
doi: 10.1093/rpd/nch151
pmid: 15353713
Methods for dosimetry of epithermal neutron beams used in boron neutron capture therapy (BNCT) have been developed and utilised within the Finnish BNCT project as well as within a European project for a code of practise for the dosimetry of BNCT. One outcome has been a travelling toolkit for BNCT dosimetry. It consists of activation detectors and ionisation chambers. The free-beam neutron spectrum is measured with a set of activation foils of different isotopes irradiated both in a Cd-capsule and without it. Neutron flux (thermal and epithermal) distribution in phantoms is measured using activation of Mn and Au foils, and Cu wire. Ionisation chamber (IC) measurements are performed both in-free-beam and in-phantom for determination of the neutron and gamma dose components. This toolkit has also been used at other BNCT facilities in Europe, the USA, Argentina and Japan.
dosimetry, Neutron Dosimetry, toolkits, Radiotherapy Planning, Computer-Assisted, Transducers, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Fast Neutrons, Systems Integration, Radiation Protection, Body Burden, Humans, Radiometry, Relative Biological Effectiveness
dosimetry, Neutron Dosimetry, toolkits, Radiotherapy Planning, Computer-Assisted, Transducers, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Fast Neutrons, Systems Integration, Radiation Protection, Body Burden, Humans, Radiometry, Relative Biological Effectiveness
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