(Sunday, 7/12/2020) [Eastern Time (GMT-4)]
Room: AAPM ePoster Library
Purpose: We present a new method for creating accurate patient specific boron neutron capture therapy (BNCT) input files to run in MCNP6 for treatment planning. BNCT uses an epithermal neutron beam and targeted boron doped pharmaceuticals to preferentially irradiate malignant cells. While several treatment planning systems perform this task, our method reduces the number of assumptions made about tissue density and boron concentrations outside of the target. This should yield more accurate dose distributions that account for tissue and boron inhomogeneities. This method also utilizes new mesh tally capabilities introduced in MCNP6.
Methods: Input files are auto generated based off of raw DICOM PET/CT files. A user input is requested before running to determine the desired voxel size. The PET/CT is then compressed into evenly spaced voxels, each with unique density and boron concentrations based off of HU and SUV values, respectively. This allows several hundred thousand lines of error free input code to be written in several minutes. This generated input file can be run with the latest version of MCNP, MCNP6.2. The only manual coding required by the user is selecting the source position and desired energy spectrum. For testing purposes, an energy spectrum published by Lawrence Berkley National Labs for BNCT clinical trials is being used. A method has also been developed to convert the output files from MCNP into a dose grid importable by RayStation. This will allow direct comparison of a BNCT plan generated using MCNP to an IMRT plan created in RayStation.
Results: Current testing of this model shows that the raw DICOM PET/CT files are accurately being converted into a user-defined grid, with each voxel containing its own unique density and boron concentration. Simulations are compared to RayStation IMRT plans.
Conclusion: work allows for more accurate, patient specific BNCT dose calculations.
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