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Neutron absorbed dose determination by calculations of recoil energy

Identifieur interne : 001E39 ( Istex/Curation ); précédent : 001E38; suivant : 001E40

Neutron absorbed dose determination by calculations of recoil energy

Auteurs : F. Wrobel [France] ; M. Benabdesselam [France] ; P. Iacconi [France] ; D. Lapraz [France]

Source :

Radiation Protection Dosimetry [ 0144-8420 ] ; 2004-08-01.

RBID : ISTEX:890EEB130C801C6C7A12CE157A05155737D09C95

Descripteurs français

Wicri :
- topic : Aluminium.

English descriptors

KwdEn :
- Aluminium, Average energy, Average recoil energy, Caso4, Dose decreases, Dose determination, Dosemeter, Dosim, Dosimetry, Ecis, Ecis code, Elastic, Elastic reactions, Energy range, Energy transfer, Incident neutron energy, Kalbach, Light particles, Luminescence, Luminescent, Luminescent properties, Monte carlo approach, Neutron, Neutron energy, Nuclear reactions, Nucleus decay, Phys, Prot, Radiat, Radiation protection dosimetry, Recoil, Recoil energy, Recoil energy determination, Reference input parameters library, Thermoluminescence, Uence.
Teeft :
- Aluminium, Average energy, Average recoil energy, Caso4, Dose decreases, Dose determination, Dosemeter, Dosim, Dosimetry, Ecis, Ecis code, Elastic, Elastic reactions, Energy range, Energy transfer, Incident neutron energy, Kalbach, Light particles, Luminescence, Luminescent, Luminescent properties, Monte carlo approach, Neutron, Neutron energy, Nuclear reactions, Nucleus decay, Phys, Prot, Radiat, Radiation protection dosimetry, Recoil, Recoil energy, Recoil energy determination, Reference input parameters library, Thermoluminescence, Uence.

Abstract

The aim of this work is to calculate the absorbed dose to matter due to neutrons in the 5–150 MeV energy range. Materials involved in the calculations are Al2O3, CaSO4 and CaS, which may be used as dosemeters and have already been studied for their luminescent properties. The absorbed dose is assumed to be mainly due to the energy deposited by the recoils. Elastic reactions are treated with the ECIS code while for the non-elastic ones, a Monte Carlo code has been developed and allowed to follow the nucleus decay and to determine its characteristics (nature and energy). Finally, the calculations show that the absorbed dose is mainly due to non-elastic process and that above 20 MeV this dose decreases slightly with the neutron energy.

Url:

https://api.istex.fr/document/890EEB130C801C6C7A12CE157A05155737D09C95/fulltext/pdf

DOI: 10.1093/rpd/nch147

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ISTEX:890EEB130C801C6C7A12CE157A05155737D09C95

Le document en format XML

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<wicri:regionArea>Université de Nice-Sophia Antipolis, Laboratoire de Physique Electronique des Solides, Centre de Recherche sur les Solides et leurs Applications, LPES-CRESA, EA1174, Parc Valrose, 06108 Nice Cedex 2</wicri:regionArea>
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<term>Average energy</term>
<term>Average recoil energy</term>
<term>Caso4</term>
<term>Dose decreases</term>
<term>Dose determination</term>
<term>Dosemeter</term>
<term>Dosim</term>
<term>Dosimetry</term>
<term>Ecis</term>
<term>Ecis code</term>
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<term>Energy range</term>
<term>Energy transfer</term>
<term>Incident neutron energy</term>
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<term>Light particles</term>
<term>Luminescence</term>
<term>Luminescent</term>
<term>Luminescent properties</term>
<term>Monte carlo approach</term>
<term>Neutron</term>
<term>Neutron energy</term>
<term>Nuclear reactions</term>
<term>Nucleus decay</term>
<term>Phys</term>
<term>Prot</term>
<term>Radiat</term>
<term>Radiation protection dosimetry</term>
<term>Recoil</term>
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<term>Recoil energy determination</term>
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<term>Average energy</term>
<term>Average recoil energy</term>
<term>Caso4</term>
<term>Dose decreases</term>
<term>Dose determination</term>
<term>Dosemeter</term>
<term>Dosim</term>
<term>Dosimetry</term>
<term>Ecis</term>
<term>Ecis code</term>
<term>Elastic</term>
<term>Elastic reactions</term>
<term>Energy range</term>
<term>Energy transfer</term>
<term>Incident neutron energy</term>
<term>Kalbach</term>
<term>Light particles</term>
<term>Luminescence</term>
<term>Luminescent</term>
<term>Luminescent properties</term>
<term>Monte carlo approach</term>
<term>Neutron</term>
<term>Neutron energy</term>
<term>Nuclear reactions</term>
<term>Nucleus decay</term>
<term>Phys</term>
<term>Prot</term>
<term>Radiat</term>
<term>Radiation protection dosimetry</term>
<term>Recoil</term>
<term>Recoil energy</term>
<term>Recoil energy determination</term>
<term>Reference input parameters library</term>
<term>Thermoluminescence</term>
<term>Uence</term>
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<front><div type="abstract" xml:lang="en">The aim of this work is to calculate the absorbed dose to matter due to neutrons in the 5–150 MeV energy range. Materials involved in the calculations are Al2O3, CaSO4 and CaS, which may be used as dosemeters and have already been studied for their luminescent properties. The absorbed dose is assumed to be mainly due to the energy deposited by the recoils. Elastic reactions are treated with the ECIS code while for the non-elastic ones, a Monte Carlo code has been developed and allowed to follow the nucleus decay and to determine its characteristics (nature and energy). Finally, the calculations show that the absorbed dose is mainly due to non-elastic process and that above 20 MeV this dose decreases slightly with the neutron energy.</div>
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Neutron absorbed dose determination by calculations of recoil energy

Neutron absorbed dose determination by calculations of recoil energy

Source :

Descripteurs français

English descriptors

Abstract

Links toward previous steps (curation, corpus...)

Links to Exploration step

Le document en format XML

Pour manipuler ce document sous Unix (Dilib)

Pour mettre un lien sur cette page dans le réseau Wicri