Dspace IEN: 05 Engenharia e Segurança de Reatores Nucleares

05 Engenharia e Segurança de Reatores Nucleares : [210] Página inicial da comunidade Visualizar estatísticas

Actran: a code for depletion calculations in PWR cores aiming the production of minor actinide for using in ads

A stabilized finite element formulation for the solution of the Navier-Stokes equations in axyssimetric geometry

Estudo experimental de escoamentos bifásicos em duto horizontal usando uma técnica de visualização

Artificial neural network used in the study of sensitives in iris reactor pressurizer

Calibração por comparação do sistema de aquisição de dados de temperatura de um circuito de circulação natural

Methodology for studies of natural circulation in closed circuits

Particle trajectory tracing for electrostatic and magnetostatic fields

Startup transients in accelerator driven systems using cinesp-ads code

Site selection process for new nuclear power plants-a method to support decision making and improving public participation

Modeling of the CTEx subcritical unit using MCNPX code

Modelling the transport of radionuclides released in the Ilha Grande bay (BRAZIL) after a LBLOCA in the primary system of A PWR

An experimental low-pressure facility to study boron transients in the pressurizer of an a integral modular nuclear reactor

Basic CFD investigation of decay heat removal in a pool type research reactor

Computer codes for the calculation of thermodynamic properties of water

Estudo experimental da circulação natural bifásica utilizando uma técnica de visualização

Event and fault tree model for reliability analysis of the greek research reactor

Flow visualization of bubble behavior under two-phase natural circulation flow conditions using high speed digital camera

Modeling of the dispersion of tritium from postulated accidental releases from nuclear power plants

One-dimensional termohidraulic model of the nucleus and lower and upper pool regions of the reactor RMB

Passive residual energy utilization system in thermal cycles on water-cooled power reactors

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