4650105F-82F1-4B3C-9E12-6FD10A29996BCOMPUTATIONAL MODELLING FOR ADVANCED NUCLEAR POWER PLANTSResearch GrantEP/I003010/1798CB33D-C79E-4578-83F2-72606407192CEPSRCINCOME_ACTUAL15692314893F447-DA3F-435B-B2E5-52E724E008F6Phenomenological modeling of critical heat flux: The GRAMP code and its validationNuclear Engineering and Design1bc7950b5f359e11948eacef581c1caeAhmad M2013-01-01http://dx.doi.org/10.1016/j.nucengdes.2012.09.004http://dx.doi.org/10.1016/j.nucengdes.2012.09.004Journal Article/Reviewdoi_53d0030030288899