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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Veröffentlicht in: | Radiation protection dosimetry 2004-01, Vol.110 (1-4), p.807-811 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | 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. |
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ISSN: | 0144-8420 1742-3406 |
DOI: | 10.1093/rpd/nch147 |