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Articles in Scholarly Journals [Incomplete List]
Comparison of the CHF data for water and refrigerant HFC-134a by using the fluid-to-fluid modeling methods
International Journal of Heat and Mass Transfer, vol. 50, no. 21-22, pp. 4446–4456, 2007
Modeling capability of R134a for a critical heat flux of water in a vertical 5×5 rod bundle geometry
International Journal of Heat and Mass Transfer, vol. 49, no. 7-8, pp. 1299–1309, 2006
Effect of the Axial Heat Flux on the Critical Heat Flux in Low Flow Conditions with Vertical Annuli
Journal of Nuclear Science and Technology, vol. 43, no. 11, pp. 1336–1343, 2006
Direct observation of a liquid film under a vapor environment in a pool boiling using a nanofluid
Applied Physics Letters, vol. 86, no. 13, p. 134107, 2005
Visualization of a principle mechanism of critical heat flux in pool boiling
International Journal of Heat and Mass Transfer, vol. 48, no. 25-26, pp. 5371–5385, 2005
Why aren’t inner-city adolescents sticking with the patch?
Journal of Adolescent Health, vol. 36, no. 2, pp. 143–144, 2005
Flooding limited CHF in a vertical 3×3 rod bundle with non-uniform axial heat flux
Nuclear Engineering and Design, vol. 235, no. 1, pp. 77–90, 2005
An experimental study on the critical heat flux for low flow of water in a non-uniformly heated vertical rod bundle over a wide range of pressure conditions
Nuclear Engineering and Design, vol. 235, no. 21, pp. 2295–2309, 2005
Hybrid accident simulation methodology using artificial neural networks for nuclear power plants
Information Sciences, vol. 160, no. 1-4, pp. 207–224, 2004
Effect of multiple holes on the performance of sparger during direct contact condensation of steam
Experimental Thermal and Fluid Science, vol. 28, no. 6, pp. 629–638, 2004
Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall
International Journal of Heat and Mass Transfer, vol. 47, no. 19-20, pp. 4349–4363, 2004
Non-heating simulation of pool-boiling critical heat flux
International Journal of Heat and Mass Transfer, vol. 45, no. 19, pp. 3987–3996, 2002
A photographic study on the near-wall bubble behavior in subcooled flow boiling
International Journal of Thermal Sciences, vol. 41, no. 7, pp. 609–618, 2002
Improved methodology for generation of axial flux shapes in digital core protection systems
Annals of Nuclear Energy, vol. 29, no. 7, pp. 805–819, 2002
An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs
Annals of Nuclear Energy, vol. 28, no. 12, pp. 1237–1250, 2001
Critical heat flux of water in vertical round tubes at low pressure and low flow conditions
Nuclear Engineering and Design, vol. 199, no. 1-2, pp. 49–73, 2000
CHF detection using spationtemporal neural network and wavelet transform
International Communications in Heat and Mass Transfer, vol. 27, no. 2, pp. 285–292, 2000
A correction method for heated length effect in critical heat flux prediction
Nuclear Engineering and Design, vol. 199, no. 1-2, pp. 1–11, 2000
An integral equation model for critical heat flux at subcooled and low quality flow boiling
Nuclear Engineering and Design, vol. 199, no. 1-2, pp. 13–29, 2000
Measurement of critical heat flux for narrow annuli submerged in saturated water
Nuclear Engineering and Design, vol. 199, no. 1-2, pp. 41–48, 2000
Critical heat flux under flow oscillation of water at low-pressure, low-flow conditions
Nuclear Engineering and Design, vol. 193, no. 1-2, pp. 131–143, 1999
Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions
Nuclear Engineering and Design, vol. 183, no. 3, pp. 235–247, 1998
Assessment of a tube-based bundle CHF prediction method using a subchannel code
Annals of Nuclear Energy, vol. 25, no. 14, pp. 1159–1168, 1998
An improved physical model for flooding limited CHF under zero and very low flow conditions
International Communications in Heat and Mass Transfer, vol. 25, no. 3, pp. 339–348, 1998
Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow
International Communications in Heat and Mass Transfer, vol. 24, no. 4, pp. 453–464, 1997
Critical heat flux prediction using genetic programming for water flow in vertical round tubes
International Communications in Heat and Mass Transfer, vol. 24, no. 7, pp. 919–929, 1997
Pool-boiling critical heat flux of water on small plates: Effects of surface orientation and size
International Communications in Heat and Mass Transfer, vol. 24, no. 8, pp. 1093–1102, 1997
Assessment of passive containment cooling concepts for advanced pressurized water reactors
Annals of Nuclear Energy, vol. 24, no. 6, pp. 467–475, 1997
Critical heat flux and flow pattern for water flow in annular geometry
Nuclear Engineering and Design, vol. 172, no. 1-2, pp. 137–155, 1997
An independent assessment of Groeneveld et al.'s 1995 CHF look-up table
Nuclear Engineering and Design, vol. 178, no. 3, pp. 331–337, 1997
Parametric trends analysis of the critical heat flux based on artificial neural networks
Nuclear Engineering and Design, vol. 163, no. 1-2, pp. 29–49, 1996
Effects of the spacer and mixing vanes on critical heat flux for low-pressure water at low-velocities
International Communications in Heat and Mass Transfer, vol. 23, no. 6, pp. 757–765, 1996
Assessment of CHF correlations for internally heated concentric annulus channels
International Communications in Heat and Mass Transfer, vol. 23, no. 8, pp. 1077–1086, 1996
Derivation of mechanistic critical heat flux model for water based on flow instabilities
International Communications in Heat and Mass Transfer, vol. 23, no. 8, pp. 1109–1119, 1996
Theoretical investigation of vapor blanket velocity based on mass, energy, and momentum balance to predict CHF at low quality flow
International Communications in Heat and Mass Transfer, vol. 19, no. 5, pp. 619–628, 1992