o:29021 DOSE ASSESSMENT WITH MCNP5/X CODE FOR BORON NEUTRON CAPTURE THERAPY OF PANCREAS CANCER en Abstract: Boron neutron capture therapy is based on neutron capture by 10B and creation of high energy alpha particle and recoiled 7Li ion which have ranges comparable to cell dimensions. The MCNP5/X code is applied for calculation of the absorbed doses as well as dose distribution by depth in pancreas cancer and the organs of the analytical and voxelized Oak Ridge National Laboratory phantom, which represents the human body. The depth dose distributions for thermal, epithermal neutrons, and neutron spectrum, show that the absorbed doses are the largest exactly in the cancer, in all cases. It is found by this simulation that the epithermal neutrons are the optimal choice for BNC therapy. They deliver a similar dose to cancer as the thermal neutrons but, spare the healthy tissue more than the thermal ones. Keywords: absorbed dose; Boron neutron capture therapy; cancer; MCNP5/X code; pancreas 1552099 10.2298/NTRP2103294K 1552101 1451-3994 2023-05-04T09:16:48.431Z 44 no 46 Dragana Ž Krstić Dragoslav R Nikezić Državni univerzitet u Novom Pazaru person 0000-0002-3236-4912 Milena P. Živković person Marija Ž. Jeremić person application/pdf 470166 https://phaidrabg.bg.ac.rs/o:29021 no yes 1 70 92000001 20A01 Nuclear Technology and Radiation Protection 36 3 294 298 2021