Reactivity Calibrator

Vasilenko, V. A.; Pankin, A.M.; Skvortsov, K. V.

doi:10.1007/s10512-018-00459-0

Cited by 3 publications

(2 citation statements)

References 1 publication

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“…This method is commonly employed in computer-based simulations and facilitates the development of digital reactivity meters. To apply this model, the neutron density is required as an input, which can be measured using devices like ionization chambers (Vasilenko, Pankin, and Skvortsov, 2019). Studies that take this perspective are being conducted in the context of the decommissioning of the Fukushima Daiichi nuclear power plant.…”

Section: Introductionmentioning

confidence: 99%

Nuclear Reactivity Calculation with Reduction of Fluctuations

Suescún-Díaz¹,

Ule-Duque²,

Chala-Casanova³

2023

IJTech

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This article presents a study based on a series of numerical experiments. It demonstrates the possibility of reducing fluctuations in the calculation of reactivity using the second Bernoulli number based on the approximation of the Euler-Maclaurin formula. This approach requires knowledge of the first three derivatives, which are implemented progressively. The fluctuations are assumed to occur around an average value of the neutron density with a Gaussian distribution. Jitter reduction is performed with a first-order delayed low-pass filter for different forms of neutron population density, with different time steps and with different filter constants. The numerical results show that the method can be used as a digital reactivity meter.

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Section: Introductionmentioning

confidence: 99%

Nuclear Reactivity Calculation with Reduction of Fluctuations

Suescún-Díaz¹,

Ule-Duque²,

Chala-Casanova³

2023

IJTech

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“…La reactividad nuclear es posiblemente el parámetro más esencial en los reactores nucleares. Existen técnicas experimentales para su cálculo o estimación, como, por ejemplo, los dispositivos electrónicos que utilizan los datos de las cámaras de ionización (Vasilenko et al, 2019); las técnicas Rossi-alpha y Feynman-alpha (Malkawi et al, 2021) empleadas en reactores en estados subcríticos y, en reactores de agua ligera es posible estimar valores de la reactividad, utilizando el período del reactor y la ecuación en horas (Jiang et al, 2022). Otro enfoque en el cálculo de la reactividad es el computacional, que se fundamenta en métodos numéricos que se utilizan ampliamente en una variedad de estudios, incluidos, por nombrar algunos, el comportamiento térmico en régimen transitorio de flujo de gas en redes de ductos, en presencia de varios tipos de componentes como válvulas, compresores, intercambiadores de calor y bifurcaciones (Ortega et al, 2009), la propagación de una fisura (Palma et al, 2010), en el proceso de mezclado metano-oxígeno para un sistema confinado con arreglo de chorros 4-Lug-Bolt bajo la influencia de la variación de presión (De la Cruz et al, 2015).…”

Section: Introductionunclassified

Reducción de ruido en el cálculo de la reactividad con filtro digital y cuadraturas de Gauss-Legendre

2022

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This study presents a method that applies the Gauss-Legendre quadrature to approximate the integral contained in the inverse equation of point kinetics for the calculation of nuclear reactivity. Fluctuations in a neutron population of a nuclear reactor are assumed to be multiplicative Gaussian white noise around the mean. A modified low-pass filter performs fluctuation reductions by considering a symmetrical sampling window for both low and high frequencies. Filter parameters such as the filter constant and the sampling window are optimized for different values of standard deviation. An error surface is estimated from differences between the analytical values and the numerical values of reactivity, which is minimized to determine optimal parameters. It is concluded that the method presented here can be considered as an alternative method to reduce fluctuations in the calculation of nuclear reactivity and can be implemented in a digital reactivity meter.

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Using Self-Powered Neutron Detectors to Monitor Neutron-Multiplying Characteristics of the Water-Water Power Reactor Core

Pankin,

Kostarev,

Kalyutik

et al. 2024

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A method is described for diagnosing the water-water power reactor core components using self-powered neutron detector (SPND) readings. Self-powered neutron detectors are part of the incore instrumentation system. The method monitors both the detector itself and fuel element. The paper’s authors suggest using both steady state and dynamic reactor core conditions for interpretation of SPND readings. Dynamic conditions can be used to determine the coefficients of neutron flux dynamics that are calculated by analogy with determination of reactivity values from output signals of ion chambers in the reactor control and protection system.

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Reactivity Calibrator

Cited by 3 publications

References 1 publication

Nuclear Reactivity Calculation with Reduction of Fluctuations

Nuclear Reactivity Calculation with Reduction of Fluctuations

Reducción de ruido en el cálculo de la reactividad con filtro digital y cuadraturas de Gauss-Legendre

Using Self-Powered Neutron Detectors to Monitor Neutron-Multiplying Characteristics of the Water-Water Power Reactor Core

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