Abstract
The gamma dose determination using thermoluminescent (TL) dosimeters in mixed neutron-gamma fields, such as in boron neutron capture therapy (BNCT), is difficult due to the thermal neutron sensitivity of the detectors; especially when equipment capable of glow curve analysis is not available. The two TL analysis methods used previously in Finnish BNCT to correct the measured TL signal to obtain absorbed gamma dose in vivo were studied and compared, and an enhanced method was introduced. The three TL methods were found surprisingly consistent despite, e.g. the rough estimate made in the first method.
Original language | English |
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Pages (from-to) | 793-797 |
Journal | Applied Radiation and Isotopes |
Volume | 61 |
Issue number | 5 |
DOIs | |
Publication status | Published - 1 Nov 2004 |
MoE publication type | A1 Journal article-refereed |
Keywords
- BNCT
- Gamma dose
- In vivo
- TL dosimeter
- TPS