The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1

Johanna Karila, Tiina Seppälä, Tom Serén, Petri Kotiluoto, Iiro Auterinen, C. Aschan, Leena Kankaanranta, Sauli Savolainen

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)

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 languageEnglish
Pages (from-to)793-797
JournalApplied Radiation and Isotopes
Volume61
Issue number5
DOIs
Publication statusPublished - 1 Nov 2004
MoE publication typeA1 Journal article-refereed

Fingerprint

therapy
boron
neutrons
dosage
thermal neutrons
dosimeters
luminescence
detectors
curves
estimates

Keywords

  • BNCT
  • Gamma dose
  • In vivo
  • TL dosimeter
  • TPS

Cite this

Karila, Johanna ; Seppälä, Tiina ; Serén, Tom ; Kotiluoto, Petri ; Auterinen, Iiro ; Aschan, C. ; Kankaanranta, Leena ; Savolainen, Sauli. / The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1. In: Applied Radiation and Isotopes. 2004 ; Vol. 61, No. 5. pp. 793-797.
@article{55284e7e0a6c416788fbcd47a32fe6d0,
title = "The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1",
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.",
keywords = "BNCT, Gamma dose, In vivo, TL dosimeter, TPS",
author = "Johanna Karila and Tiina Sepp{\"a}l{\"a} and Tom Ser{\'e}n and Petri Kotiluoto and Iiro Auterinen and C. Aschan and Leena Kankaanranta and Sauli Savolainen",
year = "2004",
month = "11",
day = "1",
doi = "10.1016/j.apradiso.2004.05.029",
language = "English",
volume = "61",
pages = "793--797",
journal = "Applied Radiation and Isotopes",
issn = "0969-8043",
publisher = "Elsevier",
number = "5",

}

The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1. / Karila, Johanna; Seppälä, Tiina; Serén, Tom; Kotiluoto, Petri; Auterinen, Iiro; Aschan, C.; Kankaanranta, Leena; Savolainen, Sauli.

In: Applied Radiation and Isotopes, Vol. 61, No. 5, 01.11.2004, p. 793-797.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - The TL analysis methods used to determine absorbed gamma doses in vivo for the BNCT patients treated at FiR 1

AU - Karila, Johanna

AU - Seppälä, Tiina

AU - Serén, Tom

AU - Kotiluoto, Petri

AU - Auterinen, Iiro

AU - Aschan, C.

AU - Kankaanranta, Leena

AU - Savolainen, Sauli

PY - 2004/11/1

Y1 - 2004/11/1

N2 - 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.

AB - 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.

KW - BNCT

KW - Gamma dose

KW - In vivo

KW - TL dosimeter

KW - TPS

UR - http://www.scopus.com/inward/record.url?scp=4143074855&partnerID=8YFLogxK

U2 - 10.1016/j.apradiso.2004.05.029

DO - 10.1016/j.apradiso.2004.05.029

M3 - Article

C2 - 15308146

AN - SCOPUS:4143074855

VL - 61

SP - 793

EP - 797

JO - Applied Radiation and Isotopes

JF - Applied Radiation and Isotopes

SN - 0969-8043

IS - 5

ER -