An optimized Monte Carlo (PENELOPE) code for the characterization of gel-layer detectors in radiotherapy

Castellano, G.; Brusa, D.; Carrara, M.; Gambarini, G.; Valente, M.

doi:10.1016/j.nima.2007.05.215

Cited by 9 publications

(9 citation statements)

References 6 publications

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“…PENELOPE has found different applications in the dosimetry field, both related to nuclear medicine and external beam radiation therapy. 28,29 ETRAN was developed at the National Bureau of Standards to simulate the transport of electrons and photons at low energies. It has been used mostly in topics related to electron radiation therapy.…”

Section: Discussionmentioning

confidence: 99%

Calculation of electron and isotopes dose point kernels with fluka Monte Carlo code for dosimetry in nuclear medicine therapy

et al. 2011

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Section: Discussionmentioning

confidence: 99%

Calculation of electron and isotopes dose point kernels with fluka Monte Carlo code for dosimetry in nuclear medicine therapy

et al. 2011

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“…Although only 1 % of the neutron capture reaction energy is transported by the Auger and IC electrons, which accounts for 79 keV out of 7.9 MeV reaction Q-value, the energy deposition rate of Gd is still 2.3 times higher than that of boron due to its much higher cross section. The theoretical yields of Auger electrons and characteristic X-rays during the atomic relaxation of an excited Gd atom are observed using the atomic relaxation database in PENELOPE code package (5) , and are presented in Figure 1, where their low-energy origins and main energy lines are shown. It is worth noting that the total number of prompt gamma rays from level transitions of daughter Gd nuclei after neutron capture is about 1543 (6) , some more favourable than others.…”

Section: Gadolinium Interaction With Neutronmentioning

confidence: 99%

Gamma-ray rejection, or detection, with gadolinium as a converter

Kandlakunta¹,

Cao²

2012

Radiation Protection Dosimetry

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Gadolinium is a competent neutron conversion material for neutron detection due to its extremely high neutron capture cross section. It differs from the other neutron reactive materials by emitting large amounts of low-energy electrons for the consequent signal generation in a detector. Such low-energy electrons, though abundant, are prone to be contaminated by internal and/or external gamma rays, such as the activated 43.0 keV K-X rays, given the high atomic number of gadolinium. While the 43.0 keV K-X ray ought to be rejected as it originates in part from the external gamma rays when neutron detection is concerned, the ability to separate this energy line from other signals points to a practical mode of gamma-ray detection by a thin-film semiconductor with gadolinium as a converter. In this paper, a gamma-ray discrimination scheme for neutron detection is studied, which also provides insight into gamma-ray detection with a small semiconductor device with gadolinium as a converter, in line with the same principle of isolating the K-X rays activated by high- or medium-energy gamma rays.

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“…The main code PENELOPE, constituting the basic core of the present software, is widely validated as well as often used in numerous international publications, which have demonstrated its reliability 26–31. To establish the feasibility and accuracy of the designed Monte Carlo subroutine devoted to conventional X‐ray tube spectra, computation has been suitably checked by means of performing several simulations corresponding to accelerating voltages in the range of 20–50 kV and comparing the obtained spectra with those provided by experimental data and/or validated methods like the XOP software.…”

Section: Resultsmentioning

confidence: 99%

X‐ray spectra by means of Monte Carlo simulations for imaging applications

Tirao¹,

Quintana²,

Malano³

et al. 2010

X-Ray Spectrometry

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X-ray tubes have a broad range of applications worldwide, including several techniques for atomic physics, like X-ray fluorescence, as well as for medical imaging, like computed tomography. The performances of X-ray imaging detectors have shown to be significantly sensitive to the incident beam spectrum. Therefore, an accurate knowledge of the X-ray beam becomes necessary for the emission source characterization and the whole imaging process comprehension. Direct measurements and suitable Monte Carlo simulations may be used to establish the X-ray spectra. Dedicated Monte Carlo simulation routines, based on the PENELOPE code, have been developed to determine the Bremsstrahlung X-ray spectra generated by conventional X-ray tubes. The simulated spectra have been validated by comparison with the corresponding experimental data showing an overall good agreement. The incorporation of a suitably designed virtual grid allowed to assess the angular distribution of Bremsstrahlung yield, showing a remarkable anisotropy. In addition, a dedicated program has been developed for virtual imaging, which enables to perform suitable X-ray absorption contrast images. Also, the developed program includes a user-friendly graphic interface to allow the upload of required input parameters, which include setup arrangement, beam characteristics, sample properties and image simulation parameters (spatial resolution, tracks per run, etc.). The software includes dedicated subroutines which handle the physical process from X-ray generation up to detector signal acquisition. The aim of the developed program is to perform virtual imaging by means of absorption contrast and using conventional X-ray sources, which may be a useful tool for the study the X-ray imaging techniques in several research fields as well as for educational purposes. The performed comparisons with experimental data have shown good agreement. The obtained results for X-ray imaging may constitute useful information for the comprehension and improvement of X-ray image quality, like absorption contrast optimization, detail visualization, definition and detectability.

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An optimized Monte Carlo (PENELOPE) code for the characterization of gel-layer detectors in radiotherapy

Cited by 9 publications

References 6 publications

Calculation of electron and isotopes dose point kernels with fluka Monte Carlo code for dosimetry in nuclear medicine therapy

Calculation of electron and isotopes dose point kernels with fluka Monte Carlo code for dosimetry in nuclear medicine therapy

Gamma-ray rejection, or detection, with gadolinium as a converter

X‐ray spectra by means of Monte Carlo simulations for imaging applications

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