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Lozano Parada, Jaime Humberto Suescún-Díaz, Daniel Rasero, Diego Universidad Autónoma de Occidente. Calle 25 115-85. Km 2 vía Cali-Jamundí 2019-11-25T19:45:26Z 2019-11-25T19:45:26Z 2019 0022-3131 http://hdl.handle.net/10614/11570 https://doi.org/10.1080/00223131.2019.1611502 A new method for calculating nuclear reactivity based on the Discrete Fourier Transform (DFT) – with two filters: a first-order delay low-pass filter and a Savitzky-Golay filter – is presented. The reactivity is calculated from an integrodifferential equation known as the inverse point kinetic equation, which contains the history of neutron population density. The new method can be understood as a convolution between the neutron population density signal and the response to the characteristic impulse of a linear system. The proposed method is based on the discrete Fourier transform (DFT) that performs a circular convolution. The fast Fourier transform algorithm (FFT) with the zero-padding technique is implemented to reduce the computational cost application/pdf 9 páginas eng Taylor and Francis Derechos Reservados - Universidad Autónoma de Occidente https://creativecommons.org/licenses/by-nc-nd/4.0/ info:eu-repo/semantics/openAccess Atribución-NoComercial-SinDerivadas 4.0 Internacional (CC BY-NC-ND 4.0) reponame:Repositorio Institucional UAO Novel fluctuation reduction procedure for nuclear reactivity calculations based on the discrete fourier transform method Artículo de revista http://purl.org/coar/resource_type/c_6501 Text info:eu-repo/semantics/article http://purl.org/redcol/resource_type/ARTREF info:eu-repo/semantics/publishedVersion Molecular dynamics Dinámica molecular Reactivity Nuclear power plant Nuclear reactor Numerical simulation 616 7 608 56 Suescún-Díaz, D., Lozano-Parada, J. H., & Rasero-Causil, D. A. (2019). Novel fluctuation reduction procedure for nuclear reactivity calculations based on the discrete fourier transform method. Journal of Nuclear Science and Technology, 56(7), 608-616 Journal of Nuclear Science and Technology [1] Shimazu Y, Nakano Y, Tahara Y, Okayama T. Development of a compact digital reactivity meter and a reactor physics data processor. Nucl Technol. 1987;77:247–254. [2] Ansari SA. Development of on-line reactivity meter for nuclear reactors. IEEE Trans Nucl Sci. 1991;38:946–952. [3] Binney SE, Bakir AIM. Design and development of a personal computer based reactivity meter for a nuclear reactor. Nucl Technol. 1989;85:12–21. [4] Hoogenboom JE, Van Der Sluijs AR. Neutron source strength determination for on-line reactivity measurements. Ann Nucl Energy. 1988;15:553–559. [5] Tamura S. Signal fluctuation and neutron source in inverse kinetics method for reactivity measurement in the sub-critical domain. J Nucl SciTechnol. 2003;40:153–157. [6] Suescún DD, Senra AM, Carvalho Da Silva F. Calculation of reactivity using a finite impulse response filter. Ann Nucl Energy. 2008;35:472–477. [7] Suescún DD, Senra AM. Finite difference with exponential filtering in the calculation of reactivity. Kerntechnik. 2010;75:210–213. [8] Malmir H, Vosoughi N. On-line reactivity calculation using Lagrange method. Ann Nucl Energy. 2013;62:463–467. [9] Suescún DD, Bonilla HFL, Figueroa JJH. Savitzky-Golay filter for reactivity calculation. J Nucl Sci Technol. 2016;53:944–950. [10] Suescún DD, Rasero CDA, Figueroa JJH. Adams-Bashforth-Moulton method with Savitzky-Golay filter to reduce reactivity fluctuations. Kerntechnik. 2017;82:674–677. [11] Duderstadt JJ, Hamilton LJ. Nuclear reactor analysis. New York (NY): Wiley; 1976. [12] Palma DAP, Martinez AS, Gonçalves AC. Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor. Ann Nucl Energy. 2009;36:1469–1471. [13] Haykin S, Veen BV. Signal and system. New York (NY): Wiley; 1999. [14] Diniz RPS, Da Silva BEA, Netto LS. Digital signal processing: system analysis and design. Cambridge: Cambridge University Press; 2010. [15] Kitano A, Itagaki M, Narita M. Memorial-indexbased inverse kinetics method for continuous measurement of reactivity and source strength. J Nucl Sci Technol. 2000;37:53–59. http://purl.org/coar/access_right/c_abf2 http://purl.org/coar/version/c_970fb48d4fbd8a85 Publicationopen.access