Three dose calculation codes applied to neutron transport in BNCT

Juha Lampinen (Corresponding author), Tiina Seppälä, Iiro Auterinen, Sauli Savolainen

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

    Abstract

    The three dimensional BNCT_Rtpe/rtt.MC is used for treatment planning in the proposed patient irradiations at the Finnish boron neutron capture therapy (BNCT) facility FiR 1. Two other radiation transport calculation codes used mainly in the characterization of the treatment beam, are DORT (Two-Dimensional Discrete Ordinates Transport Code) and MCNP (Monte Carlo N-Particle Transport Code System).
    Original languageEnglish
    Title of host publicationFrontiers in Neutron Capture Therapy
    Subtitle of host publicationProceedings of the 8th International Symposium on Neutron Capture Therapy for Cancer
    EditorsM. Frederick Hawthorne, Kenneth Shelly, Richard J. Wiersema
    Place of PublicationBoston
    PublisherSpringer
    Pages213-217
    Volume2
    ISBN (Electronic)978-1-4615-1285-1
    ISBN (Print)978-1-4613-5478-9
    Publication statusPublished - 2001
    MoE publication typeA4 Article in a conference publication
    Event8th International Symposium on Neutron Capture Therapy for Cancer - Los Angeles, United States
    Duration: 13 Aug 199818 Aug 1998

    Conference

    Conference8th International Symposium on Neutron Capture Therapy for Cancer
    Country/TerritoryUnited States
    CityLos Angeles
    Period13/08/9818/08/98

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