| Progress on ruthenium release and transport under air ingress conditions A Auvinen, G Brillant, N Davidovich, R Dickson, G Ducros, Y Dutheillet, ... Nuclear engineering and design 238 (12), 3418-3428, 2008 | 48 | 2008 |
| International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor A Hainoun, A Doval, P Umbehaun, S Chatzidakis, N Ghazi, S Park, ... Nuclear Engineering and Design 280, 233-250, 2014 | 42 | 2014 |
| 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 | 26 | 2009 |
| 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 |
| Fuel behavior comparison for a research reactor G Negut, M Mladin, I Prisecaru, N Danila Journal of nuclear materials 352 (1-3), 157-164, 2006 | 13 | 2006 |
| 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 | 8 | 2009 |
| The prompt gamma neutron activation analysis facility at ICN—Pitesti D Bărbos, C Păunoiu, M Mladin, C Cosma AIP Conference Proceedings 1036 (1), 180-185, 2008 | 7 | 2008 |
| Calculation of radioactive species transport in a TRIGA reactor D Mladin, M Mladin, A Toma, C Dulama, I Prisecaru, S Covaci Nuclear Engineering and Design 262, 29-38, 2013 | 6 | 2013 |
| 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 |
| Evaluation of UV optical fibers behavior under neutron irradiation D Sporea, A Sporea, M Ancuta, D Barbos, M Mihalache, M Mladin Advances in Materials Physics and Chemistry 2 (4B), 115-118, 2012 | 5 | 2012 |
| Scdap/relap5 analysis of progression of severe accident in candu 6 plant D Dupleac, M Mladin, I Prisecaru International Conference on Nuclear Engineering 43536, 47-57, 2009 | 5 | 2009 |
| Multiple aspects of raw data collection and processing for Romanian TRIGA SSR D Mladin, M Mladin, M Preda, I Prisecaru Nuclear engineering and design 240 (6), 1630-1643, 2010 | 4 | 2010 |
| Effect of Candu Fuel Bundle Modeling on Sever Accident Analysis D Dupleac, I Prisecaru, M Mladin | 4 | 2009 |
| Investigation on header manifold model effect at CANDU6 large loss of cooling accident D Dupleac, I Prisecaru, M Mladin, G Negut, P Ghitescu International Conference on Nuclear Engineering 48175, 673-679, 2008 | 4 | 2008 |
| Neutronic calculations regarding the new LEU 6 x 6 fuel bundle for 14 MW TRIGA-SSR, in order to increase the reactor power up to 21 MW C Iorgulis, M Ciocanescu, M Preda, M Mladin | 4 | 1998 |
| Verification of Modified SCDAP/RELAP5 Against CANDU Fuel Deformation Experimental Results M Mladin, D Dupleac, I Prisecaru International Conference on Nuclear Engineering 43529, 379-385, 2009 | 3 | 2009 |
| Sensitivity Studies on uncertainty parameters and code modeling of calandria vessel integrity during late phase CANDU 6 severe accident D Dupleac, M Mladim, I Prisecaru | 2 | 2011 |
