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 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.
Wrobel
F
F
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 2, France. wrobel@unice.fr
Benabdesselam
M
M
Iacconi
P
P
Lapraz
D
D
D000042:Absorption; D000465:Algorithms; D000537:Aluminum Oxide / Q000528:radiation effects; D017610:Calcium Compounds / Q000528:radiation effects; D002133:Calcium Sulfate / Q000528:radiation effects; D003198:Computer Simulation; D017076:Computer-Aided Design; D004867:Equipment Design / Q000379:methods; D005214:Fast Neutrons; D018499:Linear Energy Transfer; D008956:Models, Chemical; D011829:Radiation Dosage; D011874:Radiometry / Q000295:instrumentation* / Q000379:methods*; D015203:Reproducibility of Results; D012680:Sensitivity and Specificity; D013440:Sulfides / Q000528:radiation effects
D017610:Calcium Compounds; D013440:Sulfides; C033907:calcium sulfide; D000537:Aluminum Oxide; D002133:Calcium Sulfate