Soon Heung Chang

发表

Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

Seung Hyun Nam, Paolo Venneri, Yong Hoon Jeong, 2015 .

The manipulation of time-varying dynamic variables using the rule modification method and performance-index in NPP accident diagnostic expert systems

Soon Heung Chang, K.-Y. Choi, J.-O. Yang, 1987 .

An experimental study on CHF enhancement in flow boiling using Al2O3 nano-fluid

Yong Hoon Jeong, Soon Heung Chang, Soon-Heung Chang, 2010 .

Critical Heat Flux Experiments on the Reactor Vessel Wall Using 2-D Slice Test Section

Won-Pil Baek, Yong Hoon Jeong, Soon Heung Chang, 2005 .

CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy

Hae Min Park, Soon Heung Chang, Soon-Heung Chang, 2012 .

The Analysis of Security Cost for Different Energy Sources

Wonjoon Kim, Soon Heung Chang, Eunju Jun, 2009 .

Visualization of a principle mechanism of critical heat flux in pool boiling

Won-Pil Baek, In Cheol Bang, Soon Heung Chang, 2005 .

Effects of mechanical vibration on critical heat flux in vertical annulus tube

Soon Heung Chang, Soon-Heung Chang, D. Kim, 2007 .

Optimal heliostat system using hybrid type solar tracking device

Dong Il Lee, Seung Wook Baek, Soon Heung Chang, 2012 .

The Effect of Vibration on Critical Heat Flux in a Vertical Round Tube

Soon Heung Chang, Soon-Heung Chang, Yong Ho Lee, 2003 .

Effects of the spacer and mixing vanes on critical heat flux for low-pressure water at low-velocities

Won-Pil Baek, Soon Heung Chang, Ji Bum Chung, 1996 .

Flow boiling CHF enhancement using Al2O3 nanofluid and an Al2O3 nanoparticle deposited tube

Won Joon Chang, Soon Heung Chang, Soon-Heung Chang, 2011 .

Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes

In Cheol Bang, Soon Heung Chang, Soon-Heung Chang, 2005 .

A study of critical heat flux for low flow of water in vertical round tubes under low pressure

Won-Pil Baek, Soon Heung Chang, Soon-Heung Chang, 1991 .

CHF characteristics of R-134a flowing upward in uniformly heated vertical tube

Soon Heung Chang, Soon-Heung Chang, C. Kim, 2005 .

DEVELOPMENT OF A BUNDLE CORRECTION METHOD AND ITS APPLICATION TO PREDICTING CHF IN ROD BUNDLES

Won-Pil Baek, Dae-Hyun Hwang, Soon Heung Chang, 1993 .

Flow-induced vibration in two-phase flow with wire coil inserts

Soon Heung Chang, Soon-Heung Chang, D. Kim, 2008 .

Fusion Licensing and Safety Studies in Korea

Gyunyoung Heo, In-Ju Hwang, Soon Heung Chang, 2014, IEEE Transactions on Plasma Science.

Critical heat flux under flow oscillation of water at low-pressure, low-flow conditions

Won-Pil Baek, Soon Heung Chang, Soon-Heung Chang, 1999 .

Assessment of passive containment cooling concepts for advanced pressurized water reactors

Won-Pil Baek, Soon Heung Chang, Soon-Heung Chang, 1997 .

Critical Heat Flux for Oscillatory Water Flow in Vertical Round Tubes

Soon Heung Chang, Wp Baek, Soon Heung Chang, 1998 .

Experimental study on the effect of angles and positions of mixing vanes on CHF in a 2 × 2 rod bundle with working fluid R-134a

Soon Heung Chang, Bs Shin, Soon-Heung Chang, 2005 .

NUCLEAR REACTOR THERMAL HYDRAULICS (NURETH-10) SPECIAL ISSUE—PART 2

Sung-Jae Lee, Fan-bill B. Cheung, Soon Heung Chang, 2005 .

A correction method for heated length effect in critical heat flux prediction

Won-Pil Baek, Soon Heung Chang, Soon-Heung Chang, 2000 .

Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Won-Pil Baek, In Cheol Bang, Soon Heung Chang, 2004 .

Application of neural networks to a connectionist expert system for transient identification in nuclear power plants

Soon Heung Chang, Se Woo Cheon, Soon Heung Chang, 1993 .

An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs

Won-Pil Baek, Yong Hoon Jeong, Soon Heung Chang, 2001 .

Experimental study on the effect of angles and positions of mixing vanes on CHF in a 2 × 2 rod bundle with working fluid R-134 a

Soon Heung Chang, Soon-Heung Chang, Byung Soo Shin, 2005 .

Critical heat flux prediction using genetic programming for water flow in vertical round tubes

Won-Pil Baek, Soon Heung Chang, Dong-Gyu Lee, 1997 .

Development of a thermal-hydraulic analysis code for annular fuel assemblies

Soon Heung Chang, Soon-Heung Chang, K. Han, 2003 .

THE TRINOMIAL FAILURE RATE MODEL FOR TREATING COMMON-MODE FAILURES

Soon Heung Chang, Won Hyo Yoon, Sang Gil Han, 1989 .

Measuring the Social Value of Nuclear Energy Using Contingent Valuation Methodology

Wonjoon Kim, Yong Hoon Jeong, Soon Heung Chang, 2010 .

CHF experiment and CFD analysis in a 2 × 3 rod bundle with mixing vane

Soon Heung Chang, Bs Shin, Soon-Heung Chang, 2009 .

The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel

Yong Hoon Jeong, Jae Jun Jeong, Heetaek Chae, 2015 .