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

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Showing results 1 to 18 of 18

1	A passive decay heat removal strategy of the integrated passive safety system (IPSS) for SBO combined with LOCA Kim, Sang Ho; Chang, Soon Heung; Choi, Yu Jung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.295, pp.346 - 359, 2015-12
2	A Stream Line Method to Remove Cross Numerical Diffusion and Its Application to The Solution of Navier - Stokes Equations Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.1, pp.21 - 28, 1984
3	A study on prediction methods of the critical heat flux for upward flow in a vertical narrow rectangular channel Choi, Gil Sik; Jeong, Yong Hoon; Chang, Soon Heung, NUCLEAR ENGINEERING AND DESIGN, v.294, pp.103 - 116, 2015-12
4	An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs Park, Jae Hong; Jeong, Yong Hoon; Baek, Won Pil; Chang, Soon Heung, ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250, 2001-08
5	Buoyancy Effects on Turbulent Mixing in the LMFBR Outlet Plenum Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.15, no.1, pp.50 - 56, 1983
6	Coolant Options and Critical Heat Flux Issues in Fusion Reactor Divertor Design Baek, Won-Pil; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.29, no.4, pp.348 - 359, 1997-08
7	Correction factor development for the 2006 Groeneveld CHF look-up table for rectangular channels under low pressure Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, pp.110869, 2020-12
8	Development of an Expert System (ESRCP) for Failure Diagnosis of Reactor Coolant Pumps Cheon, Se-Woo; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.22, no.2, pp.128 - 138, 1990
9	DEVELOPMENT OF SEVERE ACCIDENT MANAGEMENT SUPPORTING SYSTEMS USING QUANTIFIED CONTAINMENT EVENT TREES Chang, HS; Kang, KS; Chang, Soon Heung, RELIABILITY ENGINEERING SYSTEM SAFETY, v.48, no.3, pp.205 - 216, 1995
10	Feedwater Flowrate Estimation Based on the Two-step De-noising Using the Wavelet Analysis and an Autoassociative Neural Network Heo, Gyunyoung; Choi, Seong S; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.31, no.2, pp.192 - 201, 1999-04
11	Flow boiling CHF experiment with sudden expansion tubes Kim, Yong Jin; Song, Sub Lee; Moon, Sang-Ki; Chang, Soon Heung; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.114, 2020-05
12	Flow instability during subcooled boiling for a downward flow at low pressure in a vertical narrow rectangular channel Lee, Juhyung; Chae, Heetaek; Chang, Soon Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.67, pp.1170 - 1180, 2013-12
13	INNOVATIVE CONCEPT FOR AN ULTRA-SMALL NUCLEAR THERMAL ROCKET UTILIZING A NEW MODERATED REACTOR Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.6, pp.678 - 699, 2015-10
14	Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.109, pp.498 - 506, 2017-11
15	Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels Choi, Gil Sik; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.303, pp.1 - 16, 2016-07
16	Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; Chang, Soon Heung; Jeong, Yong Hoon, PROGRESS IN NUCLEAR ENERGY, v.91, pp.183 - 207, 2016-08
17	Proposed Concept of a Tube-Type Passive Water-Cooled Reactor Without Emergency Core Cooling System Chang, Soon Heung; Baek, Won-Pil; Lee, Goung-Jin; Lee, Jae-Young, NUCLEAR ENGINEERING AND TECHNOLOGY , v.26, no.2, pp.161 - 167, 1994
18	Risk Model Development for PWR During Shutdown Yoon, Won-Hyo; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.21, no.1, pp.1 - 11, 1989-03

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