The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1.
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.
Karila
J
J
Department of Physical Sciences, FIN-00014 University of Helsinki, Helsinki, Finland. johanna.karila@helsinki.fi
Seppälä
T
T
Serén
T
T
Kotiluoto
P
P
Auterinen
I
I
Aschan
C
C
Kankaanranta
L
L
Savolainen
S
S
D016754:Boron Neutron Capture Therapy / Q000295:instrumentation / Q000706:statistics & numerical data; D005387:Finland; D005720:Gamma Rays / Q000627:therapeutic use; D006801:Humans; D011879:Radiotherapy Dosage; D013819:Thermoluminescent Dosimetry / Q000379:methods* / Q000706:statistics & numerical data