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Ilie Prisecaru
Ilie Prisecaru
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Title
Cited by
Cited by
Year
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
272009
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
212013
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
162016
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
162015
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
162014
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
162009
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
152010
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
132007
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
122006
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
122006
A study of RELAP5 capability to perform the analysis of CANDU 6 reactors accidents
I Prisecaru, D Dupleac, L Biro
122005
Thermalhydraulic analysis of CANDU 6 100% reactor outlet header break using RELAP5 code
D Dupleac, I Prisecaru, P Ghitescu, G Negut
112007
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
102009
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
102008
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
92013
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
92009
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
82015
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
72014
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
72009
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
62019
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