Neutron absorbed dose determination by calculations of recoil energy

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 assume...

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Bibliographic Details
Published in:Radiation protection dosimetry 2004-01, Vol.110 (1-4), p.807-811
Main Authors: Wrobel, F., Benabdesselam, M., Iacconi, P., Lapraz, D.
Format: Article
Language:English
Subjects:
Absorption
Algorithms
Aluminum Oxide - radiation effects
Calcium Compounds - radiation effects
Calcium Sulfate - radiation effects
Computer Simulation
Computer-Aided Design
Engineering Sciences
Equipment Design - methods
Fast Neutrons
Linear Energy Transfer
Models, Chemical
Radiation Dosage
Radiometry - instrumentation
Radiometry - methods
Reproducibility of Results
Sensitivity and Specificity
Sulfides - radiation effects
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Summary: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.
ISSN:0144-8420
1742-3406
DOI:10.1093/rpd/nch147