Monte Carlo techniques for "real-time" simulation of neutron transport for use in radiotherapy are disclosed. The simulated neutron trajectories (160) represent neutron emission from a source during BNCT. In a preferred embodiment, a medical image having a plurality of pixels of information representative of a treatment volume are obtained. The pixels are converted into a plurality of uniform volume elements having substantially the same shape and volume as the pixels and are arranged into a geometric representation of the treatment volume. Neutron particle trajectories in the geometric representation are then computed using Monte Carlo techniques (160) and a determination is made as to whether the particle has been captured, scattered or exits from the model (174). These results are used to determine distributions of radiation doses for cancer therapy.
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