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Monte Carlo simulation of Feynman-α and Rossi-α techniques for calculation of kinetic parameters of Tehran research reactor
, Article Annals of Nuclear Energy ; Volume 38, Issue 10 , 2011 , Pages 2140-2145 ; 03064549 (ISSN) ; Vosoughi, N ; Hosseini, M ; Sharif University of Technology
2011
Abstract
Noise analysis techniques including Feynman-α (variance-to-mean) and Rossi-α (correlation) have been simulated by MCNP computer code to calculate the prompt neutron decay constant (α0), effective delayed neutron fraction (βeff) and neutron generation time (Λ) in a subcritical condition for the first operating core configuration of Tehran Research Reactor (TRR). The reactor core is considered to be in zero power (reactor power is less than 1 W) in the entire simulation process. The effect of some key parameters such as detector efficiency, detector position and its dead time on the results of simulation has been discussed as well. The results of proposed method in the current study are...
Modeling superconductive fault current limiter using constructive neural networks
, Article 2007 IEEE International Symposium on Industrial Electronics, ISIE 2007, Caixanova - Vigo, 4 June 2007 through 7 June 2007 ; 2007 , Pages 2859-2863 ; 1424407559 (ISBN); 9781424407552 (ISBN) ; Sadati, N ; Hosseini, M. N ; Sharif University of Technology
2007
Abstract
Although so many advances have been proposed in the field of artificial intelligence and superconductivity, there are few reports on their combination. On the other hand, because of the nonlinear and multivariable characteristics of the superconductive elements and capabilities of neural networks in this field, it seems useful to apply the neural networks to model and control the superconductive phenomena or devices. In this paper, a new constructive neural network (CNN) trained by two different optimization algorithms; back-propagation and genetic algorithm, is proposed which models the behavior of the superconductive fault current limiters (SFCLs). Simulation results show that the proposed...
Development of a VVER-1000 core loading pattern optimization program based on perturbation theory
, Article Annals of Nuclear Energy ; Volume 39, Issue 1 , 2012 , Pages 35-41 ; 03064549 (ISSN) ; Vosoughi, N ; Sharif University of Technology
2012
Abstract
In-core nuclear fuel management is one of the most important concerns in the design of nuclear reactors. Two main goals in core fuel loading pattern design optimization are maximizing the core effective multiplication factor in order to extract the maximum energy, and keeping the local power peaking factor lower than a predetermined value to maintain the fuel integrity. Because of the numerous possible patterns of fuel assemblies in the reactor core, finding the best configuration is so important and challenging. Different techniques for optimization of fuel loading pattern in the reactor core have been introduced by now. In this study, a software is programmed in C# language to find an...
Application of a dual functional luminescent layer to enhance the light harvesting efficiency of dye sensitized solar cell
, Article Materials Letters ; 2016 ; 0167577X (ISSN) ; Taghavinia, N ; Diau, E. W. G
Elsevier B.V
2016
Abstract
A luminescent coating of CaAlSiN3:Eu2+ particles applied on photoanode (TiO2) layer of SQ1 sensitized solar cell by doctor blading the paste of phosphor particles. The luminescent layer acted as a dual functional layer and enhanced the short circuit current density (JSC) by 64% via both scattering effect and downshifting of the photons in 400-600nm spectral range to photons in 600-800nm spectral range. Considerable relative enhancement in incident photon to current conversion efficiency (IPCE) up to 350% in 400-600nm spectral range proves the down shifting effect as the dominant factor for the improved performance of dye sensitized solar cell (DSSC). © 2016 Elsevier B.V
Calculation of fuel burn up and radioactive inventory for HEU fuel element of Tehran Research Reactor
, Article International Conference on Nuclear Engineering, Proceedings, ICONE, 17 May 2010 through 21 May 2010 ; Volume 2 , 2010 ; 9780791849309 (ISBN) ; Vosoughi, N ; Hosseini, M ; Nuclear Engineering Division ; Sharif University of Technology
2010
Abstract
This paper presents a new approach for fuel burn up evaluation and radioactive inventory calculation used in Tehran Research Reactor. The approach is essentially based upon the utilization of a program written by C# which integrates the cell and core calculation codes, i.e., WIMSD-4 and CITVAP, respectively. Calculation of fuel burn up and radioactive inventories has been done for 26 core configuration of Tehran Research Reactor with HEU fuel element. The present inventory and fuel enrichment of each fuel element have been calculated
Noise source reconstruction using ANN and hybrid methods in VVER-1000 reactor core
, Article Progress in Nuclear Energy ; Vol. 71, issue , 2014 , pp. 232-247 ; ISSN: 01491970 ; Vosoughi, N ; Sharif University of Technology
2014
Abstract
The present paper consists of two separate sections. In the first section, the neutron noise source is reconstructed using Artificial Neural Network (ANN) in a typical VVER-1000 reactor core. In the first stage of this section, the neutron noise calculations are performed based on Galerkin Finite Element Method (GFEM). To this end, two types of noise sources including absorber of variable strength and vibrating absorber are considered. As the results of noise calculations, the neutron noise is obtained in the location of detectors. In the second stage, the multilayer perception neural network is developed for reconstruction of the noise source. Complex neutron noises (real and imaginary...
Neutron noise simulation by GFEM and unstructured triangle elements
, Article Nuclear Engineering and Design ; Volume 253 , 2012 , Pages 238-258 ; 00295493 (ISSN) ; Vosoughi, N ; Sharif University of Technology
2012
Abstract
In the present study, the neutron noise, i.e. The stationary fluctuation of the neutron flux around its mean value, is calculated in 2-group forward and adjoint diffusion theory for both hexagonal and rectangular reactor cores. To this end, the static neutron calculation is performed at the first stage. The spatial discretization of equations is based on linear approximation of Galerkin Finite Element Method (GFEM) using unstructured triangle elements. Using power iteration method, forward and adjoint fluxes with the corresponding eigenvalues are obtained. The results are then benchmarked against the valid results for BIBLIS-2D and IAEA-2D benchmark problems and DONJON computer code. The...
On a various noise source reconstruction algorithms in VVER-1000 reactor core
, Article Nuclear Engineering and Design ; Volume 261 , 2013 , Pages 132-143 ; 00295493 (ISSN) ; Vosoughi, N ; Sharif University of Technology
2013
Abstract
In present study, the neutron noise source is reconstructed using three different unfolding techniques in a typical VVER-1000 reactor core. In first stage, the neutron noise calculation based on Galerkin finite element method (GFEM) is performed; in which the neutron noise in two energy group due to the noise sources of type absorber of variable strength and vibrating absorber is calculated. The neutron noise due to inadvertent loading of a fuel assembly in an improper position (ILFAIP), as a new defined noise source in the neutron noise studies, is calculated as well. In the second stage, the inversion, zoning and scanning methods are applied for reconstruction of the noise source of type...
Development of two-dimensional, multigroup neutron diffusion computer code based on GFEM with unstructured triangle elements
, Article Annals of Nuclear Energy ; Volume 51 , 2013 , Pages 213-226 ; 03064549 (ISSN) ; Vosoughi, N ; Sharif University of Technology
2013
Abstract
Various methods for solving the forward/adjoint equation in hexagonal and rectangular geometries are known in the literatures. In this paper, the solution of multigroup forward/adjoint equation using Finite Element Method (FEM) for hexagonal and rectangular reactor cores is reported. The spatial discretization of equations is based on Galerkin FEM (GFEM) using unstructured triangle elements. Calculations are performed for both linear and quadratic approximations of the shape function; based on which results are compared. Using power iteration method for the forward and adjoint calculations, the forward and adjoint fluxes with the corresponding eigenvalues are obtained. The results are then...
Development of 3D neutron noise simulator based on GFEM with unstructured tetrahedron elements
, Article Annals of Nuclear Energy ; Volume 97 , 2016 , Pages 132-141 ; 03064549 (ISSN) ; Vosoughi, N ; Sharif University of Technology
Elsevier Ltd
2016
Abstract
In the present study, the neutron noise, i.e. the stationary fluctuation of the neutron flux around its mean value is calculated based on the 2G, 3D neutron diffusion theory. To this end, the static neutron calculation is performed at the first stage. The spatial discretization of the neutron diffusion equation is performed based on linear approximation of Galerkin Finite Element Method (GFEM) using unstructured tetrahedron elements. Using power iteration method, neutron flux and corresponding eigen-value are obtained. The results are then benchmarked against the valid results for VVER-1000 (3D) benchmark problem. In the second stage, the neutron noise equation is solved using GFEM and...
Uncertainty evaluation of calculated and measured kinetics parameters of Tehran Research Reactor
, Article Nuclear Engineering and Design ; Volume 240, Issue 10 , 2010 , Pages 2761-2767 ; 00295493 (ISSN) ; Vosoughi, N ; Sharif University of Technology
2010
Abstract
Effective delayed neutron fraction βeff and neutron generation time Λ are important factors in reactor physics calculation and transient analysis. In the first stage of this research, these kinetics parameters have been calculated for two states of Tehran Research Reactor (TRR), i.e. cold (fuel, clad and coolant temperature 20 °C) and hot (fuel, clad and coolant temperature 65, 49 and 44 °C, respectively) states using MTR-PC computer code. The ratio of (βeff) i/(βeff)core plays an important role in reactivity accident analysis codes. This parameter and its contribution to effective delayed neutron fraction from each nucleus have been calculated in cold and hot reactor states. Uncertainty of...
Fabrication of high conductivity TiO2/Ag fibrous electrode by the electrophoretic deposition method
, Article Journal of Physical Chemistry C ; Volume 112, Issue 47 , 2008 , Pages 18686-18689 ; 19327447 (ISSN) ; Taghavinia, N ; Sharifi, N ; Chavoshi, M ; Rahman, M ; Sharif University of Technology
2008
Abstract
TiO2 deposited on a membrane of Ag fibers was prepared as a photoelectrochemical cell electrode. Ag fibers were made by reduction of Ag complexes on cellulose fibers, followed by burning out the template. TiO 2 photocatalyst layers were grown on the fibers by electrophoretic deposition of TiO2 nanoparticles. Ag fibers could be uniformly deposited. Photocatalytic tests by dye decomposition and electrochemical impedance spectroscopy (EIS) under UV illumination demonstrate that Ag fibers act as a good substrate that provides both high surface area and good separation of photogenerated electron-hole pairs and causes the enhancement of photocatalytic activity in comparison with a thin film of...
Neutron noise simulation using ACNEM in the hexagonal geometry
, Article Annals of Nuclear Energy ; Volume 113 , 2018 , Pages 246-255 ; 03064549 (ISSN) ; Vosoughi, N ; Vosoughi, J ; Sharif University of Technology
Elsevier Ltd
2018
Abstract
In the present study, the development of a neutron noise simulator, DYN-ACNEM, using the Average Current Nodal Expansion Method (ACNEM) in 2-G, 2-D hexagonal geometries is reported. In first stage, the static neutron calculation is performed. The neutron/adjoint flux distribution and corresponding eigen-values are calculated using the algorithm developed based on power iteration method by considering the coarse meshes. The results of the static calculation are validated against the well-known IAEA-2D benchmark problem. In the second stage, the dynamic calculation is performed in the frequency domain in which the dimension of the variable space of the noise equations is lower than the time...
The effects of Misch-Metal oxide addition on magnetic properties and crystal structure of Sr1-xMMxFe12O19 ferrite
, Article Journal of Alloys and Compounds ; Volume 448, Issue 1-2 , 2008 , Pages 284-286 ; 09258388 (ISSN) ; Naghibolashraphy, N ; Sharif University of Technology
2008
Abstract
The effects of Misch-Metal (MM) oxide addition on magnetic properties, crystal structure and microstructure of the M-type strontium ferrite have been studied. By MM substitution of Sr a significant increase in intrinsic coercivity and a slight decrease in remanence was observed. The highest value of energy product was obtained at 4 wt.% MM addition. By calculating the lattice constants of 4 and 8 wt.% MM added specimens, it was found that the length of c-axis decreases by 4 wt.% MM addition and then undergoes a considerable increase at 8 wt.%, while the a-axis increases monotonously. The SEM observations revealed that the migration of MM oxides to the grain boundaries could be the major...
Development of MCNPX-ESUT computer code for simulation of neutron/gamma pulse height distribution
, Article Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment ; Volume 782 , May , 2015 , Pages 112-119 ; 01689002 (ISSN) ; Vosoughi, N ; Zangian, M ; Sharif University of Technology
Elsevier
2015
Abstract
In this paper, the development of the MCNPX-ESUT (MCNPX-Energy Engineering of Sharif University of Technology) computer code for simulation of neutron/gamma pulse height distribution is reported. Since liquid organic scintillators like NE-213 are well suited and routinely used for spectrometry in mixed neutron/gamma fields, this type of detectors is selected for simulation in the present study. The proposed algorithm for simulation includes four main steps. The first step is the modeling of the neutron/gamma particle transport and their interactions with the materials in the environment and detector volume. In the second step, the number of scintillation photons due to charged particles such...
An extended-fem model for co2 leakage through a naturally fractured cap-rock during carbon dioxide sequestration
, Article Transport in Porous Media ; Volume 145, Issue 1 , 2022 , Pages 175-195 ; 01693913 (ISSN) ; Ehsani, R ; Hosseini, N ; Sharif University of Technology
Springer Science and Business Media B.V
2022
Abstract
In this paper, a numerical model is developed for the assessment of carbon dioxide transport through naturally fractured cap-rocks during CO2 sequestration in underground aquifers. The cap-rock contains two types of fracture with different length scales: micro-cracks (fissures) and macro-cracks (faults). The effect of micro-cracks is incorporated implicitly by modifying the intrinsic permeability tensor of porous matrix, while the macro-cracks are modeled explicitly using the extended finite element method (X-FEM). The fractured porous medium is decomposed into the porous matrix and fracture domain, which are occupied with two immiscible fluid phases, water and CO2. The flow inside the...
Utilizing network coding for file dessimination in peer-to-peer systems
, Article 3rd International Conference on New Technologies, Mobility and Security, NTMS 2009, 20 December 2009 through 23 December 2009, Cairo ; 2009 ; 9781424462735 (ISBN) ; Movaghar, A ; Sadat Bathaee, N ; Sharif University of Technology
2009
Abstract
Network coding was first introduced in information theory for increasing the multicast rate in the networks with directed links. We can model many of the content distribution networks and overlay networks with such a network. Therefore, the solutions introduced in information theory can be used in these networks. In this paper, we analyze using of network coding in uncoordinated cooperative content distribution systems. Reaching the optimum performance in an uncoordinated system needs blocks of the system to be "equally important". In that case, we can retrieve the whole data without need of central controller or complex algorithms. In part of this paper, we exactly define the concept of...
Luminescent Spectral Conversion to Improve the Performance of Dye-Sensitized Solar Cells
, Article ChemPhysChem ; Volume 18, Issue 23 , 2017 , Pages 3292-3308 ; 14394235 (ISSN) ; Taghavinia, N ; Wei Guang Diau, E ; Sharif University of Technology
2017
Abstract
Relative to the broadband solar spectrum, a narrow range of spectral absorption of photovoltaic (PV) devices is considered an important determinant that the efficiency of light harvesting of these devices is less than unity. Having the narrowest spectral response to solar radiation among all PV devices, dye-sensitized solar cells (DSSCs) suffer severely from this loss. Luminescent spectral conversion provides a mechanism to manipulate and to adapt the incident solar spectrum by converting, through photoluminescence, the energies of solar photons into those that are more effectively captured by a PV device. This mechanism is particularly helpful for DSSCs because there is much flexibility in...
Preparation of electrospun affinity membrane and cross flow system for dynamic removal of anionic dye from colored wastewater
, Article Fibers and Polymers ; Volume 18, Issue 12 , 2017 , Pages 2387-2399 ; 12299197 (ISSN) ; Vossoughi, M ; Mahmoodi, N. M ; Sharif University of Technology
2017
Abstract
In this research, poly(vinyl alcohol) (PVA)/chitosan electrospun nanofibrous membrane (ENM) was prepared by electrospinning method in order to investigate its dye removal ability from colored wastewater. The morphology and average fiber diameter of the membranes were investigated by scanning electron microscopy (SEM), image analysis and atomic force microscopy (AFM). The chemical characterization was studied by Fourier transform infrared spectroscopy (FTIR). The permeability of the membranes was evaluated by measuring pure water flux (PWF). In order to investigate the performance of the prepared membranes they were used in the batch adsorption and membrane separation for dye removal from...
Modeling of reactive acid transport in fractured porous media with the Extended–FEM based on Darcy-Brinkman-Forchheimer framework
, Article Computers and Geotechnics ; Volume 128 , December , 2020 ; Salehi Sichani, A ; Hosseini, N ; Sharif University of Technology
Elsevier Ltd
2020
Abstract
In this paper, a fully coupled numerical model is developed based on the X-FEM technique to simulate the reactive acid transport in fractured porous media. The porous medium consists of the solid and fluid phases, in which the fluid phase includes water and acid components, and chemical reactions can be occurred between acid component and solid phase at the solid–fluid interfaces. The governing equations include the mass and momentum conservation laws for fluid phase, and the advective–diffusive transport of acid component that must be solved to obtain the primary unknowns, including the pore fluid pressure, acid concentration, and fluid velocity vector. Applying the...