Validation of GEANT code of CERN as predictive tool of dose rate measurement in the Tunisian gamma irradiation facility

Gharbi, F.; Kadri, O.; Farah, K.; Mannai, K.

doi:10.1016/j.radphyschem.2005.02.006

Cited by 25 publications

(10 citation statements)

References 4 publications

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“…Given that the uncertainty on the source activity is about 10% [8], the distribution of the experimental data and the theoretical curve show a very good agreement which is a proof of the validity of the calculation. The conversion factor between the dose rates in a given thick medium using the one measured by a PMMA dosimeter can be very useful, for instance, when commissioning a similar irradiation facility.…”

Section: Resultssupporting

confidence: 58%

“…In our case A = 1.81 ± 0.18 PBq [8] and L = 45 cm, we obtain K = 660 Gy m/h. We obtain the same expression found by Huttlin [4], for a linear source of length 2L.…”

Section: Front End Regionsupporting

confidence: 47%

“…The authors of reference [8] have determined the dose rate by simulating the dosimeters with spheres of 8 cm diameter filled with water. The mass thickness of the sphere is more than 20 times the range of the forward Compton electrons.…”

Section: Discussionmentioning

confidence: 99%

“…Gharbi et al [8] selected 29 positions, with a 10 cm step, parallel to the Z axis, at a constant distance X = 150 cm from this axis. Dose measurements were carried out using PMMA dosimeters which are oriented perpendicularly to the X-axis (Figure 1).…”

Section: Methodsmentioning

confidence: 99%

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Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Jemii¹,

Mazouz²,

Ghedira³

2013

WJNST

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Dose rates calculations, in PMMA dosimeters, placed in the vicinity of the Tunisian 60 Co gamma ray irradiator, have been achieved using a pencil like model. The obtained results are in good agreement with recent experimental data. Moreover, in this work we determine also the conversion factor between the dose rate deposited in a PMMA dosimeter and the one deposited in a reel medium. This factor is used to determine the dose deposited in a real irradiated medium such as foodstuff products.

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Section: Resultssupporting

confidence: 58%

“…In our case A = 1.81 ± 0.18 PBq [8] and L = 45 cm, we obtain K = 660 Gy m/h. We obtain the same expression found by Huttlin [4], for a linear source of length 2L.…”

Section: Front End Regionsupporting

confidence: 47%

Section: Discussionmentioning

confidence: 99%

Section: Methodsmentioning

confidence: 99%

See 2 more Smart Citations

Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Jemii¹,

Mazouz²,

Ghedira³

2013

WJNST

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“…The source rack contains 10 free housings allowing the addition of supplementary pencils in order to compensate the decrease of the activity [3]. The total source activity in August/2004 is about 1.81 PBq [5]. In order to determine the photon flux rates and the dose rates deposited in PMMA dosimeters placed in the vicinity of this irradiator, various measurements have been realized by the CNSTN researchers.…”

Section: Introductionmentioning

confidence: 99%

Study of the Photon Flux and the Dose Rate in the Vicinity of a <sup>60</sup>Co Gamma Irradiator

Jemii¹,

Ghedira²

2016

WJNST

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The present work presents an overview of the study of some dosimetric quantities in the vicinity of the Tunisian Gamma Irradiation Facility. Firstly, we have confirmed our previous calculation of the photon flux and the dose rates, using a simulation with GEANT 4. A good agreement between calculation and simulation was obtained, which well confirmed the modeling of the CNSTN extended source by a pencil-like source. Secondly we have determined the isodose curves in the vicinity of the irradiator using a straightforward calculation. Finally, we have presented many comments for some published work concerning the methods used to determine these dosimetric quantities.

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Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source

Ounalli

Bhar²,

Mejri³

et al. 2017

NUCL SCI TECH

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Validation of GEANT code of CERN as predictive tool of dose rate measurement in the Tunisian gamma irradiation facility

Cited by 25 publications

References 4 publications

Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Study of the Photon Flux and the Dose Rate in the Vicinity of a <sup>60</sup>Co Gamma Irradiator

Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source

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Validation of GEANT code of CERN as predictive tool of dose rate measurement in the Tunisian gamma irradiation facility

Cited by 25 publications

References 4 publications

Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Dose Rate Calculation in the Vicinity of the Tunisian Gamma Irradiation

Study of the Photon Flux and the Dose Rate in the Vicinity of a &lt;sup&gt;60&lt;/sup&gt;Co Gamma Irradiator

Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source

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Study of the Photon Flux and the Dose Rate in the Vicinity of a <sup>60</sup>Co Gamma Irradiator