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    On the limitations of linear power reactor noise analysis: A point kinetics approach

    , Article Annals of Nuclear Energy ; Volume 102 , 2017 , Pages 124-133 ; 03064549 (ISSN) Ayyoubzadeh, S. M ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2017
    Abstract
    A novel method is introduced which allows the higher order perturbative solution of a linear operator with a time variant coefficient. This method employs a form of raising and lowering operators which generate higher and lower order harmonics from a given harmonic. The analysis has been applied to the point kinetics equations with a monotone oscillatory reactivity to place bounds on the relative error of the linearization method frequently employed in the power reactor noise techniques. As a result, the maximum permissible reactivity amplitude for a given reactor as a function of frequency has been obtained such that regular power reactor noise methods remain accurate enough. Three... 

    A new approach for calculation of the neutron noise of power reactor based on Telegrapher's theory: Theoretical and comparison study between Telegrapher's and diffusion noise

    , Article Nuclear Engineering and Technology ; Volume 52, Issue 4 , 2020 , Pages 681-688 Bahrami, M ; Vosoughi, N ; Sharif University of Technology
    Korean Nuclear Society  2020
    Abstract
    The telegrapher's theory was used to develop a new formulation for the neutron noise equation. Telegrapher's equation is supposed to demonstrate a more realistic approximation for neutron transport phenomena, especially in comparison to the diffusion theory. The physics behind such equation implies that the signal propagation speed is finite, instead of the infinite as in the case of ordinary diffusion. This paper presents the theory and results of the development of a new method for calculation of the neutron noise using the telegrapher's equation as its basis. In order to investigate the differences and strengths of the new method against the diffusion based neutron noise, a comparison was... 

    Development of an embedded FPGA-based data acquisition system dedicated to zero power reactor noise experiments

    , Article Metrology and Measurement Systems ; Vol. 21, issue. 3 , Aug , 2014 , p. 433-446 ; 08608229 Arkani, M ; Khalafi, H ; Vosoughi, N ; Sharif University of Technology
    Abstract
    An embedded time interval data acquisition system (DAS) is developed for zero power reactor (ZPR) noise experiments. The system is capable of measuring the correlation or probability distribution of a random process. The design is totally implemented on a single Field Programmable Gate Array (FPGA). The architecture is tested on different FPGA platforms with different speed grades and hardware resources. Generic experimental values for time resolution and inter-event dead time of the system are 2.22 ns and 6.67 ns respectively. The DAS can record around 48-bit × 790 kS/s utilizing its built-in fast memory. The system can measure very long time intervals due to its 48-bit timing structure... 

    SN transport method for neutronic noise calculation in nuclear reactor systems: comparative study between transport theory and diffusion theory

    , Article Annals of Nuclear Energy ; Volume 114 , 2018 , Pages 236-244 ; 03064549 (ISSN) Bahrami, M ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2018
    Abstract
    In this paper, the neutron noise based on transport theory and diffusion noise theory using Green's function technique is calculated. As the neutron noise is used for core diagnostic, surveillance and monitoring, calculation of neutron noise precisely can play an important role in monitoring and safety. We compare the accuracy of Green's function based on transport and diffusion theory in order to survey the differences between these theories. In this study some deviation between results obtained two theories are observed, and the impact of dimensions, cross sections and frequency on the results investigated. © 2017  

    Application of minimum plutonium criteria at EOC to optimize the fuel loading pattern in VVER-1000 reactors

    , Article Annals of Nuclear Energy ; Volume 35, Issue 2 , 2008 , Pages 269-276 ; 03064549 (ISSN) Mohseni, N ; Boroushaki, M ; Ghofrani, M. B ; Raji, M. H ; Sharif University of Technology
    2008
    Abstract
    Most of the strategies yet implemented to optimal fuel loading pattern design in nuclear power reactors, are based on maximizing the core effective multiplication factor (Keff) to extract maximum energy and lowering the local power peaking factor (Pq) from a predetermined value. However, a new optimization criterion could be of interest, aiming at maximum burn-up of the plutonium content in fuel assemblies, i.e., minimization of remaining plutonium in spent fuel at the end of cycle (EOC). In this research, we developed a new strategy for optimal fuel core loading pattern of a VVER-1000 reactor, based on multi-objective optimization: lowering the Pq, maximization of the Keff and minimization... 

    Development and experimental validation of a correlation monitor tool based on the endogenous pulsed neutron source technique

    , Article Metrology and Measurement Systems ; Volume 24, Issue 3 , 2017 , Pages 441-461 ; 20809050 (ISSN) Arkani, M ; Khalafi, H ; Vosoughi, N ; Khakshournia, S ; Sharif University of Technology
    Abstract
    A correlation measuring tool for an endogenous pulsed neutron source experiment is developed in this work. Paroxysmal pulses generated by a bursts of neutron chains are detected by a 10-kbit embedded shift register with a time resolution of 100 ns. The system is implemented on a single reprogrammable device making it a compact, cost-effective instrument, easily adaptable for any case study. The system was verified experimentally in the Esfahan heavy-water zero power reactor (EHWZPR). The results obtained by the measuring tool are validated by the Feynman-α experiment, and a good agreement is seen within the boundaries of statistical uncertainties. The theory of the methods is briefly... 

    Higher order power reactor noise analysis: the multigroup diffusion model

    , Article Annals of Nuclear Energy ; Volume 111 , 2018 , Pages 354-370 ; 03064549 (ISSN) Ayyoubzadeh, M ; Hosseini, A ; Vosoughi, N ; Sharif University of Technology
    Elsevier Ltd  2018
    Abstract
    Power reactor noise analysis is one of the most powerful tools in online monitoring and diagnostics of nuclear power reactors. Unfortunately, since such an analysis belongs to the non-linear “parametric excitation” realm, its theoretical aspects and relations have been mostly carried out after linearization. In this paper a general framework, i.e. the Ladder Expansion Method, is developed to convert such equations to a series of coupled linear equations, up to any desired accuracy. This method is then applied to the single mode random fluctuations of the absorption cross sections in a power reactor which is modelled by the multigroup diffusion equation with multiple delayed neutron groups. A... 

    Kinetic parameters evaluation of PWRs using static cell and core calculation codes

    , Article Annals of Nuclear Energy ; Volume 41 , 2012 , Pages 110-114 ; 03064549 (ISSN) Jahanbin, A ; Malmir, H ; Sharif University of Technology
    Abstract
    In this paper, evaluation of the kinetic parameters (effective delayed neutron fraction and prompt neutron lifetime) in PWRs, using static cell and core calculation codes, is reported. A new software has been developed to link the WIMS, BORGES and CITATION codes in Visual C# computer programming language. Using the WIMS cell calculation code, multigroup microscopic cross-sections and number densities of different materials can be generated in a binary file. By the use of BORGES code, these binary-form cross-sections and number densities are converted to a format readable by the CITATION core calculation code, by which the kinetic parameters can be finally obtained. This software is used for... 

    A FPGA based time analyser for stochastic methods in experimental physics

    , Article Instruments and Experimental Techniques ; Volume 58, Issue 3 , May , 2015 , Pages 350-358 ; 00204412 (ISSN) Arkani, M ; Khalafi, H ; Vosoughi, N ; Khakshournia, S ; Sharif University of Technology
    Maik Nauka Publishing / Springer SBM  2015
    Abstract
    A two-channel time analyser data acquisition system is developed for analysis of stochastic processes of random time interval pulses. The system is implemented on a typical low cost FPGA device. Two stochastic processes of nuclear interactions can be recorded by the system independently without any inter-channel dead time behaviour. The experimental results without any hardware based data reduction are transferred to the computer to perform arbitrary post analysis of the data using powerful software engineering tools to estimate the statistical properties of the processes. The performance of the system is verified experimentally. The maximum time digitization period and the minimum channel... 

    Simulation of Power Reactor Noise Based on Transport Equation

    , Ph.D. Dissertation Sharif University of Technology Bahrami, Mona (Author) ; Vosoughi, Naser (Supervisor)
    Abstract
    In every nuclear reactor core, there are neutron flux fluctuations around the mean value. The neutron noise is the deviation between the time-dependent neutron flux and its expected value, assuming that all process is stationary and ergodic in time. These fluctuations can be caused by the stochastic nature of neutron interactions or mechanical oscillations in the reactor cores. In a reactor working at a high-power level, mechanical fluctuations are the major cause of the fluctuations measured by the detectors. These mechanical vibrations include control rod or fuel rod vibrations, changes in the incoming coolant speed, or changes in the coolant temperature. These perturbations are seen as... 

    Optimization of fuel core loading pattern design in a VVER nuclear power reactors using Particle Swarm Optimization (PSO)

    , Article Annals of Nuclear Energy ; Volume 36, Issue 7 , 2009 , Pages 923-930 ; 03064549 (ISSN) Babazadeh, D ; Boroushaki, M ; Lucas, C ; Sharif University of Technology
    2009
    Abstract
    The two main goals in core fuel loading pattern design optimization are maximizing the core effective multiplication factor (Keff) in order to extract the maximum energy, and keeping the local power peaking factor (Pq) lower than a predetermined value to maintain fuel integrity. In this research, a new strategy based on Particle Swarm Optimization (PSO) algorithm has been developed to optimize the fuel core loading pattern in a typical VVER. The PSO algorithm presents a simple social model by inspiration from bird collective behavior in finding food. A modified version of PSO algorithm for discrete variables has been developed and implemented successfully for the multi-objective optimization...