Discrete Fourier Transform Method for Discrimination of Digital Scintillation Pulses in Mixed Neutron-Gamma Fields

Safari, M. J.; Davani, F. Abbasi; Afarideh, H.; Jamili, S.; Bayat, E.

doi:10.1109/tns.2016.2514400

Cited by 39 publications

(20 citation statements)

References 25 publications

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“…The rise time method and the discrete Fourier transform method can be applied as a pulse shape discrimination technique in the mixed neutron and gamma ray fields [15,16].…”

Section: Signal To Noise Discriminationmentioning

confidence: 99%

Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

et al. 2020

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This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken. A fission chamber neutron flux detection and instrumentation model were designed. Its accuracy was evaluated and proven by comparing the model data with data gathered from tests and plant operations. A conceptual design was proposed through a combined structure that digitalizes only part of the system. The detector signal pre-amplification remains in analog form while the other functions such as reactor power calculation as well as signal conditioning and processing will be digitalized. Simulations showed that the true mean squared voltage (MSV) of the digitalized ENFMS maintained a linear relationship between real and estimated reactor power in the wide range compared to averaged magnitude squared value of analog ENFMS. Extended Kalman Filter (EKF) was also utilized for estimating reactor power and reactor period from measurement signals that are contaminated with gamma ray interaction and electric noise. This study proved that the ENFMS can be successfully digitalized as proposed wherein all functional and performance requirements are satisfied. Simulations results demonstrated that the functions and performance can be improved through the use of digital processing algorithms such as EKF and MSV.

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“…The rise time method and the discrete Fourier transform method can be applied as a pulse shape discrimination technique in the mixed neutron and gamma ray fields [15,16].…”

Section: Signal To Noise Discriminationmentioning

confidence: 99%

Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

et al. 2020

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“…A large number of digital PSD algorithms have been proposed for the discrimination of fast neutrons against γ-rays in liquid scintillation detectors. Some of these algorithms include the digital versions of the classic analog chargecomparison and the zero-crossing methods [33,34], pulse gradient analysis [35] and frequency domain methods [7][8][9]. There have been also some efforts on the utilization of machine learning methods including artificial neural networks [36], support vector machine [37], Bayes' theorem [38] and fuzzy cmeans [39].…”

Section: B Liquid Scintillation Detectormentioning

confidence: 99%

“…An advantage of digital systems is the possibility of multifunction operation that allows building a single versatile pulse processing module for extracting PSD information along with energy and timing information from a wide range of radiation detectors. However, while rather general-purpose algorithms for energy and timing measurements are available, the reported PSD algorithms that rely on the capabilities of digital realm, such as frequency analysis methods [7][8][9], least-square methods [10][11][12] and pattern recognition methods [13][14][15], need to be tailored to the characteristics of the concerned detectors. In this paper, we report on a high-performance and general-purpose digital PSD algorithm that with minimum alterations can be used with a wide range of radiation detectors.…”

mentioning

confidence: 99%

A General-Purpose Digital Pulse Shape Discrimination Algorithm

Nakhostin

2019

IEEE Trans. Nucl. Sci.

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Digital pulse-shape discrimination (PSD) systems are widely used to extract various kinds of information from the shape of output pulses of radiation detectors. Such systems replace the traditional analog PSD circuits with numerical algorithms running on a digital processor which makes them more flexible for implementing various PSD methods. However, the available digital PSD algorithms have been generally tailored to the characteristics of the concerned detectors which limits their general use. Here, for the purpose of building a general-purpose digital PSD module, we present a PSD algorithm that with minimum alterations can be used with a wide range of radiation detectors. Our approach is based on using the cosine similarity measure to quantify the variations in the shape of detectors' pulses with respect to the shape of a unit step pulse. The method is described in details, and the results of the test experiments with different types of radiation detectors, including a boron tetrafluoride (BF3) proportional counter, a liquid scintillation detector, and a high purity germanium (HPGe) detector are shown. The performance of the algorithm is also compared to that of the common rise-time discrimination method.

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“…Many PSD algorithms have been evaluated and reported, such as zero-crossing (ZC) [6][7][8], PGA [9], CC [6][7][8][9][10][11], frequency gradient analysis (FGA) [5], TCT [12], discrete Fourier transform (DFT) [13], CPR [14], etc. Among them, the CC and ZC algorithms are commonly implemented, therefore they have become the industrial standards which are used to compare with new discrimination algorithms [5,6].…”

Section: Introductionmentioning

confidence: 99%

Manufacture of a fast neutron detector using EJ-301 liquid scintillator

Phan¹,

Nguyen²,

Nguyen³

et al. 2019

Sci. Tech. Dev. J. - Nat. Sci.

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A fast neutron detector using the EJ- 301 scintillator was manufactured for study on detecting fast neutrons and gamma-rays. Detector characteristics include the energy linearity, the efficiency response and the neutron/gamma discrimination were guaranteed for neutron detection in the energy range from 50 to 3000 keVee. The ability discrimination of neutrons/gamma-rays of the detector was evaluated by the charge comparison (CC) method using an 252Cf source. The total efficiencies when measured on 22Na, 137Cs, 60Co and 252Cf sources were obtained 17.8%, 3.9%, 9.8% and 14.8%, respectively. The Figure of Merit (FoM) values of CC method were 0.4–1.55 for the range of energy 50–1000 keVee (keV electron equivalent).

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Discrete Fourier Transform Method for Discrimination of Digital Scintillation Pulses in Mixed Neutron-Gamma Fields

Cited by 39 publications

References 25 publications

Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant

A General-Purpose Digital Pulse Shape Discrimination Algorithm

Manufacture of a fast neutron detector using EJ-301 liquid scintillator

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