PENELOPE-2008 Monte Carlo simulation of gamma exposure induced by 60Co and NORM-radionuclides in closed geometries

Merk, Rainer; Kröger, H.; Edelhäuser-Hornung, L.; Hoffmann, B.

doi:10.1016/j.apradiso.2013.07.006

Cited by 6 publications

(4 citation statements)

References 13 publications

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“…Then, the collisional kerma is derived for each voxel using the Linear Track Length Estimator (LTLE), calculating the energy fluence and folding it into the material and energy dependent energy absorption cross‐section. Details of the different implementations and use of geometric modeling, physics models, photon spectrum, interaction cross‐sections, and tracking methods for photon transport have been extensively discussed for each MC code elsewhere …”

Section: Methodsmentioning

confidence: 99%

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy

Vijande

Ballester

et al. 2017

Medical Physics

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Section: Methodsmentioning

confidence: 99%

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy

Vijande

Ballester

et al. 2017

Medical Physics

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“…The several geometries used are constructed from quadratic surfaces, and variance reduction techniques are incorporated to have better adaptability and greater precision. [ 30 33 36 47 48 ] PENELOPE allows creating materials with a single component, alloys, or mixed materials that are present in the constitution of a clinical linear accelerator. All these help to make better reproductions and representations of experimental conditions.…”

Section: Aterials and M Ethodsmentioning

confidence: 99%

“…It has extensive information on various applications for radiotherapy and radiodiagnosis. [ 4 29 30 31 32 33 34 ] Since its first version launched in 1996, the MCS PENELOPE code has become a flexible and reliable tool to describe the coupled transport of photons and electrons in complex material structures,[ 35 36 ] presenting simplicity and versatility to be used in the two most used programming platforms such as Windows and Linux without the necessity of the usage of an intermediary interface. Moreover, the results obtained are presented in .dat extension which is easy to read in any code for statistical analysis such as Origin, Matlab, and Gnuplot.…”

Section: Introductionmentioning

confidence: 99%

Monte carlo calculation of the energy spectrum of a 6 MeV electron beam using penetration and energy loss of positrons and electrons code

et al. 2020

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Background: The limited bibliographic existence of research works on the use of Monte Carlo simulation to determine the energy spectra of electron beams compared to the information available regarding photon beams is a scientific task that should be resolved. Aims: In this work, Monte Carlo simulation was performed through the PENELOPE code of the Sinergy Elekta accelerator head to obtain the spectrum of a 6 MeV electron beam and its characteristic dosimetric parameters. Materials and Methods: The central-axis energy spectrum and the percentage depth dose curve of a 6 MeV electron beam of an Elekta Synergy linear accelerator were obtained by using Monte Carlo PENELOPE code v2014. For this, the linear accelerator head geometry, electron applicators, and water phantom were simplified. Subsequently, the interaction process between the electron beam and head components was simulated in a time of 86.4x10 4 s. Results: From this simulation, the energy spectrum at the linear accelerator exit window and the surface of the phantom was obtained, as well as the associated percentage depth dose curves. The validation of the Monte Carlo simulation was performed by comparing the simulated and the measured percentage depth dose curves via the gamma index criterion. Measured percentage depth- dose was determined by using a Markus electron ionization chamber, type T23343. Characteristic parameters of the beam related with the PDD curves such as the maximum dose depth (R 100 ), 90% dose depth (R 90 ), 90% dose depth or therapeutic range (R 85 ), half dose depth (R 50 ), practical range (R p ), maximum range (R max ), surface dose (D s ), normalized dose gradient (G 0 ) and photon contamination dose (D x ) were determined. Parameters related with the energy spectrum, namely, the most probable energy of electrons at the surface (E p,0 ) and electron average energy ( E – 0 ) were also determined. Conclusion: It was demonstrated that PENELOPE is an attractive and accurate tool for the obtaining of dosimetric parameters of a medical linear accelerator since it can reliably reproduce important clinical data such as the energy spectrum, depth dose, and dose profile.

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“…Consequently, this is considered as a radioactive waste. To evaluate the radiation safety due to the nuclear interactions, one of the best ways is the use of Monte Carlo simulation [2][3][4]. According to Monte Carlo approach, statistical processing time is prolonged at 13 hrs partly due to the complex geometry design [5,6].…”

Section: Introductionmentioning

confidence: 99%

Calculation of Lead-Iron Double-Layer Thickness for Gamma-Ray Shielding by MATLAB Program

Lekchaum

Locharoenrat

2017

Science and Technology of Nuclear Installations

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This contribution is aimed at designing the optimal thickness of lead-iron double-layer container to store a radioactive waste releasing the photon energy at 1.3325 MeV and initial radiation intensity at 100 mSv/hr using the optimization design by MATLAB software. This design consisted of three parts of calculations to achieve 1000 times the radiation attenuation of container. The first was the logarithmic interpolation for the mass attenuation coefficient. The second was the bilogarithmic interpolation for the exposure buildup factor. The third was the contour-plotting analytical technique for the optimal thickness of radiation container. The values of mass attenuation coefficient and exposure buildup factor were exactly validated as compared with the standard reference database. Furthermore, we have found that the optimal thickness was 3.2 cm for lead (1st layer) and 17.0 cm for iron (2nd layer). Container weight was 994.30 kg, whilst container cost was 167.30 USD. The benefit of our design can quickly and precisely apply for the radiation safety assessment of the occupational radiation workers who always work in the nuclear reactor area.

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PENELOPE-2008 Monte Carlo simulation of gamma exposure induced by 60Co and NORM-radionuclides in closed geometries

Cited by 6 publications

References 13 publications

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy

Monte carlo calculation of the energy spectrum of a 6 MeV electron beam using penetration and energy loss of positrons and electrons code

Calculation of Lead-Iron Double-Layer Thickness for Gamma-Ray Shielding by MATLAB Program

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PENELOPE-2008 Monte Carlo simulation of gamma exposure induced by 60Co and NORM-radionuclides in closed geometries

Cited by 6 publications

References 13 publications

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate 192Ir brachytherapy

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate 192Ir brachytherapy

Monte carlo calculation of the energy spectrum of a 6 MeV electron beam using penetration and energy loss of positrons and electrons code

Calculation of Lead-Iron Double-Layer Thickness for Gamma-Ray Shielding by MATLAB Program

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A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy

A generic TG‐186 shielded applicator for commissioning model‐based dose calculation algorithms for high‐dose‐rate ¹⁹²Ir brachytherapy