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Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code

This paper describes a complete Monte Carlo study of the Tunisian gamma irradiation facility (CNSTN) using the GEANT4 CERN's code. The work focused on the optimization of the absorbed dose distribution inside the irradiation cell, with and without product. For this purpose, 32 different points...

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Detalles Bibliográficos
Autores principales: Kadri, O, Gharbi, F, Farah, K, Mannai, K, Trabelsi, A
Lenguaje:eng
Publicado: 2005
Materias:
Acceso en línea:http://cds.cern.ch/record/921327
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author Kadri, O
Gharbi, F
Farah, K
Mannai, K
Trabelsi, A
author_facet Kadri, O
Gharbi, F
Farah, K
Mannai, K
Trabelsi, A
author_sort Kadri, O
collection CERN
description This paper describes a complete Monte Carlo study of the Tunisian gamma irradiation facility (CNSTN) using the GEANT4 CERN's code. The work focused on the optimization of the absorbed dose distribution inside the irradiation cell, with and without product. For this purpose, 32 different points at the middle plane of the source rack, 29 positions along Z axis and 7 critical points, were carried out using PMMA dosimeters. Then, to achieve a given bulk density, boxes loaded with “dummy” product were used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity within product.
id cern-921327
institution Organización Europea para la Investigación Nuclear
language eng
publishDate 2005
record_format invenio
spelling cern-9213272019-09-30T06:29:59Zhttp://cds.cern.ch/record/921327engKadri, OGharbi, FFarah, KMannai, KTrabelsi, AMonte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 codeHealth Physics and Radiation EffectsThis paper describes a complete Monte Carlo study of the Tunisian gamma irradiation facility (CNSTN) using the GEANT4 CERN's code. The work focused on the optimization of the absorbed dose distribution inside the irradiation cell, with and without product. For this purpose, 32 different points at the middle plane of the source rack, 29 positions along Z axis and 7 critical points, were carried out using PMMA dosimeters. Then, to achieve a given bulk density, boxes loaded with “dummy” product were used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity within product.oai:cds.cern.ch:9213272005
spellingShingle Health Physics and Radiation Effects
Kadri, O
Gharbi, F
Farah, K
Mannai, K
Trabelsi, A
Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title_full Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title_fullStr Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title_full_unstemmed Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title_short Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code
title_sort monte carlo studies of the tunisian gamma irradiation facility using geant4 code
topic Health Physics and Radiation Effects
url http://cds.cern.ch/record/921327
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AT gharbif montecarlostudiesofthetunisiangammairradiationfacilityusinggeant4code
AT farahk montecarlostudiesofthetunisiangammairradiationfacilityusinggeant4code
AT mannaik montecarlostudiesofthetunisiangammairradiationfacilityusinggeant4code
AT trabelsia montecarlostudiesofthetunisiangammairradiationfacilityusinggeant4code