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2. Analysis of thermal-hydraulic fluctuations in Trillo NPP with CTF/PARCS v. 2.7 coupled code;Abarca;ASME. ASME J. Nuclear Rad. Sci.,2016
3. Application of best estimate plus uncertainty in review of research reactor safety analysis;Adu,2014
4. CTF – A Thermal-Hydraulic Subchannel Code for LWRs Transient Analyses User’s Manual;Avramova,2015
5. Turbine trip transient analysis in peach bottom NPP with TRAC-BF1 code and Simtab-1D methodology;Barrachina,2010