1. Assessment of a tube-based bundle CHF prediction method using a subchannel code;Chun;Ann. Nucl. Energy,1998
2. 1986 AECL-UO critical heat flux lookup table;Groeneveld;Heat Transfer Eng.,1986
3. Groeneveld, D.C., Joober, K., Doerffer, S., Wong, W., Leung, L.K.H., Cheng, S.C., 1992. The effect of fuel subchannel geometry on CHF, NURETH-5.
4. The 1995 look-up table for critical heat flux in tubes;Groeneveld;Nucl. Eng. Des.,1996
5. Evaluation of the thermal margin in a KOFA-loaded core by a multichannel analysis methodology;Hwang;J. KNS,1995