Application of the new radiation transport (TMG) technique in dose calculations

Petri Kotiluoto, Pekka Hiismäki, Sauli Savolainen

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


    In this paper a novel deterministic calculation method of three-dimensional neutron transport is presented, based on the tree-multigrid (TMG) technique and SP3 approximation. The neutron fluence rate distribution has been calculated for cylindrical PMMA (polymethyl-methacrylate) phantom used in characterisation of Finnish epithermal beam. The PMMA phantom and neighbouring beam collimator structures have been modelled by a CAD system. An octree grid of the advanced tree-multigrid iteration technique has been generated directly from CAD files. The source plane fluence used in Monte Carlo based treatment planning has been utilised. Calculations have been carried out with 47-group BUGLE cross sections. The applicability of the method in BNCT dose planning is discussed.
    Original languageEnglish
    Title of host publicationProceedings of the ninth international symposium on neutron capture therapy for cancer
    Place of PublicationOsaka
    Pages137 - 138
    Publication statusPublished - 2000
    MoE publication typeA4 Article in a conference publication
    Event9th International Symposium on Neutron Capture Therapy for Cancer: NCT Osaka 2000 - Osaka, Japan
    Duration: 2 Oct 20006 Oct 2000


    Conference9th International Symposium on Neutron Capture Therapy for Cancer


    Dive into the research topics of 'Application of the new radiation transport (TMG) technique in dose calculations'. Together they form a unique fingerprint.

    Cite this