Evaluation the nonlinear response function of a 3×3in NaI scintillation detector for PGNAA applications

Hakimabad, Seyyed Hashem Miri; Panjeh, Hamed; Vejdani-Noghreiyan, Alireza

doi:10.1016/j.apradiso.2007.03.014

Cited by 37 publications

(14 citation statements)

References 22 publications

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“…Molecular effects and scattering treatment, S(α,β), were considered for neutrons below 4 keV (MTm card) in all calculations that included neutron transport. The neutron energy spectrum was simulated, according to the report by Kluge et al published in 1982 [37], and gamma rays of 241 Am-Be were chosen based on a previous study by Miri et al [38]. …”

Section: Methodsmentioning

confidence: 99%

“…Detector spectra were compared for photon energies lower than 7 MeV with statistical error of the order of about 5%, in most cases even less. To consider detector resolution, the initial responses of the MCNP calculation were broadened with a FT card together with the GEB (Gaussian Energy Broadening) option using appropriate indices of the experimentally applied detector [38]. …”

Section: Methodsmentioning

confidence: 99%

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Facility optimization to improve activation rate distributions during IVNAA

Khankook

Rafat-Motavalli

Hakimabad

2013

Journal of Radiation Research

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Currently, determination of body composition is the most useful method for distinguishing between certain diseases. The prompt-gamma in vivo neutron activation analysis (IVNAA) facility for non-destructive elemental analysis of the human body is the gold standard method for this type of analysis. In order to obtain accurate measurements using the IVNAA system, the activation probability in the body must be uniform. This can be difficult to achieve, as body shape and body composition affect the rate of activation. The aim of this study was to determine the optimum pre-moderator, in terms of material for attaining uniform activation probability with a CV value of about 10% and changing the collimator role to increase activation rate within the body. Such uniformity was obtained with a high thickness of paraffin pre-moderator, however, because of increasing secondary photon flux received by the detectors it was not an appropriate choice. Our final calculations indicated that using two paraffin slabs with a thickness of 3 cm as a pre-moderator, in the presence of 2 cm Bi on the collimator, achieves a satisfactory distribution of activation rate in the body.

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Section: Methodsmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

Facility optimization to improve activation rate distributions during IVNAA

Khankook

Rafat-Motavalli

Hakimabad

2013

Journal of Radiation Research

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“…However, in order to increase the counts number of the gamma ray, the thickness of the detector was set thicker than conventional instruments [5,9]. The distance between neutron source and the center of target was set at the 100 cm, and the distance between detector and target was defined as the 50 cm [9,27]. The neutron particle can induce the prompt gamma ray by the nuclear reaction with atoms.…”

Section: Theory and Simulationmentioning

confidence: 99%

Statistical analysis for discrimination of prompt gamma ray peak induced by high energy neutron: Monte Carlo simulation study

Yoon

Jung

Han

et al. 2014

J Radioanal Nucl Chem

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The purpose of this research is a statistical analysis for discrimination of prompt gamma ray peak induced by the 14.1 MeV neutron particles from spectra using Monte Carlo simulation. For the simulation, the information of 18 detector materials was used to simulate spectra by the neutron capture reaction. The discrimination of nine prompt gamma ray peaks from the simulation of each detector material was performed. We presented the several comparison indexes of energy resolution performance depending on the detector material using the simulation and statistics for the prompt gamma activation analysis.

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“…There are several methods of calculating response functions of detector. The methods can be experimental or computational 20,21 . The approach selected for this study was to determine the response function by Monte Carlo…”

Section: Gamma-ray Detector Selectionmentioning

confidence: 99%

A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

Navarro

2013

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Evaluation the nonlinear response function of a 3×3in NaI scintillation detector for PGNAA applications

Cited by 37 publications

References 22 publications

Facility optimization to improve activation rate distributions during IVNAA

Facility optimization to improve activation rate distributions during IVNAA

Statistical analysis for discrimination of prompt gamma ray peak induced by high energy neutron: Monte Carlo simulation study

A feasibility and optimization study to determine cooling time and burnup of advanced test reactor fuels using a nondestructive technique

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