Modes with violation of the reactor plant cooling conditions on the primary circuit side of a VVER reactor were simulated using the TRAC-PD2 and Open FOAM thermohydraulic codes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer's Guide Version 1.6. 2009) based on energy and mass conservation equations for the three-dimensional unsteady flow of a two-phase mixture. Coupled simulation of the dynamics of neutronic and thermohydraulic processes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer's Guide Version 1.6. 2009, Bolshagin et al. 2009, Galanin 1971, Weinberg and Wigner 1961, Ovchinnikov and Semenov 1988, Report LA-UR-03-1987) aims to improve the qualitative understanding and the quantitati...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
This work is a continuation of previous work on the importance of accuracy in the simulation of nucl...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
Two reactor dynamics related computer codes of the calculation system at the Technical Research Cent...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Two reactor dynamics related computer codes of the calculation system at the Technical Research Cent...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
This work is a continuation of previous work on the importance of accuracy in the simulation of nucl...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
The reactor dynamics codes for transient and accident analyses inherently include the coupling of ne...
Two reactor dynamics related computer codes of the calculation system at the Technical Research Cent...
TRAB-3D is the newest member in the reactor dynamics code family developed in VTT. It is now possibl...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Two reactor dynamics related computer codes of the calculation system at the Technical Research Cent...
The scope of the presented thesis work aimed at investigating the thermal-hydraulic phenomena that t...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
According to the R&D agenda of the SNETP (Sustainable Nuclear Energy Technology Platform) and Genera...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
This work is a continuation of previous work on the importance of accuracy in the simulation of nucl...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...