Browse "NE-Journal Papers(저널논문)" by Author Chang, Soon-Heung
Showing results 98 to 157 of 176
| Effects of mechanical vibration on critical heat flux in vertical annulus tube Kim, Dae Hun; Lee, Yong Ho; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.237, no.9, pp.982 - 987, 2007-05 |
| Effects of the spacer and mixing vanes on critical heat flux for low-pressure water at low-velocities Chung, JB; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.6, pp.757 - 765, 1996-10 |
| Enhancement of critical heat flux using nano-fluids for Invessel Retention-External Vessel Cooling Pham, Q. T.; Kim, Tae-Il; Song, Sub Lee; Chang, Soon-Heung, APPLIED THERMAL ENGINEERING, v.35, pp.157 - 165, 2012-03 |
| ESTIMATION OF THE FISSION PRODUCTS, ACTINIDES AND TRITIUM OF HTR-10 Jeong, Hyedong; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.5, pp.729 - 738, 2009-06 |
| EXPERIMENTAL AND ANALYTICAL STUDY ON THE TIME-DEPENDENT REMOVAL EFFICIENCY OF METHYL-IODIDE BY AN IMPREGNATED CHARCOAL BED Chang, Soon-Heung; CHO, WJ, NUCLEAR TECHNOLOGY, v.68, no.2, pp.242 - 251, 1985 |
| Experimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids Lee, Kwi Lim; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3397 - 3404, 2010-10 |
| Experimental study of post-dryout with R-134a upward flow in smooth tube and rifled tubes Lee, Song Kyu; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.11-12, pp.3153 - 3163, 2008-06 |
| Experimental study on the effect of angles and positions of mixing vanes on CHF in a 2x2 rod bundle with working fluid R-134a Shin, BS; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.235, no.16, pp.1749 - 1759, 2005-07 |
| Experimental study on the heat transfer characteristics during the pressure transients under supercritical pressures Kang, Kyoung-Ho; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.52, no.21-22, pp.4946 - 4955, 2009-10 |
| FISA-2/WS, A COMPACT REAL-TIME SIMULATOR FOR 2-LOOP PRESSURIZED WATER-REACTOR PLANTS JEONG, JJ; OH, DY; No, Hee Cheon; Chang, Soon-Heung; CHO, SJ; JUN, HY; LEE, YK, NUCLEAR TECHNOLOGY, v.90, no.3, pp.356 - 370, 1990-06 |
| Flow analysis using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.33, no.11-12, pp.966 - 974, 2006-07 |
| Flow boiling CHF enhancement using Al2O3 nanofluid and an Al2O3 nanoparticle deposited tube Kim, Tae-Il; Chang, Won-Joon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.54, no.9-10, pp.2021 - 2025, 2011-04 |
| Flow boiling CHF enhancement with surfactant solutions under atmospheric pressure Jeong, Yong Hoon; Sarwar, Mohammad Sohail; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.7-8, pp.1913 - 1919, 2008-04 |
| Flow-induced vibration in two-phase flow with wire coil inserts Kim, Dae Hun; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, v.34, no.4, pp.325 - 332, 2008-04 |
| Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification Kang, Dong Gu; Jhung, Myung Jo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.241, no.1, pp.257 - 269, 2011-01 |
| Foreword Chang, Soon-Heung; Baek W.-P.; Rempe J., NUCLEAR TECHNOLOGY, v.152, no.2, pp.143, 2005-11 |
| Fourteen lessons learned from the successful nuclear power program of the Republic of Korea Choi, Sungyeol; Jun, Eunju; Hwang, IlSoon; Starz, Anne; Mazour, Tom; Chang, Soon-Heung; Burkart, Alex R, ENERGY POLICY, v.37, no.12, pp.5494 - 5508, 2009-12 |
| Fusion Licensing and Safety Studies in Korea Kim, Hyuck Jong; Kim, Hyung Chan; Kwon, Myeun; Heo, Gyunyoung; Hwang, In-Ju; Chang, Soon-Heung; Kim, Jong Kyung; et al, IEEE TRANSACTIONS ON PLASMA SCIENCE, v.42, no.3, pp.664 - 670, 2014-03 |
| Genetic programming model for long-term forecasting of electric power demand Lee, DG; Lee, BW; Chang, Soon-Heung, ELECTRIC POWER SYSTEMS RESEARCH, v.40, no.1, pp.17 - 22, 1997-01 |
| Hybrid accident simulation methodology using artificial neural networks for nuclear power plants Choi, YJ; Kim, HK; Baek, WP; Chang, Soon-Heung, INFORMATION SCIENCES, v.160, no.1-4, pp.207 - 224, 2004-03 |
| Identification of reactor vessel failures using spatiotemporal neural networks Roh, CH; Chang, HS; Kim, HG; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.43, no.6, pp.3229 - 2, 1996-12 |
| Improved methodology for generation of axial flux shapes in digital core protection systems Lee, GC; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.29, no.7, pp.805 - 819, 2002-05 |
| Korea looks beyond the next generation Chang, Soon-Heung; No, Hee Cheon; Baek, WP; Lee, SI; Lee, SW, NUCLEAR ENGINEERING INTERNATIONAL, v.42, no.511, pp.12 - 12, 1997-02 |
| LINEAR PROGRAMMING OPTIMIZATION OF NUCLEAR ENERGY STRATEGY WITH SODIUM-COOLED FAST REACTORS Lee, Je-Whan; Jeong, Yong-Hoon; Chang, Yoon-Il; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.43, no.4, pp.383 - 390, 2011-08 |
| LOCA Uncertainty Analysis Using the Fourier Amplitude Sensitivity Test and the Stepwise Regression Technique Kim, Tae Woon; Lee, Byung Ho; Chang, Soon-Heung, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.53, pp.344 - 346, 1986 |
| Measurement of critical heat flux for narrow annuli submerged in saturated water Kim, SH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.41 - 48, 2000-06 |
Measurement of local two-phase flow parameters of nanofluids using conductivity double-sensor probe Park, Yu-Sun; Chang, Soon-Heung, NANOSCALE RESEARCH LETTERS, v.6, 2011-04 |
| Measuring the social value of nuclear energy using contingent valuation methodology Jun, Eunju; Kim, Wonjoon; Jeong, Yong Hoon; Chang, Soon-Heung, ENERGY POLICY, v.38, pp.1470 - 1476, 2010-03 |
| Model development for the estimation of fission product release under normal and accident conditions in a HTGR Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.239, no.6, pp.1066 - 1075, 2009-06 |
| Multi dimensional analysis of Design Basis Events using MARS-LMR Woo, Seung Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.244, pp.83 - 91, 2012-03 |
| NEURAL NETWORK MODEL FOR ESTIMATING DEPARTURE FROM NUCLEATE BOILING PERFORMANCE OF A PRESSURIZED WATER-REACTOR CORE KIM, HK; LEE, SH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.101, no.2, pp.111 - 122, 1993-02 |
| Non-heating simulation of pool-boiling critical heat flux Jeong, Yong Hoon; Baek, WP; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.45, no.19, pp.3987 - 3996, 2002-09 |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - part 1 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.1, pp.1 - 1, 2005-10 |
| Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - Part 2 - Foreword Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.2, pp.143 - 143, 2005-11 |
| OPTIMAL FUEL LOADING PATTERN DESIGN USING AN ARTIFICIAL NEURAL-NETWORK AND A FUZZY RULE-BASED SYSTEM KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.115, no.2, pp.152 - 163, 1993-10 |
| OPTIMAL TEST INTERVAL MODELING OF THE NUCLEAR SAFETY SYSTEM USING THE INHERENT UNAVAILABILITY AND HUMAN ERROR LEE, JH; Chang, Soon-Heung; YOON, WH; HONG, SY, NUCLEAR ENGINEERING AND DESIGN, v.122, no.1-3, pp.339 - 348, 1990-09 |
| Parametric trends analysis of the critical heat flux based on artificial neural networks Moon, SK; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.163, no.1-2, pp.29 - 49, 1996-06 |
| Performance test of the quenching meshes for hydrogen control Hong, Seong Wan; Shin, YS; Song, JH; Chang, Soon-Heung, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.40, no.10, pp.814 - 819, 2003-10 |
| PHYSICAL MODELING AND FINITE-ELEMENT METHOD FOR THE ANALYSIS OF LATERAL PHASE DISTRIBUTION PHENOMENA LEE, GJ; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.18, no.3, pp.333 - 342, 1991 |
| Pool-boiling critical heat flux of water on small plates: Effects of surface orientation and size Yang, SH; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.8, pp.1093 - 1102, 1997-12 |
| POWER PREDICTION IN NUCLEAR-POWER-PLANTS USING A BACK-PROPAGATION LEARNING NEURAL NETWORK ROH, MS; CHEON, SW; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.94, no.2, pp.270 - 278, 1991-05 |
| Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels Choi, Gil Sik; Chang, Soon-Heung; Jeong, Yong Hoon, Transactions of the Korean Society of Mechanical Engineers, B, v.39, no.12, pp.953 - 963, 2015-12 |
| Prediction of the human response time with the similarity and quantity of information Lee, S; Heo, G; Chang, Soon-Heung, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.6, pp.728 - 734, 2006-06 |
| PRESSURIZED WATER-REACTOR CORE PARAMETER PREDICTION USING AN ARTIFICIAL NEURAL NETWORK KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.113, no.1, pp.70 - 76, 1993-01 |
| PROBABILISTIC RISK ASSESSMENT OF NUCLEAR WASTE REPOSITORY WITH THE MECHANISTICALLY MODELED FAILURE RATE CHO, WJ; Chang, Soon-Heung, RADIOACTIVE WASTE MANAGEMENT AND ENVIRONMENTAL RESTORATION, v.15, no.4, pp.203 - 220, 1991 |
| QUANTITATIVE EVENT TREE APPROACH INVOLVING THE DEBRIS BED COOLABILITY KIM, SH; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.13, no.2, pp.105 - 119, 1985 |
| Radial basis function networks applied to DNBR calculation in digital core protection systems Lee, GC; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.30, no.15, pp.1561 - 1572, 2003-10 |
| Risk analysis of radioactive waste repository based on the time dependent hazard rate Chang, Soon-Heung; Cho, WonJin, RADIOACTIVE WASTE MANAGEMENT AND THE NUCLEAR FUEL CYCLE, v.5, no.1, pp.63 - 80, 1984-06 |
| Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident Kim, Sang Ho; Futami, Tsuneo; Chang, Soon-Heung; Jeong, Yong Hoon, SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, v.520756, 2015-02 |
| Simplified Probabilistic Risk Assemssment of Low Level Radioactive Waste Disposal System Kim, Poong-Oh; Cho, Won Jin; Chang, Soon-Heung, RADIOACTIVE WASTE MANAGEMENT AND THE NUCLEAR FUEL CYCLE, v.9, no.4, pp.365 - 380, 1988 |
| Simulant melt experiments on in-vessel retention through external reactor vessel cooling Kang, Kyoung-Ho; Park, Rae-Joon; Kim, Sang-Baik; Kim, Hee-Dong; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.155, no.3, pp.324 - 339, 2006-09 |
| Simulation of the market penetration of hydrogen fuel cell vehicles in Korea Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.32, no.4, pp.318 - 327, 2008-03 |
| STRATEGY AND TOOL DEVELOPMENT FOR NUCLEAR-POWER-PLANT DESIGN SYNTHESIS WITH MEASUREMENT OF RELIABILITY AND SIMPLICITY MIN, BK; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.40, no.1, pp.69 - 76, 1993 |
| STUDY ON THE DATA TREATMENT USING THE KALMAN FILTER TECHNIQUE AND THE BAYESIAN-APPROACH PARK, JY; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.14, no.1, pp.19 - 36, 1986 |
| Subcooled flow boiling CHF enhancement with porous surface coatings Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.50, no.17-18, pp.3649 - 3657, 2007-08 |
| Swirl flow analysis in a helical wire inserted tube using CFD code Park, Yu-Sun; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, pp.3405 - 3412, 2010-10 |
| SYSTEM-COMPLEXITY MEASURE IN THE ASPECT OF OPERATIONAL DIFFICULTY MIN, BK; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.38, no.5, pp.1035 - 1039, 1991-10 |
| SYSTEMATIC BAYES PRIOR-ASSIGNMENT BY COUPLING THE MINI-MAX ENTROPY AND MOMENT-MATCHING METHODS YOON, WH; Chang, Soon-Heung, IEEE TRANSACTIONS ON RELIABILITY, v.43, no.2, pp.279 - 287, 1994-06 |
| Team crystallization (SIO2): Dynamic model of team effectiveness evaluation under the dynamic and tactical environment at nuclear installation Kim, Sok Chul; Chang, Soon-Heung; Heo, Gyunyoung, SAFETY SCIENCE, v.44, no.8, pp.701 - 721, 2006-10 |
| The analysis of security cost for different energy sources Jun, Eunju; Kim, Wonjoon; Chang, Soon-Heung, APPLIED ENERGY, v.86, pp.1894 - 1901, 2009-10 |
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Type
- 2,776 Article
Open Access
- 152 OA Article
Date issued
- 465 2020 - 2024
- 1,120 2010 - 2019
- 712 2000 - 2009
- 369 1990 - 1999
- 110 1980 - 1989