Abstract
For any routine clinical application of Boron Neutron Capture Therapy fast and accurate dose calculations will be required for treatment planning. Such calculations are also necessary for the planning and interpretation of results from pre-clinical and clinical trials where the speed of calculation is not so critical. A number of treatment planning systems have been developed1,2. A dose calculation system based on the MCNP3 Monte Carlo Neutron transport code has also been developed by Wallace4. This system takes image data from CT scans and constructs a voxel based geometrical model for input into MCNP. To validate the calculations, a number of phantoms were constructed and exposed in the HB11 epithermal neutron beam at the HFR of the CEC Joint Research Centre in Petten5. The doses recorded by arrays of dosimeters in these phantoms were compared with the calculated results from the MCNP dose planning system. The phantoms used included a cylindrical phantom, a human head phantom and a human torso phantom. The measurements used gold, manganese and copper activation foils as well as P-I-N diode neutron dosimeters6 and MOSFET gamma dosimeters. The overall aim was to show that doses to these detectors placed within the phantoms could be accurately predicted by the dose calculation system.
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© 1996 Springer Science+Business Media New York
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Carolan, M.G. et al. (1996). Validation of Monte Carlo Dose Planning Calculations by Epithermal Beam Dose Distribution Measurements in Phantoms. In: Mishima, Y. (eds) Cancer Neutron Capture Therapy. Springer, Boston, MA. https://doi.org/10.1007/978-1-4757-9567-7_44
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DOI: https://doi.org/10.1007/978-1-4757-9567-7_44
Publisher Name: Springer, Boston, MA
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