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 |
Experimental and numerical study of freezing and flow characteristics of Wood’s Metal injection in a water pool R Secareanu, R Mereu, M Takahashi, F Inzoli, I Prisecaru Applied Thermal Engineering 103, 1261-1277, 2016 | 16 | 2016 |
NSC-PSO, a novel PSO variant without speeds and coefficients G Anescu, I Prisecaru 2015 17th International Symposium on Symbolic and Numeric Algorithms for …, 2015 | 16 | 2015 |
MMOSA–a new approach of the human and organizational factor analysis in PSA M Farcasiu, I Prisecaru Reliability Engineering & System Safety 123, 91-98, 2014 | 16 | 2014 |
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 |
The irradiation effects on zirconium alloys G Negut, M Ancuta, V Radu, S Ionescu, V Stefan, O Uta, I Prisecaru, ... Journal of nuclear materials 362 (2-3), 300-308, 2007 | 13 | 2007 |
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 |
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 | 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 |
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 |
Improvement of the Thermal hydraulic characteristics in the Calandria Vessel of a CANDU 6 Nuclear Reactor R Arsene, I Prisecaru, Ş Nicolici UPB Sci. Bull., Series C 75 (4), 2013 | 9 | 2013 |
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 |
The use of PESTEL analysis in development of the Romanian geological repository.'' V Andrei, I Prisecaru Scientific Bulletin of University Politehnica of Bucharest, Series C 76, 247-254, 2014 | 7 | 2014 |
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 |
BEPU approach in the CANDU 6 severe accident analysis R Mușoiu, RM Nistor-Vlad, I Prisecaru, C Allison 2019 International Conference on Energy and Environment (CIEM), 73-77, 2019 | 6 | 2019 |