Minimizing Gamma Exposure During Boron Neutron Capture Therapy Treatment At Psbr Using Mcnp PDF Download

Boron neutron capture therapy (BNCT) is a form of targeted radiotherapy meant to selectively deliver high amounts of energy to tumor cells while being more likely to spare healthy tissue than traditional forms of cancer treatment. This method of cancer treatment uses a stable isotope of boron, 10B, which has a high probability of absorbing a neutron, and the reaction resulting from this absorption leaves this isotope in an excited state of 11B, which ultimately fissions to produce an alpha particle. This alpha particle is what delivers the energy to the tumor, and the fact that these particles do not travel far, sparing healthy tissue and making alpha particles ideal for targeted radiotherapy. The issue is that neutron sources, such as the Penn State Breazeale Reactor (PSBR), also produce gamma radiation in addition to neutrons, exposing patients to additional, unwanted radiation. The aim of this project was to help combat patient exposure to gamma radiation from the neutron source used during boron neutron capture therapy (BNCT). A model of Neutron Beam Port 4 (NBP4) at the PSBR was created in MCNP to help accomplish this goal. This model was created to execute simulations involving the neutron beam port used in the BNCT procedure. From this model execution, neutron and photon flux profiles were determined at varying axial and radial locations along the beam port. The results of these calculations were then to be used to make recommendations towards the implementation of some shielding geometry in NBP4 for BNCT procedures. This model was originally to be executed under four conditions: no shielding, and gamma ray shielding made of concrete, steel, and lead. Future work is recommended to achieve more detailed MCNP model results.