laboratory Chemical Sciences and Engineering Division, 2012-08 |
| 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 |
| 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 |
| A Method for Monitoring Deposition at a Solid Cathode in an Electrorefiner for a Two-Species System Using Electrode Potentials Devin Rappleye; Riley M. Cumberland; Yim, Man-Sung, 2013 Global Conference, 2013 Global Conference, 2013-10-03 |
| 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 |
| A Method for Risk-Informed Safety Significance Categorization Using the Analytic Hierarchy Process (AHP) and Bayesian Belief Networks (BBN) Ha, Jun Su; Seong, Poong-Hyun, 한국원자력학회 2003 춘계학술발표회, pp.91 - 91, 한국원자력학회, 2003-05 |
| 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 |
| A Method for Selection of Spent Nuclear Fuel (SNF) Transportation Route Considering Socioeconomic Cost based on Contingent Valuation Method (CVM) Kim, YS; Goh, GT; Seong, Poong-Hyun, ISSNP2008, 2008-09-20 |
| 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 |
| A method of concurrent imaging for in-situ PET monitoring in hadron therapy Son, Kihong; Cho, Seungryong; Kim, Jin Sung; Kim, Heejong; Kao,Chien-Min, 54th Annual Conference of the Particle Therapy Co-Operative Group, PTCOG, 2015-05-22 |
| 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 |
| A Method of Formal Requirement Analysis for NPP I&C Systems Based on Object-Oriented UML Modeling with Software Cost Reduction Koo, Seo Ryong; Son, Han Seong; Seong, Poong-Hyun, International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies (NPIC&HMIT 2000), 2000-11 |
| A Method of Formal Requirements Analysis for NPP I&C systems Based on Object-Oriented Visual Modeling with SCR Koo, Seo Ryong; Seong, Poong-Hyun, 한국원자력학회 '99 추계 학술발표회, 한국원자력학회, 1999-10 |
| 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 |
| A Method to Select Test Input Cases for Safety-critical Software 김희은; 손한성; 강현국, KNS 2013 춘계 학술발표대회, 한국원자력학회, 2013-05-31 |
| 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 |
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- 1,207 2020 - 2024
- 4,359 2010 - 2019
- 2,657 2000 - 2009
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