The 7th dynamic AER benchmark is the first in which three-dimensional thermal hydraulics codes are supposed to be applied. The aim is to get a more precise core inlet temperature profile than the sector temperatures available typically with system codes. The benchmark consists of a start-up of the sixth, isolated loop in a VVER-440 plant. The isolated loop initially contains cold water without boric acid and the start-up leads to a somewhat asymmetrical core power increase due to feedbacks in the core. In this study, the 7th AER benchmark is calculated with the three-dimensional nodal reactor dynamics code HEXTRAN-SMABRE coupled with the porous computational fluid dynamics code PORFLO. These three codes are developed at VTT. A novel two-way...
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of co...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
The 7th dynamic AER benchmark is the first in which three-dimensional thermal hydraulics codes are s...
The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hyd...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
Having thoroughly analyzed the design features of VVER-type pressurized water reactors and VVR-type ...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
This paper presents a VVER-1000 coolant transient benchmark calculated using Serpent 2 generated gro...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of co...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...
The 7th dynamic AER benchmark is the first in which three-dimensional thermal hydraulics codes are s...
The VVER-1000 coolant transient benchmark is intended for validation of couplings of the thermal hyd...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
A three-dimensional reactor dynamics computer code has been developed, validated and applied for tra...
Having thoroughly analyzed the design features of VVER-type pressurized water reactors and VVR-type ...
International audienceComputational fluid dynamics (CFD) research for nuclear reactor safety dedicat...
This paper presents a VVER-1000 coolant transient benchmark calculated using Serpent 2 generated gro...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
As a result of upgrading, adapting, developing and validating several reactor physics and dynamics c...
The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of co...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
International audienceThis work has been performed in the framework of the OECD-NEA thermalhydraulic...