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Total 139 records

    Source Tracing of the Dust Storms to the Country Using the Nuclear Techniques

    , M.Sc. Thesis Sharif University of Technology Bagri, Mohammad (Author) ; Sohrabpour, Mostafa (Supervisor) ; Hosseini, Abolfazl (Co-Advisor)
    Abstract
    Dust phenomenon is a combination of tiny particle with urban pollution that it is harmful for respiratory disease. But this phenomenon has been prevalent in our country recently. We utilized NASA satellite pictures to observe dust storms in the present project. We have collected images of possible sources of dust on the days when we are faced with the dust storm phenomenon. Then by processing of NASA satellite pictures (recognition of distribution of optical and particle density in the dust particle arising and comparing results through analysis of these images to estimate the main characteristics of the sampling locations). we have find the desired location for taking samples of soil... 

    Cross-Matching of OGLE and Gaia catalogues: Investigation of Dark-lens microlensing candidates

    , M.Sc. Thesis Sharif University of Technology Dehghanizadeh, Amir Hossein (Author) ; Rahvar, Sohrab (Supervisor)
    Abstract
    Discovery of the effect of a massive object on the light path, reaching its exact formalism through general relativity and utilizing this phenomenon as a natural lens, opened a new window in astronomical research. Gravitational lensing occurs in three different ways; strong lensing, weak lensing, and microlensing which we focus on the third one. Gravitational microlensing is useful in studying dark matter candidates, discovering exoplanets, finding the surface properties of stars, and calculating the mass distribution of galactic objects. From a typical microlensing event, Einstein crossing time is obtained which is the time scale of source star passing by the lens. This is the only... 

    Neutronic and Thermal-Hydraulic Coupling in time domain and Feasibility Study of its Application in Accident Prediction

    , M.Sc. Thesis Sharif University of Technology Abbasi Fashami, Sajjad (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Analysis of neutronic and thermal-hydraulics fluctuations has various applications in calculation or measurement of the core dynamical parameters (temperature reactivity coefficients) furthermore it is applicable in thermal-hydraulics surveillance and diagnostics. Experience of the Fukushima Dai-ichi plant and the lessons learned from the European stress tests, demonstrated that alternative and various tools and methods are needed for the reactor's condition identification. In this paper the feasibility of development of an alternative accident monitoring via eminent coupling of neutron and thermal-hydraulics noise is proposed. and it is programming a simple simulator for calculating... 

    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... 

    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... 

    Neutron Noise Calculation Using High order Nodal Expansion Method

    , M.Sc. Thesis Sharif University of Technology Kolali, Ali (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    This study consists of two parts: steady state calculations and neutron noise calculations in the frequency domain for two rectangular and hexagonal geometries. In the steady state calculation, the neutron diffusion and its adjoint equations are approximated by two-dimensional coordinates in two-group energy and are solved using the average current nodal expansion method. Then, by considering the node size in the dimensions of a fuel assembly, different orders of flux expansion are investigated. For verification purposes, the calculations have been performed by power iteration method for two test problems of BIBLIS-2D and IAEA-2D. For rectangular geometry with increasing flux expansion order... 

    Design and Construction of PE/W/LiF Composites as the Shield of Neutron-gamma in Mixed Fields

    , M.Sc. Thesis Sharif University of Technology Mirazimi, Samaneh (Author) ; Vossoughi, Nasser (Supervisor) ; Asadi, Skandar (Co-Advisor)
    Abstract
    In a nuclear reaction, particles such as gamma, neutron, alpha beta, etc. May be emitted. Environment and humans could be damaged severely if these radiations are not properly shielded. One of the main goals of this project is manufacture proper shields for neutron and gamma attenuation and absorption in mixed fields, benefiting the particular properties of composites. In preliminary stage of this project, with comprehensive studies, primary materials were selected. These materials are Tungsten, Polyethylene and Lithium Fluoride selected as Gamma absorber, thermalizer and thermalized neutron absorber respectively. In the next step, weight fractions of each material and thicknesses of... 

    Design and Construction of a Neutron Porosity Probe and Comparison of its Experimental Measurement with MCNP Simulation Results

    , M.Sc. Thesis Sharif University of Technology Valadi, Ahmad (Author) ; SohrabPour, Mostafa (Supervisor)
    Abstract
    Today the hydrocarbon materials rank in the list of requirements of the modern societies. The increased growth of the human population, their industrial economic activities, transportation etc. requires sufficient supplies of our resources. Therefore, the hydrocarbon resources need to be discovered and evaluated accurately. There are different methods that are used to measure underground hydrocarbon resources such as well logging. In this method, a measuring device is lowered into a well to evaluate several parameter of the surrounding soil. Nuclear well logging is a sub category of well logging that uses nuclear rays to do this measurement. This method has different types of sondes which... 

    Design of Neutron Radiography System Based on the Time of Flight Method Using GEANT4 Software

    , M.Sc. Thesis Sharif University of Technology Vahidian, Mohamad (Author) ; Hosseini, Abolfazl (Supervisor) ; Mehrabi, Mohammad (Co-Supervisor)
    Abstract
    Neutron Radiography is one of the non-destructive testing methods of materials and due to its special application compared to gamma or X-ray imaging, it is highly regarded and developed in the world. A special application of neutron imaging is the imaging of materials with a low atomic number, even when coated with a material with a high atomic number. Neutron Radiography has different methods for capturing and recording images by neutrons. Among these methods, the following 7 methods can be mentioned: Neutron radiography (film), Track Etch, Digital neutron imaging, Neutron camera (DR System), Image plates (CR System), Flat panel silicon detectors (DR system) and Micro channel plates (DR... 

    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... 

    Simulation and Optimization of the Neutron Velocity Selector

    , M.Sc. Thesis Sharif University of Technology Moeini Roodbally, Hamed (Author) ; Hosseini, Abolfazl (Supervisor)
    Abstract
    To study the structure of materials, among materials containing hydrogen, an instrument called the "small-angle neutron scattering instrument" is used. Having a monochromatic neutron beam is the most basic component of this instrument. This beam is often produced using a device called the "neutron velocity selector". The neutron velocity selector is a rotating mechanical piece that allows for passage of neutrons at a certain speed, according to its rotational speed. In fact, this device produces a monochromatic neutron beam with continuous flux. Until now, it has been designed and manufactured in a variety of models, which are generally divided into two groups of multi-disc and multi-blade... 

    Simulation and Optimization of Neutron Activation Analysis Using the K0- IAEA Software and Comparison with the Experimental Results

    , M.Sc. Thesis Sharif University of Technology Sattari Heris, Aghil (Author) ; Vossoughi, Naser (Supervisor) ; Hosseini, Abolfazl (Supervisor)
    Abstract
    Neutron activation is a nuclear method for determination of elements in each sample. In this method, the samples are exposed to neutron irradiation by neutrons which are usually produced by research reactor, and then the core becomes unstable due to capturing the neutron and emits gamma rays. The emitted gamma rays can be detected by a detector like a HPGe semiconductor which has a high resolution. All nucleuses have a probability of neutron absorption, expressed by the absorption cross section area. The radioactive nuclei value depends on the nuclear half-life and the number of unstable nuclei. The only Windows environment commercial software for neutron activation analysis was K0 for... 

    (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... 

    Mass-Radius Relation for a Rotating and Magnetized Neutron Star Using the Nambu-Jona-Lasinio Model

    , M.Sc. Thesis Sharif University of Technology Saⅾeghi, Ⅿohaⅿⅿaⅾ Sharif (Author) ; Sadooghi, Neda (Supervisor)
    Abstract
    One of the most essential concepts for describing neutron stars is investigating their radial mass distribution or mass-radius relation. The aim of this thesis is to evaluate radial mass distribution of neutron stars in the presence of magnetic fields. To achieve this objective we use the Tolman- Oppenheimer-Volkoff equation of hydrostatic equilibrium for non-rotating cases and the Hartle- Thorne equations for rotating cases. olving these equations depends on determination of equation of state of neutron star in the presence of magnetic fields. For determining the corresponding equation of state, one can use QCD-like non-perturbative models, in particular Nambu-Jona- Lasinio (NJL) model. In... 

    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... 

    Neutron Noise Calculation using Nodal Expansion Method

    , M.Sc. Thesis Sharif University of Technology Vosoughi, Javad (Author) ; Vosoughi, Naser (Supervisor) ; Hosseini, Abolfazl (Co-Advisor)
    Abstract
    The present M.Sc. thesis consists of two sections including the static calculation and neutron noise calculation in rectangular and hexagonal geometries. The multi-group, two dimensional neutron diffusion equations and corresponding adjoint equations are solved in the static calculation. The spatial discretization of equations is based on Average Current Nodal Expansion Method (ACNEM). Size of nodes is the same size of the fuel assemblies in modeling both of rectangular and hexagonal geometries. The results are benchmarked against the valid results for BIBLIS-2D and IAEA-2D benchmark problems. In the second section, neutron noise calculations are performed for two types of noise sources,... 

    Discrimination of Neutron and Gamma Spectrum Using a Method Based on Digital Filters

    , M.Sc. Thesis Sharif University of Technology Valipour, Mahdi (Author) ; Hosseini, Abolfazl (Supervisor)
    Abstract
    Since the beginning of discussion on neutron-gamma discrimination, different methods were suggested for this purpose. In early 2000s, Analogue methods were mainly used to discriminate the spectrum in mixed fields which mostly depends on electronic modules used in the lab setup; Nowadays, with improvements in digital pulse processing techniques, analyzing mixed neutron-gamma fields for pulse discrimination is also available.In this research, the recent MC developed toolkit called GEANT4 is used to simulate the 3-inch BC501A scintillation detector and 500 mCi Am-Be source (that emits neutron and gamma at the same time). For the next step, an experiment with same source and detector was done... 

    Production of New Nanocomposites for Neutron and Gamma Shielding and Modeling of the Attenuation Phenomena Using Computational Methods

    , M.Sc. Thesis Sharif University of Technology Safavi, Mohammad Reza (Author) ; Outokesh, Mohammad (Supervisor) ; Vosoughi, Naser (Supervisor) ; Kiani, Mohammad Amin (Co-Supervisor)
    Abstract
    If nuclear radiation is not weakened and absorbed, it can cause serious damage to human devices or the environment. Dual-purpose dry casks are one of the sources of nuclear radiation production as a place to keep the spent fuel assemblies. One of the ways to protect against them is to use shield. One of the most common of them is composite shield. The composite used in this study has a polymer matrix. The matrix of the used polymer is epoxy resin. In this study, two separate composites have been made to attenuate neutron and gamma radiation. In this thesis, first, by using the MCNPX code, the necessary simulations for the design and construction of composite shields have been carried out.... 

    Accurate Generation of Scintillator Detector Energy Spectrum by Monte Carlo Method for Gamma-Ray Spectrum Analysis Using whole Spectrum Data

    , M.Sc. Thesis Sharif University of Technology Ahmadi, Donya (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    Generating the experimental spectrum for all gamma-ray elements is difficult and practically impossible in some industrial applications. Furthermore, in many applications such as neutron activation, it is not possible to obtain an experimental spectrum for a single isotope on account of the fact that the gamma-ray spectrum obtained from neutron activation is derived from the gamma-rays of various elements in a sample. Therefore, using computational techniques like Monte Carlo method for calculating the detector response functions seems an appropriate solution. The detector response functions for 3''×3'' NaI detectors have been simulated using MCNPX 2.7 code and Ptrac card in this project....