1. Current status of high conversion pressurized water reactor studies;Umeoka;Nucl. Technol.,1988
2. Feasibility design studies on HCPWR's with semi-tight core configuration-II;Iizuka,1988
3. Fluid to fluid modeling of critical heat flux: a compensated distortion model;Ahmad;AECL-3663,1971
4. Parametric study of CHF data: compilation of rod bundle CHF data available at the Columbia University heat transfer research facility;Fighetti;EPRI-NP-2609,1982
5. COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and core;Wheeler;BNWL-1962,1976