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

    Publication series

    SeriesASTM Selected Technical Papers
    Volume1398

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    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