Validation of a NaI(Tl) detector's model developed with MCNP-X code

Salgado, César Marques; Brandão, Luís Eduardo Barreira; Schirru, Roberto; Pereira, Cláubia; Conti, C.C.

doi:10.1016/j.pnucene.2012.03.006

Cited by 113 publications

(61 citation statements)

References 19 publications

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“…The accuracy of the simulation depends on the parameters like detector dimensions, geometrical arrangement and the physical composition of the sample [9]. For the present work, for modeling the NaI(Tl) detector, dimensions provided by the manufactures were considered for making input for the simulation.…”

Section: Simulation Methodologymentioning

confidence: 99%

Application of simulated standard spectra for the analysis of complex sample spectra from NaI(Tl) detectors

Anilkumar

Narayani

Verma

et al. 2014

J Radioanal Nucl Chem

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The most accurate method for the analysis of complex gamma ray spectra from scintillation detectors is least squares method. The major requirement of this method is individual standard spectra of all nuclides expected in the complex spectrum which is not possible and feasible for some nuclides. In the present work, an approach of using simulated standard spectrum of the radionuclides for the least squares analysis is studied. The paper describes the methodology used for the generation of simulated spectrum which is the main objective, and validation of results using standard sources in the Sodium Iodide (NaI(Tl)) based gamma ray spectrometer.

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Section: Simulation Methodologymentioning

confidence: 99%

Application of simulated standard spectra for the analysis of complex sample spectra from NaI(Tl) detectors

Anilkumar

Narayani

Verma

et al. 2014

J Radioanal Nucl Chem

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“…The response matrix is obtained by using Monte Carlo simulations of the energy deposition within the detector using the same methodology as in [5]. The experimental spectra have a Gaussian distribution shape for the photons energy lines.…”

Section: Notationsmentioning

confidence: 99%

Fast Computation of Pulse Height Spectra Using SGRD Code

Humbert

Méchitoua

2017

EPJ Web Conf.

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Abstract. SGRD (Spectroscopy, Gamma rays, Rapid, Deterministic) code is used for fast calculation of the gamma ray spectrum produced by a spherical shielded source and measured by a detector. The photon source lines originate from the radioactive decay of the unstable isotopes. The emission rate and spectrum of these primary sources are calculated using the DARWIN code. The leakage spectrum is separated in two parts, the uncollided component is transported by ray-tracing and the scattered component is calculated using a multigroup discrete ordinates method. The pulsed height spectrum is then simulated by folding the leakage spectrum with the detector response functions which are pre-calculated using MCNP5 code for each considered detector type. An application to the simulation of the gamma spectrum produced by a natural uranium ball coated with plexiglass and measured using a NaI detector is presented.

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“…The Monte Carlo technique is a widely used simulation tool for radiation transport, mainly in situations where measurements are inconvenient or impracticable. The Monte Carlo methods make it possible to calculate the response function for detectors with good accurate results [14,15]. Monte Carlo models of the detectors used in this work were constructed using the MCNP5 code [16,17].…”

Section: Performance Test Of Carborne Survey Equipmentmentioning

confidence: 99%