W. Lee

发表

Preliminary Sensitivity Study on Gas-Cooled Reactor for NHDD System Using MARS-GCR

Seung Wook Lee, J. Jeong, W. Lee, 2005 .

Regulatory Issues on the Safety Distance between a VHTR and a H2 Production Facility and an Overpressure Prediction Using Correlations and a CFD Analysis for the JAEA Explosion Test in an Open Space

S. B. Kim, Min-Hwan Kim, W. Lee, 2009 .

Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor

W. Lee, Yong-Hee Kim, N. Tak, 2008 .

Computational Assessment of the Reactor Vessel Cooling Options in a prismatic core VHTR

Min-Hwan Kim, W. Lee, N. Tak, 2009 .

Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs

W. Lee, L. Snead, K. Terrani, 2013 .

Development of the film-splitting look-up table applicable to mechanistic annular film dryout model in annulus geometry

W. Lee, J. Chun, U. Lee, 2006 .

Turbulent mixed convection heat transfer experiments in a vertical cylinder using analogy concept

W. Lee, B. Chung, Bong-Jin Ko, 2010 .

Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1

Bub Dong Chung, Won-Jae Lee, Kwi-Seok Ha, 1999 .

Development of the critical film thickness correlation for an advanced annular film mechanistic dryout model applicable to MARS code

Ji-Han Chun, Won Jae Lee, W. Lee, 2003 .

Turbulence-induced Heat Transfer in PBMR Core Using LES and RANS

Su-Jong Yoon, Goon-Cherl Park, Won-Jae Lee, 2007 .

Numerical treatment of pebble contact in the flow and heat transfer analysis of a pebble bed reactor core

Kwang-Yong Kim, Won-Jae Lee, Jung-Jae Lee, 2007 .

Safety evaluation of accident-tolerant FCM fueled core with SiC-coated zircalloy cladding for design-basis-accidents and beyond DBAs

Ji-Han Chun, Won Jae Lee, Sung-Won Lim, 2015 .

Numerical investigation of a heat transfer within the prismatic fuel assembly of a very high temperature reactor

Min-Hwan Kim, Won Jae Lee, Nam-il Tak, 2008 .

DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS- COOLED REACTOR SYSTEMS

Jonghwa Chang, Seung Wook Lee, Won-Jae Lee, 2005 .

Safety Analysis of High-Power-Density Annular Fuel for PWRs

M. Kazimi, W. Lee, P. Saha, 2007 .

Simulation of a main steam line break accident using a coupled “system thermal-hydraulics, three-dimensional reactor kinetics, and hot channel analysis” code

Bub Dong Chung, Jae Jun Jeong, Won-Jae Lee, 2006 .