Dosimetry of neutron beams for BNCT involves characterization of the neutron¯ux in the free ®eld as well as characterization of¯ux, KERMA, and dose distributions in realistic phantoms and in vivo. Activation dosimeters and paired ion chambers are commonly used for this application and advanced techniques, especially for in vivo applications (e.g. scintillating glass ®bres) are under investigation.Computational dosimetry and treatment planning techniques for BNCT have evolved along two lines in the US. Both approaches are based on direct construction of patient geometry from medical images, followed by explicit multidimensional Monte Carlo calculations of the expected radiation dose distribution, given a description of the incident neutron source. The two approaches differ, however, in the speci®c methods used for the reconstruction and¯ux calculation. In this respect, one approach is based on use of standard general-purpose Monte Carlo software, while the other employs special-purpose radiation transport software that has been optimized for medical applications involving neutron transport.
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