Browse "NE-Journal Papers(저널논문)" by Author Chang, Soon-Heung
Showing results 123 to 176 of 176
| 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 |
| The applicability of a quenching mesh as a hydrogen flame arrester in nuclear power plants Hong, SW; Song, JH; Kim, HD; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.153, no.1, pp.89 - 99, 2006-01 |
| The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids Lee, Kwi Lim; Bang, In Cheol; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.1-2, pp.91 - 103, 2008-01 |
| The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; Chang, Soon-Heung; Jeong, Yong Hoon; Jeong, Jae Jun, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.69, pp.86 - 98, 2015-12 |
| The effect of vibration on critical heat flux in a vertical round tube Lee, YH; Chang, Soon-Heung, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.40, no.10, pp.734 - 743, 2003-10 |
| The implications of Fukushima The South Korean perspective Chang, Soon-Heung, BULLETIN OF THE ATOMIC SCIENTISTS, v.67, no.4, pp.18 - 22, 2011-07 |
| THE MANIPULATION OF TIME-VARYING DYNAMIC VARIABLES USING THE RULE MODIFICATION METHOD AND PERFORMANCE-INDEX IN NPP ACCIDENT DIAGNOSTIC EXPERT SYSTEMS CHOI, KY; YANG, JO; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.35, no.5, pp.1121 - 1125, 1988-10 |
| THE MONTE-CARLO METHOD WITHOUT SORTING FOR UNCERTAINTY PROPAGATION ANALYSIS IN PRA Chang, Soon-Heung; PARK, JY; KIM, MK, RELIABILITY ENGINEERING SYSTEM SAFETY, v.10, no.4, pp.233 - 243, 1985 |
| The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure Kang, Dong Gu; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.275, pp.142 - 153, 2014-08 |
| THE TRINOMIAL FAILURE RATE MODEL FOR TREATING COMMON-MODE FAILURES HAN, SG; YOON, WH; Chang, Soon-Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.25, no.2, pp.131 - 146, 1989 |
| THEORETICAL INVESTIGATION OF VAPOR BLANKET VELOCITY BASED ON MASS, ENERGY, AND MOMENTUM BALANCE TO PREDICT CHF AT LOW QUALITY FLOW LEE, YB; BAEK, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.19, no.5, pp.619 - 628, 1992 |
| Thermal power estimation by fouling phenomena compensation using wavelet and principal component analysis Heo, G; Choi, SS; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.31 - 40, 2000-06 |
| THERMAL POWER PREDICTION OF NUCLEAR-POWER-PLANT USING NEURAL NETWORK AND PARITY SPACE MODEL ROH, MS; CHEON, SW; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.38, no.2, pp.866 - 872, 1991-04 |
| TIME-DEPENDENT REMOVAL EFFICIENCY OF A CHARCOAL BED FOR METHYLIODIDE Chang, Soon-Heung; CHO, WJ, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.46, pp.500 - 501, 1984 |
| TRANSIENT-EFFECTS MODELING OF CRITICAL HEAT-FLUX Chang, Soon-Heung; LEE, KW; GROENEVELD, DC, NUCLEAR ENGINEERING AND DESIGN, v.113, no.1, pp.51 - 57, 1989-04 |
| Uncertainty analysis of safety assessment for high-level radioactive waste repository Cho, W.-J.; Chang, Soon-Heung; Park, H.-H., WASTE MANAGEMENT, v.12, no.1, pp.45 - 54, 1992 |
| Uncertainty and Sensitivity Analyses in Evaluating Risk of High Level Waste Repository Kim, T.W.; Chang, Soon-Heung; Lee, B.H., RADIOACTIVE WASTE MANAGEMENT AND THE NUCLEAR FUEL CYCLE, v.10, no.4, pp.321 - 356, 1988 |
| Visualization of a principle mechanism of critical heat flux in pool boiling Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12 |
| Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall Bang, IC; Chang, Soon-Heung; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363, 2004-09 |
| Wettability of heated surfaces under pool boiling using surfactant solutions and nano-fluids Jeong, Yong Hoon; Chang, Won Joon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.11-12, pp.3025 - 3031, 2008-06 |
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Open Access
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Date issued
- 465 2020 - 2024
- 1,120 2010 - 2019
- 712 2000 - 2009
- 369 1990 - 1999
- 110 1980 - 1989