Neutron beam characterization at the finnish BNCT facility

Measurements and calculations

Tom Serén, Iiro Auterinen, Petri Kotiluoto, Tiina Seppälä

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

A Boron Neutron Capture Therapy (BNCT) treatment facility with an epithermal neutron beam has been successfully completed at the Finnish FiR 1 TRIGA reactor at VTT, Espoo. The clinical trials on human patients were started in May 1999. The beam utilizes a specially developed moderator material FLUENTAL™ Extensive measurements and calculations have been carded out to characterize the neutron and gamma fields, both in the "free beam" and in tissue substitute phantoms. Despite the fairly low reactor power (250 kW) an epithermal fluence rate of 1.06 × 109 n cm-2 s-1 is achieved at the beam exit aperture with low fast-neutron contamination. The beam has been modeled in detail using the DORT transport code with the BUGLE-80 library. The neutron spectrum has been adjusted with the LSL-M2 code based on multiple-foil activation. Similar calculations and measurements have been performed by the Finnish BNCT team at the BMRR facility for direct comparison.

Original languageEnglish
Title of host publicationReactor Dosimetry
Subtitle of host publicationRadiation Metrology and Assessment
EditorsJ. Williams, D. Vehar, F. Ruddy, D. Gilliam
PublisherAmerican Society for Testing and Materials ASTM
Pages175-182
ISBN (Electronic)978-0-8031-5450-6
ISBN (Print)978-0-8031-2884-2
DOIs
Publication statusPublished - 1 Jan 2001
MoE publication typeA4 Article in a conference publication

Fingerprint

Neutron beams
Boron
Neutrons
Moderators
Metal foil
Contamination
Chemical activation
Tissue

Keywords

  • Activation detectors
  • BNCT
  • Epithermal neutrons
  • Research reactors
  • Spectrum adjustment
  • Transport methods
  • TRIGA reactors

Cite this

Serén, T., Auterinen, I., Kotiluoto, P., & Seppälä, T. (2001). Neutron beam characterization at the finnish BNCT facility: Measurements and calculations. In J. Williams, D. Vehar, F. Ruddy, & D. Gilliam (Eds.), Reactor Dosimetry: Radiation Metrology and Assessment (pp. 175-182). American Society for Testing and Materials ASTM. ASTM Selected Technical Papers, Vol.. 1398 https://doi.org/10.1520/STP13594S
Serén, Tom ; Auterinen, Iiro ; Kotiluoto, Petri ; Seppälä, Tiina. / Neutron beam characterization at the finnish BNCT facility : Measurements and calculations. Reactor Dosimetry: Radiation Metrology and Assessment. editor / J. Williams ; D. Vehar ; F. Ruddy ; D. Gilliam. American Society for Testing and Materials ASTM, 2001. pp. 175-182 (ASTM Selected Technical Papers, Vol. 1398).
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Serén, T, Auterinen, I, Kotiluoto, P & Seppälä, T 2001, Neutron beam characterization at the finnish BNCT facility: Measurements and calculations. in J Williams, D Vehar, F Ruddy & D Gilliam (eds), Reactor Dosimetry: Radiation Metrology and Assessment. American Society for Testing and Materials ASTM, ASTM Selected Technical Papers, vol. 1398, pp. 175-182. https://doi.org/10.1520/STP13594S

Neutron beam characterization at the finnish BNCT facility : Measurements and calculations. / Serén, Tom; Auterinen, Iiro; Kotiluoto, Petri; Seppälä, Tiina.

Reactor Dosimetry: Radiation Metrology and Assessment. ed. / J. Williams; D. Vehar; F. Ruddy; D. Gilliam. American Society for Testing and Materials ASTM, 2001. p. 175-182 (ASTM Selected Technical Papers, Vol. 1398).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Serén T, Auterinen I, Kotiluoto P, Seppälä T. Neutron beam characterization at the finnish BNCT facility: Measurements and calculations. In Williams J, Vehar D, Ruddy F, Gilliam D, editors, Reactor Dosimetry: Radiation Metrology and Assessment. American Society for Testing and Materials ASTM. 2001. p. 175-182. (ASTM Selected Technical Papers, Vol. 1398). https://doi.org/10.1520/STP13594S