| Generic CANDU 6 plant severe accident analysis employing SCAPSIM/RELAP5 code D Dupleac, M Mladin, I Prisecaru Nuclear engineering and design 239 (10), 2093-2103, 2009 | 27 | 2009 |
| Numerical analysis of debris melting phenomena during late phase CANDU 6 severe accident S Nicolici, D Dupleac, I Prisecaru Nuclear engineering and design 254, 272-279, 2013 | 21 | 2013 |
| Potential improvement of CANDU NPP safety margins by shortening the response time of shutdown systems using FPGA based implementation J She, J Jiang Nuclear engineering and design 244, 43-51, 2012 | 17 | 2012 |
| SCDAP/RELAP5 application to CANDU6 fuel channel analysis under postulated LLOCA/LOECC conditions M Mladin, D Dupleac, I Prisecaru Nuclear Engineering and Design 239 (2), 353-364, 2009 | 16 | 2009 |
| Adapting and applying SCDAP/RELAP5 to CANDU in-vessel retention studies M Mladin, D Dupleac, I Prisecaru, D Mladin Annals of Nuclear Energy 37 (6), 845-852, 2010 | 15 | 2010 |
| A parametric study of a large break in reactor inlet header of CANDU6 reactors using RELAP5 code I Prisecaru, D Dupleac, P Ghitescu, L Biro Proceedings of ICAPP 6, 4-8, 2006 | 12 | 2006 |
| A study of RELAP5 capability to perform the analysis of CANDU 6 reactors accidents I Prisecaru, D Dupleac, L Biro | 12 | 2005 |
| Thermalhydraulic analysis of CANDU 6 100% reactor outlet header break using RELAP5 code D Dupleac, I Prisecaru, P Ghitescu, G Negut | 11 | 2007 |
| Analysis of late phase severe accident phenomena in CANDU plant D Dupleac Journal of Nuclear Engineering and Radiation Science 3 (2), 020904, 2017 | 10 | 2017 |
| Modifications in SCDAP code for early phase degradation in a CANDU fuel channel M Mladin, D Dupleac, I Prisecaru Annals of Nuclear Energy 36 (5), 634-640, 2009 | 10 | 2009 |
| SCDAP/RELAP5 investigation on coolability of severely degraded CANDU 6 Core-Preliminary results D Dupleac, H Prisecaru, M Mladin, G Negut Proceedings of the 2008 International Congress on Advances in Nuclear Power …, 2008 | 10 | 2008 |
| Evaluation of the RELAP5/SCDAP accident analysis code applicability to CANDU nuclear reactors M Mladin, D Dupleac, I Prisecaru UPB Scientific Bulletin 71 (4), 143-156, 2009 | 9 | 2009 |
| Verification by analytical means of the efficiency of some accident management measures for SBO at a CANDU-6 NPP E Dinca, D Dupleac, I Prisecaru International Nuclear Safety Journal 4 (4), 9-22, 2015 | 8 | 2015 |
| RELAP/SCDAPSIM/MOD3. 6–Development of Severe Accident Models for Heavy Water Reactors Including CANDU and ATUCHA-2 A Bonelli, O Mazzantini, D Dupleac, E Dinca, LJ Siefken, CM Allison, ... Proc. ICAPP, 03-06, 2015 | 8 | 2015 |
| Benchmarking severe accident computer codes for heavy water reactor applications T Nitheanandan, X Cao, JH Choi, D Dupleac, DH Kim, HG Lele, ... Journal of Nuclear Engineering and Radiation Science 3 (2), 020903, 2017 | 7 | 2017 |
| Severe accident development modeling and evaluation for CANDU G Negut, A Catana, I Prisecaru, D Dupleac Annals of Nuclear Energy 36 (9), 1424-1430, 2009 | 7 | 2009 |
| Development of the ASYST VER 3. x LWR/HPWR Best Estimate Integral Code D Dupleac, RM Nistor-Vlad, C Allison, J Hohorst, M Perez-Ferragut 2021 10th International Conference on ENERGY and ENVIRONMENT (CIEM), 1-5, 2021 | 6 | 2021 |
| SCDAPSIM/RELAP5 investigation on in-vessel corium retention for CANDU 6 plant D Dupleac, M Mladin, H Prisecaru, G Negut Proceedings of the 2010 International Congress on Advances in Nuclear Power …, 2010 | 6 | 2010 |
| Two-phase flow CFD modeling for evaluation of particulate erosion S Nicolici, I Prisecaru, D Dupleac UPB Sci. Bull., Series D 75 (1), 187-198, 2013 | 5 | 2013 |
| Uncertainty analysis of the 35% reactor inlet header break in a CANDU 6 reactor using RELAP/SCDAPSIM/MOD4. 0 with integrated uncertainty analysis option D Dupleac, M Perez, F Reventos, C Allison | 5 | 2011 |
