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Boron neutron capture therapy is about a century old, but still current andactive. In this treatment, a high absorption cross-section of boron is used forthermal neutrons and the excited state is decomposed into alpha and lithiumions. These daughter particles have a high LET value and transfer their energyto the surrounding cells. In this work, the neutron generator DD-110 is theneutron source of the treatment mode. Since the neutron generator produces fastneutrons, these must be thermalized to the energy range of the epithermalneutrons. The beam shaping assembly is used for this purpose. The effectivenessof the system is analyzed using in-air and in-phantom parameters. The systemprovides an acceptable ratio of thermal to epithermal flux, gamma dose toepithermal flux and beam collimation. However, the epithermal flux and theratio of fast neutron dose to epithermal flux need to be further improved. Thiscan be achieved by improving the performance of the neutron generator to 2E13n/sec. The entire system is modeled and simulated with the MCNPX code.

Optimization of dd110 neutron generator output for boron neutron capture therapy