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Total 139 records

    Pin Power Reconstruction Method by Nodal Core Calculation Results

    , M.Sc. Thesis Sharif University of Technology Kefalati, Mohadeseh (Author) ; Vosoughi, Naser (Supervisor) ; Ghaffari, Mohsen (Supervisor)
    Abstract
    The widespread use of nuclear energy leads to obtain detailed information, such as neutron flux distribution (power) which is very effective in designing and evaluating the reactor safety. The neutron flux (power) reconstruction method uses the homogeneous flux distribution and the heterogeneous form function in a fuel assembly to calculate the heterogeneous power in the fuel rods. Therefore, this method has been widely developed in the last two decades. This study investigates to calculate two-dimensional and two-group neutron flux (power) in the fuel rod for both quadrilateral and hexagonal geometry related to core results by using nodal method. To achieve a more complete program and join... 

    Equations-of-motion method for triplet excitation operators in graphene

    , Article Journal of Physics Condensed Matter ; Volume 24, Issue 9 , February , 2012 ; 09538984 (ISSN) Jafari, S. A ; Baskaran, G ; Sharif University of Technology
    2012
    Abstract
    The particlehole continuum in the Dirac sea of graphene has a unique window underneath, which in principle leaves room for bound state formation in the triplet particlehole channel (Baskaran and Jafari 2002 Phys. Rev. Lett. 89 016402). In this work, we construct appropriate triplet particlehole operators and, using a repulsive Hubbard-type effective interaction, we employ equations of motion to derive approximate eigenvalue equations for such triplet operators. While the secular equation for the spin density fluctuations gives rise to an equation which is second order in the strength of the short range interaction, the explicit construction of the triplet operators obtained here shows that,... 

    A fast numerical method for calculating the 3D proton dose profile in a single-ring wobbling spreading system

    , Article Australasian Physical and Engineering Sciences in Medicine ; Volume 34, Issue 3 , 2011 , Pages 317-325 ; 01589938 (ISSN) Riazi, Z ; Afarideh, H ; Sadighi Bonabi, R ; Sharif University of Technology
    Abstract
    Based on the determination of protons fluence at the phantom's surface, a 3D dose distribution is calculated inside a water phantom using a fast method. The dose contribution of secondary particles, originating from inelastic nuclear interactions, is also taken into account. This is achieved by assuming that 60% of the energy transferred to secondary particles is locally absorbed. Secondary radiation delivers approximately 16.8% of the total dose in the plateau region of the Bragg curve for monoenergetic protons of energy 190 MeV. The physical dose beyond the Bragg peak is obtained for a proton beam of 190 MeV using a Geant4 simulation. It is found that the dose beyond the Bragg peak is <... 

    Galerkin and Generalized Least Squares finite element: A comparative study for multi-group diffusion solvers

    , Article Progress in Nuclear Energy ; Volume 85 , 2015 , Pages 473-490 ; 01491970 (ISSN) Hosseini, S. A ; Saadatian Derakhshandeh, F ; Sharif University of Technology
    Elsevier Ltd  2015
    Abstract
    Abstract In this paper, the solution of multi-group neutron/adjoint equation using Finite Element Method (FEM) for hexagonal and rectangular reactor cores is reported. The spatial discretization of the neutron diffusion equation is performed based on two different Finite Element Methods (FEMs) using unstructured triangular elements generated by Gambit software. Calculations are performed using Galerkin and Generalized Least Squares FEMs; based on which results are compared. Using the power iteration method for the neutron and adjoint calculations, the neutron and adjoint flux distributions with the corresponding eigenvalues are obtained. The results are then validated against the valid... 

    Permeability modeling using ANN and collocated cokriging

    , Article 72nd European Association of Geoscientists and Engineers Conference and Exhibition 2010: A New Spring for Geoscience. Incorporating SPE EUROPEC 2010 ; Volume 5 , 2010 , Pages 3939-3943 ; 9781617386671 (ISBN) Zarei, A ; Masihi, M ; Sharif University of Technology
    Society of Petroleum Engineers  2010
    Abstract
    Obtaining a reliable reservoir permeability map that is consistent with all available data is of great important for reservoir engineers. However, there is not enough core from existing wells to estimate the reservoir permeability directly but Well log data are more widely available. This study aims to model permeability within the reservoir while there is no enough data. In particular, we use artificial neural networks to estimate permeability using four input logs of sonic, gravity, porosity and neutron logs in six existing wells. In order to eliminate the correlated data, we have done Principal Component Analysis on selected input logs. Collocated cokriging is considered as a valuable... 

    Developing an approach for maximizing neutron activation reaction rate by optimizing moderator dimensions and target position using the Monte Carlo code in combination with the GA and ANN algorithms

    , Article Annals of Nuclear Energy ; Volume 168 , 2022 ; 03064549 (ISSN) Moshkbar Bakhshayesh, K ; Sahraeian, M ; Mohtashami, S ; Sharif University of Technology
    Elsevier Ltd  2022
    Abstract
    In this study, in order to maximize the reaction rate of neutron activation (NA), an approach using combination of the MCNP code, the feed-forward neural network with the Bayesian regularization (FFNN-BR) learning algorithm, and the genetic algorithm (GA) is proposed. The MCNP code calculates the reaction rates based on the different moderator dimensions/ target positions. The calculated reaction rates with appropriate features (i.e. RT, R2S, and Z2S) are applied for training of the FFNN-BR. The trained neural network is utilized for estimating the reaction rates of the generated individuals by the GA. The results show that the trained neural network estimates the reaction rates with... 

    Investigation on Direct Discrete Method for Neutron Transport Equation

    , M.Sc. Thesis Sharif University of Technology Ghafari, Mohsen (Author) ; Vosoughi, Naser (Supervisor) ; Bagher Ghofrani, Mohammad (Supervisor)
    Abstract
    Improvement of numerical solutions and application of them is very important section of engineering researches. So, there are several numerical methods and procedures for solution of equations or problems. All of them have advantages and disadvantages for selection best method. The efficiency of a method is a function of Limitation parameter like time, software and hardware. One of the recent numerical methods for engineering problems is Direct Discrete Method (DDM). This method prepares modern theory for balance equations; also this method combines some advantages of the other numerical methods like finite element and finite difference. DDM uses a double set of mesh structures namely primal... 

    Elemental Concentration of the Air of City of Karaj Using INAA and AAS and Comparing of the Results with Simulation Data of Aermod

    , M.Sc. Thesis Sharif University of Technology Mardashti, Forough (Author) ; Sohrabpour, Mostafa (Supervisor)
    Abstract
    City of Karaj with 2 million population used to enjoy very clean and accommodating air and environment . This congenial condition was due to agricultural and gardening activities of the local population . This way of life has undergone a profound change due to a change in the economic activities of the local population from farming and agriculture to industrial activities . And this has brought particulate matter wich has been exacerbated in the recent years . With the additional onslaught of the dust storms coming from the neighboring countries due to drying up of rivers and lagoons .The main object of this work was to obtain the spectrum of the PM and the additional component of PM that... 

    Noise Characterization in VVER-1000 Reactor Core

    , M.Sc. Thesis Sharif University of Technology Nassiri, Ahmad (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Neutron fluctuations in both low and high power reactors provide important information about the system. The origins of these fluctuations are different in both regimes. In low power the branching process is the reason of these fluctuations. But the random nature of technological processes such as boiling in the reactors cooling and mechanical structure vibrating such as control rod and fuel rod created the neutron noise. Mathematical descriptions and applications of neutron noise for each mode are different. In common mode, fluctuations in the neutron detection system, determine some parameters and determin the start abnormality in system. In this study the spatial dependence of the cross... 

    Solving the Neutron Transport Equation Using Unstructured Spatio-temporal Elements by the Direct Discrete Method (DDM)

    , M.Sc. Thesis Sharif University of Technology Meftahi, Mohammad (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Nowadays, the use of numerical methods is very common in solving complex equations, and various methods have been developed in this field. One of the new methods in this field, is the direct discrete method(DDM), Which was initially used to solve the electromagnetic field equations. In the past years, this method has been used to discretization some of the neutronics equations and acceptable results are recorded. So that the convergence order for the neutron diffusion equation in this method is higher than other numerical methods. In this method the geometry of the problem is divided into primary and secondary cell that primary cell platform is fixed but there is the possibility of making... 

    Elemental Characterization of the Total Suspended Particulate Matter of the Industrial City of Arak with NAA and AAS and Modeling with the AERMOD Software

    , M.Sc. Thesis Sharif University of Technology Sarlak, Mansoureh (Author) ; Sohrabpour, Mostafa (Supervisor)
    Abstract
    Environmental conditions of various cities of Iran are deteriorating due to various contributing effects of increased traffic, deforestation, industrial pollution etc. Arak is an example in point. It is a city of about 440,000 inhabitants. It is located at the edge of the main central desert (Kavir) of Iran. It lacks any appreciable vegetation or wooded areas and it is the home of a number of major industries. These include aluminum smelting, petrochemical industry, refinery, power plant and various other heavy manufacturing facilities. It was suggested to perform an air sampling of the city for a whole year (2010-2011) to determine the concentration of various elements by instrumental... 

    Localization of a Postulated Noise in VVER-1000 Reactor Core Using Neutron Noise Analysis Methods

    , M.Sc. Thesis Sharif University of Technology Malmir, Hessam (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    In this thesis, localization of a postulated noise from limited neutron detectors sparsely distributed throughout the core of a typical VVER-1000 reactor is investigated. For this purpose, developing a 2-D neutron noise simulator for hexagonal geometries based on the 2-group diffusion approximation, the reactor dynamic transfer function is calculated. The box-scheme finite difference method is first developed for hexagonal geometries, to be used for spatial discretisation of both 2-D 2-group static and noise diffusion equations. Using the discretised static equations, a 2-D 2-group static simulator (HEXDIF-2) is developed which its results are benchmarked against the well-known CITATION... 

    (MCNP Simulation of Online Elemental Analyzer in the Cement Manufacturing Poroces by Prompt Gamma Neutron Activation Analysis (PGNAA

    , M.Sc. Thesis Sharif University of Technology Sadeghi, Mohammad (Author) ; Sohrabpour, Mostafa (Supervisor)
    Abstract
    Method of Prompt Gamma Neutron Activation Analysis (PGNAA) is useful for controlling some massive production processes such as cement industry and mineral materials. Difficulty of other methods of analysis such as XRF comparing with PGNAA is that mass of sample is small and it doesn’t determine heterogeneity of mixture. On the other hand, need to sampling is also another problem of these analysis methods because sampling is terminated and it doesn’t supervise on production continuously, in fact its quality can’t be revealed simultaneously and there is a long time between sampling and control of process. Usually, analysis methods such as XRF are useful for processes that are controlled... 

    Fabrication of “Boron-Clay-Polymer" and "Lead-Clay-Polymer" Nanocomposites for Radiation Shielding of Neutron and Gamma Rays

    , M.Sc. Thesis Sharif University of Technology Kiani, Mohammad Amin (Author) ; Outokesh, Mohammad (Supervisor) ; Ahmadi, Javad (Supervisor) ; Mohammadi, Agheil (Co-Advisor)
    Abstract
    In this study, epoxy resin has been modified by nano-clay additives using direct mixing method and epoxy-clay nanocomposites were designed and produced with optimized percentage of clay content. By adding the powder of born carbide and lead oxide in nanocomposites new compounds are obtained. The results are used for protection against neutron and gamma rays, respectively. After preparation of epoxy-clay-born carbide and epoxy- clay-lead oxide nanocomposite the effects of irradiation and carbon fiber on mechanical and thermal properties of nanocomposites were examined. The Nanocomposites were exposed to Electron Beam Irradiation (EBI) in 100 and 500 kGy doses to investigate the effect of... 

    Investigation of the Suspended Particulate Matter of the Air of the City of Ahvaz In Normal and Dust storm Conditions by INAA and AAS

    , M.Sc. Thesis Sharif University of Technology Khani Veldani, Rahman (Author) ; Sohrabpour, Mostafa (Supervisor)
    Abstract
    Ahwaz is typical of a polluted city. It ranks in the third place after Tehran and Esfahan and with the onslaught Of the dust storms it has acquired the dubious distinction of 1st polluted city in the world. The pollution status of this city was investigated from May 2012 to May 2013. 110 air filters were collected during this period. The air filters were analysed with AAS and INAA techniques. with the use of AAS we measured the concentration of Cd, Cu, Fe, Mg, Mn, Ni and Pb elements. For the use of INAA method on the air filters we used two reactors of MNSR at Esfahan and the 5MW research reactor of Tehran. We managed to measure twenty five elements of Al , As , Br , Ca , Ce , Cl , Co , Cr ,... 

    Source Localization by Analysis the Response of Detectors Using Inverse Methods

    , M.Sc. Thesis Sharif University of Technology Mechershavi, Fatemeh (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Localization of a neutron point source using a designed computer program namely “MCMC-MATURE” is performed. The computer program analyses several detector responses in some certain media by Markov Chain Monte Carlo (MCMC) method and a new iteration algorithm. Identification of the possible regions of source position would be found by analyzing the initial fluxes generated by mesh tally of MCNPX computer code. The designed computer program is capable to generate the flux between detectors. “Regular-Sequential”, “Irregular-Sequential” and “Non-Sequential” are three methods used for sampling the generated random number in two dimensions. Each sample multiplied by a sampling function and lead to... 

    Range Verification and Dose Evaluation in Proton Therapy by Using Monte Carlo Method

    , M.Sc. Thesis Sharif University of Technology Rabiee, Zahra (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    In this study, the emission and detection of secondary particles such as gamma and neutron along the beam path was investigated to evaluate proton range during treatment. Simulations and detections were performed by Geant4 toolkit that was developed base on Monte Carlo method. First, a mono-energetic proton beams irradiated a homogeneous water phantom. Then the factors influencing the accuracy of beam range estimation have been investigated and finally proton beam range was evaluated by simulation the human eye phantom. According to the results, the accuracy of range verification by prompt gamma is very high, about 1 mm. In phantoms with more oxygen in their composition, the percentage of... 

    Quantitative Analysis of Elements by Scintillation Detectors Using Whole Information of Gamma-Ray Spectrum

    , Ph.D. Dissertation Sharif University of Technology Shahabinejad, Hadi (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Scintillation detectors are categorized as low energy resolution detectors in the classification of energy-sensitive detectors. The presence of broad peaks in the gamma-ray spectra of these detectors increases the overlapping probability of photopeaks of different isotopes and makes it extremely difficult to identify the spectra. The common method for identifying and quantifying of elements in a sample using nuclear spectroscopy is to use photopeak counts obtained with high-energy resolution detectors such as semiconductor detectors. To deal with the low energy resolution of scintillation detectors in quantitative analysis, the whole information of gamma-ray spectra is used instead of using... 

    A Monte Carlo Method for Neutron Noise Calculation in the Frequency Domain

    , M.Sc. Thesis Sharif University of Technology Ghorbani Ashraf, Mahdi (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Neutron noise equations, which are obtained by assuming small perturbations of macroscopic cross sections around a steady-state neutron field and by subsequently taking the Fourier transform in the frequency domain, have been usually solved by analytical techniques or by resorting to diffusion theory, but in this thesis, in order to increase of accuracy of neutron noise calculation, has been used transport approximation for neutron noise calculation and the Monte Carlo method has been used to solve transport equation of the neutron noise in the frequency domain. Since the transport equation of the neutron noise is a complex equation, a new Monte Carlo technique for treating complex-valued... 

    Investigation of the Optimum Conditions for the Regeneration of Anion and Cation Exchange Resins of the TR System of Bushehr Nuclear Power Plant

    , M.Sc. Thesis Sharif University of Technology Arkannia, Mohammad Hossein (Author) ; Outokesh, Mohammad (Supervisor) ; Seyed Kalal, Hossein (Supervisor) ; Habibian, Alireza (Co-Supervisor)
    Abstract
    The main purpose of this research is to select a suitable solution for regeneration of ion exchange resins of TR system of Bushehr nuclear power plant and also to compare and evaluate the possibility of using industrial cationic resin (Amberlite IR120) instead of nuclear grade cationic resin (Amberlite IRN97).First, different solutions for regeneration of cationic resins were investigated. For this purpose, three strong acids including hydrochloric acid (HCl), sulfuric acid (H2SO4) and nitric acid (HNO3) were selected and each of these acids was tested in two different concentrations and two different linear velocities; Also, to evaluate the appropriate solution for anionic resin...