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Browse "NE-Journal Papers(저널논문)" by Author Chang, Soon-Heung

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Showing results 1 to 60 of 176

1	A combined deterministic and probabilistic procedure for safety assessment of beyond design basis accidents in nuclear power plant: Application to ECCS performance assessment for design basis LOCA redefinition Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.260, pp.165 - 174, 2013-07
2	A correction method for heated length effect in critical heat flux prediction Lee, YH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.1 - 11, 2000-06
3	A CRITICAL HEAT-FLUX MODEL BASED ON MASS, ENERGY, AND MOMENTUM BALANCE FOR UPFLOW BOILING AT LOW QUALITIES Chang, Soon-Heung; LEE, KW, NUCLEAR ENGINEERING AND DESIGN, v.113, no.1, pp.35 - 50, 1989-04
4	A DIAGNOSTIC EXPERT SYSTEM FOR THE NUCLEAR-POWER-PLANT BASED ON THE HYBRID KNOWLEDGE APPROACH YANG, JO; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.36, no.6, pp.2450 - 2458, 1989-12
5	A DYNAMIC RELIABILITY MODEL FOR NUCLEAR-FUEL ELEMENT CHOI, KY; Chang, Soon-Heung; YOON, YK, RELIABILITY ENGINEERING SYSTEM SAFETY, v.31, no.1, pp.111 - 116, 1991
6	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
7	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
8	A NEW CRITICAL HEAT-FLUX MODEL FOR LIQUID-METALS UNDER LOW HEAT-FLUX LOW-FLOW CONDITIONS Chang, Soon-Heung; LEE, YB, NUCLEAR ENGINEERING AND DESIGN, v.148, no.2-3, pp.487 - 498, 1994-07
9	A photographic study on the near-wall bubble behavior in subcooled flow boiling Chang, Soon-Heung; Bang, IC; Baek, WP, INTERNATIONAL JOURNAL OF THERMAL SCIENCES, v.41, no.7, pp.609 - 618, 2002-07
10	A PROBABILISTIC SAFETY CRITERION FOR CORE MELT FREQUENCY BASED ON THE DISTRIBUTION OF THE PUBLICS SAFETY GOALS RA, KY; Lee, Byong-Whi; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.101, no.2, pp.149 - 158, 1993-02
11	A procedure to predict subcooled-water-flow-boiling CHF in uniformly heated tubes for high-heat-flux applications Kwon, YM; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.130, no.3, pp.310 - 328, 2000-06
12	A STATISTICAL-MODEL FOR PREDICTION OF FUEL-ELEMENT FAILURE USING THE MARKOV PROCESS AND ENTROPY MINIMAX PRINCIPLES CHOI, KY; Yoon, Young-Ku; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.93, no.2, pp.195 - 205, 1991-02
13	A STUDY OF CRITICAL HEAT-FLUX FOR LOW FLOW OF WATER IN VERTICAL ROUND TUBES UNDER LOW-PRESSURE Chang, Soon-Heung; Baek, WP; Bae, TM, NUCLEAR ENGINEERING AND DESIGN, v.132, no.2, pp.225 - 237, 1991-12
14	A Study on the Method of Combining Empirical Data and Deterministic Model for Fuel Failure Prediction Cho, Byeong-Ho; Yoon, Young-Ku; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.19, no.4, pp.233 - 241, 1987-12
15	ADAPTIVE KALMAN GAIN APPROACH TO ONLINE INSTRUMENT FAILURE-DETECTION WITH IMPROVED GLR METHOD AND SUBOPTIMAL CONTROL ON LOFT PRESSURIZER CHUNG, HY; KIM, TW; Chang, Soon-Heung; LEE, BH, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.33, no.4, pp.1103 - 1114, 1986-08
16	Advisory system for the diagnosis of lost electric output in nuclear power plants Heo, G; Chang, Soon-Heung; Choi, SS; Choi, GH; Jee, MH, EXPERT SYSTEMS WITH APPLICATIONS, v.29, no.4, pp.747 - 756, 2005-11
17	Algebraic approach for the diagnosis of turbine cycles in nuclear power plants Heo, G; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.235, no.14, pp.1457 - 1467, 2005-06
18	AN ALARM PROCESSING SYSTEM FOR A NUCLEAR-POWER-PLANT USING ARTIFICIAL-INTELLIGENCE TECHNIQUES YANG, JO; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.95, no.3, pp.266 - 271, 1991-09
19	An assessment of the effectiveness of fuel cycle technologies for the national energy security enhancement in the electricity sector Kim, Hyun Jun; Jun, Eunju; Chang, Soon-Heung; Kim, Wonjoon, ANNALS OF NUCLEAR ENERGY, v.36, no.5, pp.604 - 611, 2009-05
20	An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube Lee, YH; Kim, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.229, no.1, pp.47 - 58, 2004-04
21	An Experimental Study of the Pool-Boiling CHF on Downward-Facing Plates Yang, Soo-Hyung; Baek, Won-Pil; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.26, no.4, pp.493 - 501, 1994-04
22	An experimental study on CHF enhancement in flow boiling using Al2O3 nano-fluid Kim, Tae-Il; Jeong, Yong-Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.53, no.5-6, pp.1015 - 1022, 2010-02
23	An experimental study on CHF enhancement of wire nets covered surface in R-134a flow boiling under high pressure and high mass flux conditions Song, Sub Lee; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.90, pp.761 - 768, 2015-11
24	An experimental study on CHF in pool boiling system with SA508 test heater under atmospheric pressure Lee, Juno; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.250, pp.720 - 724, 2012-09
25	An Improved Mechanistic Model to Predict Critical Heat Flux in Subcooled and Low Quality Convective Boiling Kwon, Young Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.31, no.2, pp.236 - 255, 1999-04
26	An improved physical model for flooding limited CHF under zero and very low flow conditions Park, C; Hwang, DH; Chang, Soon-Heung; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.25, no.3, pp.339 - 348, 1998-04
27	An independent assessment of Groeneveld et al.s 1995 CHF look-up table Baek, WP; Kim, HC; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.178, no.3, pp.331 - 337, 1997-12
28	An integral equation model for critical heat flux at subcooled and low quality flow boiling Chun, TH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.13 - 29, 2000-06
29	AN ONLINE PRESSURIZER SURVEILLANCE SYSTEM-DESIGN TO PREVENT SMALL-BREAK LOSS-OF-COOLANT ACCIDENTS THROUGH POWER-OPERATED RELIEF VALVES USING A MICROCOMPUTER LEE, JH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.76, no.1, pp.27 - 40, 1987-01
30	Analysis of economics and safety to cope with station blackout in PWR Al Shehhi, Ahmed Saeed; Chang, Soon-Heung; Kim, Sang Ho; Kang, Hyun Gook, ANNALS OF NUCLEAR ENERGY, v.59, pp.63 - 71, 2013-09
31	ANALYTICAL AND NUMERICAL UNAVAILABILITY ANALYSIS OF REDUNDANT-SYSTEMS WITH DEPENDENT HUMAN ERROR Chang, Soon-Heung; KIM, MK; PARK, JY, RELIABILITY ENGINEERING SYSTEM SAFETY, v.10, no.1, pp.49 - 63, 1985
32	APPLICATION OF NEURAL NETWORKS TO A CONNECTIONIST EXPERT SYSTEM FOR TRANSIENT IDENTIFICATION IN NUCLEAR-POWER-PLANTS CHEON, SW; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.102, no.2, pp.177 - 191, 1993-05
33	APPLICATION OF NEURAL NETWORKS TO MULTIPLE ALARM PROCESSING AND DIAGNOSIS IN NUCLEAR-POWER-PLANTS CHEON, SW; Chang, Soon-Heung; CHUNG, HY; Bien, Zeung nam, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.1, pp.11 - 20, 1993-02
34	APPLICATION OF NEURAL NETWORKS TO SIGNAL PREDICTION IN NUCLEAR-POWER-PLANT KIM, WJ; Chang, Soon-Heung; LEE, BH, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.40, no.5, pp.1337 - 1341, 1993-10
35	Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02
36	Assessment of a tube-based bundle CHF prediction method using a subchannel code Chun, TH; Hwang, DH; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.25, no.14, pp.1159 - 1168, 1998-09
37	Assessment of CHF correlations for internally heated concentric annulus channels Park, JW; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.8, pp.1077 - 1086, 1996-12
38	Assessment of passive containment cooling concepts for advanced pressurized water reactors Lee, SW; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.24, no.6, pp.467 - 475, 1997-04
39	Automating strategies of emergency operation for optimal shutdown in pressurized water reactors Choi, SS; Chang, Soon-Heung; Lee, DH, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.45, no.1, pp.17 - 29, 1998-02
40	Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a pool Bang, IC; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.12, pp.2407 - 2419, 2005-06
41	CHF characteristics of R-134a flowing upward in uniformly heated vertical tube Kim, CH; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.11, pp.2242 - 2249, 2005-05
42	CHF detection using spationtemporal neural network and wavelet transform Kim, SH; Bang, IC; Baek, WP; Chang, Soon-Heung; Moon, SK, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.27, no.2, pp.285 - 292, 2000-02
43	CHF enhancement in flow boiling system with TSP and boric acid solutions under atmospheric pressure Lee, Juno; Jeong, Yong-Hoon; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3594 - 3600, 2010-10
44	CHF enhancement of SiC nanofluid in pool boiling experiment Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.52, pp.12 - 18, 2014-01
45	CHF experiment and CFD analysis in a 2 x 3 rod bundle with mixing vane Shin, Byung Soo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.239, no.5, pp.899 - 912, 2009-05
46	CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy Kim, Tae-Il; Park, Hae-Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.243, pp.272 - 278, 2012-02
47	CLASSIFICATION AND PREDICTION OF THE CRITICAL HEAT-FLUX USING FUZZY THEORY AND ARTIFICIAL NEURAL NETWORKS MOON, SK; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.150, no.1, pp.151 - 161, 1994-09
48	CLASSIFICATION OF CRITICAL HEAT-FLUX PATTERNS USING ENTROPY MINIMAX PRINCIPLE Chang, Soon-Heung; BAEK, WP; PARK, JW, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.18, no.2, pp.185 - 193, 1991
49	COBRA RELAP5 - A MERGED VERSION OF THE COBRA-TF AND RELAP5 MOD3 CODES LEE, SY; JEONG, JJ; KIM, SH; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.99, no.2, pp.177 - 187, 1992-08
50	Cognitive simulation of operators diagnostic strategies in nuclear power plants Cheon S.W.; Lee J.W.; Sim B.S.; Park J.K.; Chang, Soon-Heung, INFORMATICA (LJUBLJANA), v.21, no.2, pp.201 - 207, 1997-06
51	Comparative cost analysis of direct disposal versus pyro-processing with DUPIC in Korea Lee, Je-Whan; Lee, Jeong-Ik; Chang, Won-Joon; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.37, no.12, pp.1699 - 1704, 2010-12
52	Comparative study on state analysis of BOP in NPPs Heo, G; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.50, no.4, pp.1271 - 1281, 2003-08
53	COMPARATIVE-STUDY ON UNCERTAINTY AND SENSITIVITY ANALYSIS AND APPLICATION TO LOCA MODEL KIM, TW; Chang, Soon-Heung; LEE, BH, RELIABILITY ENGINEERING SYSTEM SAFETY, v.21, no.1, pp.1 - 26, 1988
54	Cost benefit analysis of advanced nuclear fuel cycle using Linear Programming optimization Lee, Je-Whan; Chang, Yoon-Il; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.46, pp.116 - 120, 2012-08
55	Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow Park, C; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.4, pp.453 - 464, 1997
56	Critical heat flux and flow pattern for water flow in annular geometry Park, JW; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.172, no.1-2, pp.137 - 155, 1997
57	Critical heat flux and onset of nucleate boiling tests in a finned rod bundle Chae, HT; Park, JH; Kim, H; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12
58	CRITICAL HEAT FLUX ENHANCEMENT Chang, Soon-Heung; Jeong, Yong Hoon; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11
59	Critical heat flux experiments on the reactor vessel wall using 2-D slice test section Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11
60	Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions Park, C; Chang, Soon-Heung; Baek, WP, NUCLEAR ENGINEERING AND DESIGN, v.183, no.3, pp.235 - 247, 1998-07

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