In the light of the sustained development in computer technology, the possibilities of code capabilities have been enlarged substantially. Consequently, advanced safety evaluations and design optimizations, which were not possible few years ago, can now be performed. Nowadays, it becomes possible to switch to new generation of computational tools, namely, coupled code (CC) technique. The application of such method is mandatory for the analysis of transient events where strong coupling between the core neutronics and the primary circuit thermal-hydraulics exits, and more especially when asymmetrical processes take place in the core leading to local space-dependent power generation. Through the current study, a demonstration of the matur...
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, wh...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hyd...
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the de...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics c...
Incorporation of fuil three-dimensional (3D) rnodels of the reactor core unto system transient codes...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
Incorporation of full three-dimensional (3D) models of the reactor core into system transient codes ...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
The purpose of this seminar is first to discuss the basis of the coupling between 3-D Neutron- Kinet...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity sim...
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, wh...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hyd...
Issues connected with the thermal-hydraulics and neutronics of nuclear plants still challenge the de...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
Incorporating full three-dimensional models of the reactor core into system transient codes allows f...
The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics c...
Incorporation of fuil three-dimensional (3D) rnodels of the reactor core unto system transient codes...
To simulate the mode of the RCP starting in an earlier inoperative loop, KORSAR/GP, a code supportin...
Incorporation of full three-dimensional (3D) models of the reactor core into system transient codes ...
Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermal-hydra...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
The purpose of this seminar is first to discuss the basis of the coupling between 3-D Neutron- Kinet...
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and cou...
The thermal hydraulic and neutronics coupling analysis is an important part of the high-fidelity sim...
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, wh...
The application of best-estimate codes [coupled neutron kinetics (NK)/thermal hydraulics (TH)] for s...
The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hyd...