| 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 |
| 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 | 4 | 2013 |
| 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 |
| Analysis of potential common cause failure events for Romania-TRIGA 14 MW reactor G Radu, D Mladin, I Prisecaru Nuclear Engineering and Design 265, 164-173, 2013 | 3 | 2013 |
| Aspects of probabilistic safety assessment for TRIGA research reactor D MLADIN, I PRISECARU UPB Sci. Bull., series C 76 (1), 261-270, 2014 | 2 | 2014 |
| Common cause failure data collection and analysis for safety-related components of TRIGA SSR-14MW Pitesti, Romania G Radu, D Mladin | 2 | 2003 |
| Calculation of fission products transport in a pool type reactor using CATHARE2 D MLADIN, M MLADIN, Ş COVACI, I PRISECARU UPB Sci. Bull, Ser. C 75 (1), 2013 | 1 | 2013 |
| MCNP 5 CALCULATIONS COMPARED TO EXPERIMENTAL MEASUREMENTS IN CEA-MINERVE REACTOR M Mladin, D Mladin University" Politehnica" of Bucharest Scientific Bulletin, Series D …, 2012 | 1 | 2012 |
| Simulation of B9401 Test in the RD-14M Experimental Facility With CATHARE2 M Mladin, D Mladin International Conference on Nuclear Engineering 49323, 333-342, 2010 | 1 | 2010 |
| Operational safety experience at 14 MW TRIGA research reactor from INR Pitesti, Romania M Ciocanescu, D Mladin International Conference on Research Reactors: Safe Management and Effective …, 2007 | 1 | 2007 |
| PSA support safety analysis using RELAP5 for the reactivity insertion event in 14 MW TRIGA reactor M Mladin, D Mladin, I Prisecaru, N Danila, D Dupleac Scientific Bulletin-P olitehnicaUniversity of Bucharest. Series C …, 2007 | 1 | 2007 |
| Benchmark Consolidated Results against Experimental Data from SPERT III. Annex VI AP Olson, M Mladin, D Mladin, S Dulugeac, G Budriman | | 2019 |
| Romania’s Benchmark Results against Experimental Data from SPERT III and IEA-R1 M Mladin, D Mladin, S Dulugeac, G Budriman | | 2019 |
| Comparing failure rates in different research reactors including Romanian TRIGA SSR Reactor D Mladin, M Mladin, I Prisecaru | | 2010 |
| Calculations of steady-state and reactivity insertion transients in a research reactor simulating the PWR M Mladin, D Mladin, I Prodea | | 2010 |
| Comparing case studies results and capabilities of Psaman Package versus Riskspectrum PSA professional code D Mladin, G Radu, M Mladin, I Prisecaru | | 2010 |
| Overview of probabilistic safety assessment activity for Romanian TRIGA SSR 14 MW reactor D Mladin, M Mladin, G Radu, C Constantinescu, M Preda, D Cristea, ... | | 2008 |
| Probabilistic safety assessment for TRIGA SSR 14 MW D Mladin, M Preda, M Mladin, I Stefan | | 2006 |
| Analysis of area events as part of probabilistic safety assessment for Romanian TRIGA SSR 14 MW reactor D Mladin, I Stefan | | 2005 |
| Reliability Data Collection and Processing for Romanian TRIGA-SSR 14 MW Reactor for PSA use D Mladin, M Mladin, D Cristea Probabilistic Safety Assessment and Management: PSAM 7—ESREL’04 June 14–18 …, 2004 | | 2004 |
