1 |
Churl Yoon, Bo Wook Rhee, and Byung-Joo Min, '3-D CFD Analysis of the CANDU-6 Moderator Transient for the 35% RIH Break with Loss of ECC Injection,' The 10th International Topiclal Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October (2003)
|
2 |
Churl Yoon, Bo Wook Rhee, and Byung-Joo Min, 'Development and Validation of the 3-D CFD Model for CANDU-6 Moderator Temperature Predictions,' Accepted for the publication in Nuclear Technology, vol. 148, no.3, 259-267 (2004)
|
3 |
K. Aydogdu, K.Y. Kim, and Y.I. Kim, 'Radiation Heating Report,' Wolsong NPP 2/3/4, 86-03320-AR-004, Revision 2 (1994)
|
4 |
N.E. Todreas and M.S. Kazimi, Nuclear System II: Elements of Thermal Hydraulic Design, Chap. 5, Hemisphere Publishing Corporation (1990)
|
5 |
G.!. Hadaller, R.A. Fortman, J. Szymanski, W.I. Midvidy and D.J.' Train, 'Frictional Pressure Drop for Staggered and In Line Tube Bank with Large Pitch to Diameter Ratio,' Preceedings of 17th CNS Conference, Frederiction, New Brunswick, Canada (1996)
|
6 |
R.G. Huget, J.K. Szymanski, and W.I. Midvidy, 'Experimental and Numerical Modelling of Combined Forced and Free Convection in a Complex Geometry with Internal Heat Generation,' Proceedings of 9th International Heat Transfer Conference, Vol. 3, 327 (1990)
|
7 |
W.M. Collins, 'PHOENICS2 Model Report for Wolsong 2/3/4 Moderator Circulation Analysis,' Wolsong NPP 2/3/4, 86-03500-AR-053, Revision 0 (1995)
|
8 |
P. Seodijono, W.M. Collins, and T. De, 'Moderator Analysis for In-Core and Out-of-Core Loss of Coolant Accident (LOCA),' Wolsong NPP 2/3/4, 86-03500-AR-052, Revision 0 (1995)
|
9 |
L.N. Carlucci and 1. Cheung, 'The Effects of Symmetric/Asymmetric Boundary Conditions on the Flow of an Internally Heated Fluid,' Numerical Methods for Partial Differential Equations, 2, 47-61 (1986)
DOI
|
10 |
R.G. Huget, J.K. Szymanski, and W.I. Midvidy, 'Status of Physical and Numerical Modelling of CANDU Moderator Circulation,' Proceedings of 10th Annual Conference of the Canadian Nuclear Society, Ottawa (1989).
|