Alessandro da Cruz Gonçalves

Instituição:

Universidade Federal do Rio de Janeiro

Centro:

Centro de Tecnologia

Unidade:

Coordenação dos Programas de Pós-Graduação de Engenharia

Departamento:

Programa de Engenharia Nuclear/COPPE

ORCID:

https://orcid.org/0000-0002-0487-5862


Formação:

  • Universidade Federal do Rio de Janeiro

    | Pós-Doutorado | 2010 - 2011

  • Universidade Federal do Rio de Janeiro

    Engenharia Nuclear | Doutorado | 2006 - 2010

  • Universidade Federal do Rio de Janeiro

    Engenharia Nuclear | Mestrado | 2004 - 2006

  • Universidade Federal do Rio de Janeiro

    Física | Graduação | 2000 - 2003
Laboratórios:
Nuvens de Palavras:
Artigos:

(96.88% artigos com DOI)

Titulo DOI Ano
A differential equation for inverse point kinetics 10.1016/j.nucengdes.2024.113094 2024
Annular fuel neutronic analysis 10.1016/j.anucene.2023.109824 2023
Reactivity calculation in molten salt reactors with inverse kinetics model 10.1016/j.anucene.2023.110130 2023
Non-linear differential equation for reactivity monitoring 10.1016/j.anucene.2023.109960 2023
Simplified model for nuclear reactor core loading pattern optimization 10.1016/j.nucengdes.2023.112622 2023
Analytical solution for the Doppler Broadening Function using the Tsallis distribution 10.1016/j.pnucene.2021.104071 2022
A novel analytical solution of the deformed Doppler broadening function using the Kaniadakis distribution and the comparison of computational efficiencies with the numerical solution 10.1016/j.net.2021.10.003 2022
Calculation of delayed neutron precursors? transit time in the external loop during a flow velocity transient in a Molten Salt Reactors 10.1016/j.anucene.2021.108640 2022
Doppler Broadening of Neutron Cross-Sections Using Kaniadakis Entropy 10.3390/e24101437 2022
Effective medium temperature for calculating the Doppler broadening function using Kaniadakis distribution 10.1016/j.anucene.2021.108500 2021
Online identification of trips caused by the external proton source in an ADS reactor 10.1016/j.nucengdes.2021.111419 2021
New analytical formulations for the Doppler broadening function and interference term based on Kaniadakis distributions 10.1016/j.anucene.2019.106960 2020
Neutron point kinetics model with precursors? shape function update for molten salt reactor 10.1016/j.nucengdes.2019.110466 2020
A method to identify an accidental control rod drop with inverse distance weighted interpolation 2020
Analytical solution for the Doppler broadening function using the Kaniadakis distribution 10.1016/j.anucene.2018.11.023 2019
A deformed Doppler Broadening Function considering the Tsallis speed distribution 10.1016/j.anucene.2019.01.023 2019
Adjusted mean generation time parameter in the neutron point kinetics equations 10.1016/j.anucene.2019.05.019 2019
Identification model of an accidental drop of a control rod in PWR reactors using thermocouple readings and radial basis function neural networks 10.1016/j.anucene.2017.01.004 2017
Numerical Analysis for Transients in External Source Driven Reactors 10.4236/wjnst.2017.72009 2017
Support to the identification of anomalies in an external neutron source using Hurst Exponents 10.1016/j.pnucene.2017.05.009 2017
Detection model of accidental control rod drop in PWR reactors with in-core and ex-core nuclear instrumentation using Delaunay triangulation 10.1016/j.anucene.2017.05.009 2017
Calculation of resonance self-shielding factors in a round disk using the enlarged Doppler Broadening Function 10.1016/j.anucene.2017.05.051 2017
The Doppler Broadening Function using the Kaniadakis distribution 10.1016/j.anucene.2017.06.057 2017
A new formulation for the Doppler broadening function relaxing the approximations of Beth-Plackzec 10.1016/j.anucene.2015.10.030 2016
Assessment of thermo-mechanical performance of fuel elements with the use of CNFR and FRAPCON codes 10.1504/ijnest.2015.071613 2015
On-line method to identify control rod drops in Pressurized Water Reactors 10.1016/j.anucene.2014.04.007 2014
An Approximation for the Doppler Broadening Function and Interference Term Using Fourier Series 10.4236/wjnst.2012.24021 2012
Reconstruction of the Neutron Flux in a Slab Reactor 10.4236/wjnst.2012.24028 2012
Analytical solution of modified point kinetics equations for linear reactivity variation in subcritical nuclear reactors adopting an incomplete gamma function approximation 10.4236/ns.2012.431119 2012
An alternative analytical formulation for the Voigt function applied to resonant effects in nuclear processes 10.1016/j.nima.2011.07.029 2011
Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor 10.1016/j.anucene.2009.06.016 2009
Solution of the Doppler broadening function based on the fourier cosine transform 10.1016/j.anucene.2008.04.003 2008
Eventos:

(0.00% eventos com DOI)

Titulo DOI Ano
Novo Método para Identificação de Queda de Barra de Controle em Reatores Nucleares do Tipo PWR 2019
Applications of the Piecewise Constant Approximation Method for Modified Neutron Point Kinetics Equations 2019
Analysis of Point Kinetics Equations for Reactors with Circulating Fluid Fuel 2019
Simulation of Transients in ADS Reactors in Threedimensional Geometry 2019
An Improved Kaniadakis Doppler Broadening Function. 2018
The Tsallis Statistics Applied To The Calculation of Absorption Cross Section of 238U, 232Th AND 240Pu Isotopes 2017
Modified Mean Generation Time Parameter In The Neutron Point Kinetics Equations 2017
EImpirical Model for Mean Generation Time Adjustment Factor for Classic Point Reactor Kinetics Equations 2017
External neutron source anomalies analysis using hurst's exponent for the myrrha reactor 2015
Study for on-line system to identify inadvertent control rod drops in PWR reactors using ex-core detector and thermocouple measures 2015
Análise da reatividade para solução numérica da equação da cinética pontual para sistemas subcríticos 2015
Reactivity Monitoring for Subcritical Systems Using Euler- Maclaurin Formula 2014
The influence in disregarding the first approximation of Bethe-Plackzec in the calculation of resonance self-shielding factors 2014
Study for Identification of control rod drops in PWR reactors at any burnup step 2013
Analytical Solution of Point Kinetic Equations for Subcritical Systems 2013
An Analytical Formulation for Doppler Broadening Function Additional Term Using Expansions of Salzer 2013
Evaluation of Thermomechanical Behavior of Nuclear Fuel Using the Codes CNFR and FRAPCON 2013
Parametric Study of Spallation Targets for the Myrrha Reactor Using MCNPX Simulations 2013
An Approximation for the Interference Term Applied to the Calculation of the Average Scattering Cross Section Using Fourier Series 2012
A New Formulation for Self-shielding Factors Using the Asymptotic Expansion of the Integral Exponential Function 2012
An analytical approximation for the prediction of transients with temperature feedback 2010
Inverse kinetics for subcritical systems with variating external sources 2010
Inverse kinetics for subcritical systems 2009
An alternative technique for the implementation of an analytical approximation for transients with temperature feedback 2009
Analytical calculation of the average scattering cross sections using Fourier series 2009
Analytical solution of the point kinetics equations in subcritical systems for linear reactivity variations and external sources 2009
New approximations for the interference term applied to the calculation of scattering cross section of the isotopes 238U 2008
New approximations for the Doppler broadening function applied to the calculation of resonance self-shielding factors 2008
A new approximation for the Doppler broadening function using the Fourier series method 2008
Analytical approximations for resonance self-shielding factors 2008
A new expression for the Doppler broadening function based on the Fourier cosine transform 2007
Comparative analysis among several methods used to solve the point kinetic equations 2007
Um método eficiente de cálculo da função J 2007
Uma análise numérica de novas formulações para os fatores de auto-proteção ressonantes 2007
A inserção de um termo residual como método de aceleração de cálculo dos fatores de auto-proteção ressonantes dos isótopos Th232 e Pu240 para diferentes temperaturas 2007
Novas metodologias de otimização do tempo de processamento no cálculo da função J 2007
Validação de novas técnicas de aceleração do cálculo dos fatores de auto-proteção na faixa epitérmica para os isótopo 232Th e 240Pu 2007
Monitoração da reatividade através do histórico da potência nuclear 2006
Publicações:
Minha Rede: