[EN] Recently, the interest in the study of various types of transients involving changes in the boron concentration inside the reactor, has led to an increase in the interest of developing and studying new models and tools ...
This paper constitutes a first approach of the
assessment of the ANSYS-CFX code to simulate the
TRIGA research reactor. Due to computational limits
simplifications of the core and of some other geometrical
details ...
Faria De Castro, Victor; Miró Herrero, Rafael; Mello da Silva, C. A.; Pereira, C.; Verdú Martín, Gumersindo Jesús; Barrachina Celda, Teresa María; Dalle, H.M.(Grupo Senda, 2011-09)
KENO
-
VI es un código de transporte neutrónico en el sistema SCALE6.0 que utiliza
el método de Monte Carlo para cálculos de criticidad en sistemas nucleares. Se ha construido
un modelo en 3D para caracterizar parámetros ...
[EN] In present neutron kinetics codes, control rods banks do not have the possibility of dynamic movement during the simulation of a transient; besides it is necessary to send the boron concentration from the thermal-hydraulic ...
The objective of this work is to introduce an improvement in best estimate coupled neutronicthermalhydraulic
3D codes simulations, by adding a model for the control rod movement in the
coupled code RELAP5/PARCS v2.7, by ...
[ES] El uso de los códigos de Dinámica de Fluidos Computacional (CFD) 3D para predecir el flujo
estacionario y transitorio en los reactores nucleares está creciendo rápidamente y constituye una
nueva tendencia en su ...
[EN] The Rod Ejection Accident (REA) belongs to the Reactivity-Initiated Accidents (RIA) category of accidents
and it is part of the licensing basis accident analyses required for pressurized water reactors (PWR). The
REA ...