The present work concerns the development of a technique for activity determination 68Ge/68Ga and 57Co disused radioactive sources. This aims to determine these sources by measuring Monte Carlo simulation using MCNPX code. Therefore, efficiency calibrations 3 x NaI(Tl) detector specific source geometries were carried out. Spectrums two types collected different measurement times. characteristic...

Introduction: High-energy beams of protons offer significant advantages for the treatment of deepseated local tumors. Their physical depth-dose distribution in tissue is characterized by a small entrance dose and a distinct maximum -Bragg peak- near the end of range with a sharp fall-off at the distal edge. Alongside its advantages there are some point that they need to meticul...

introduction radon is a colorless and tasteless gas which exists in most soils. it is a substance that poses a potential risk for lung cancer in case a person is exposed to high levels over long periods of time. the environmental protection agency (epa) estimates that 90% of lung cancers per year are caused by radon. the aim of this paper is to estimate the absorbed doses of 222rn by mcnpx simu...

introduction one of the best methods in the diagnosis and control of breast cancer is mammography. the importance of mammography is directly related to its value in the detection of breast cancer in the early stages, which leads to a more effective treatment. the purpose of this article was to calculate the x-ray spectrum in a mammography system with monte carlo codes, including mcnpx and mcnp5...

Conversion coefficients were calculated for fluence-to-absorbed dose, fluence-to-equivalent dose, fluence-to-effective dose and fluence-to-gray equivalent for isotropic exposure of an adult female and an adult male to tritons ((3)H(+)) in the energy range of 10 MeV to 1 TeV (0.01-1000 GeV). Coefficients were calculated using Monte Carlo transport code MCNPX 2.7.C and BodyBuilder™ 1.3 anthropomo...

Transmutation of burnup products for a typical VVER-1000 reactor in fusion-fission hybrid has been investigated using MCNPX 2.6.0 calculation code. Burnup fission was performed 1000 MW practical power VVER core UO2 fuel and light water as its coolant moderator, well. The have classified separated according to their half-lives usages, the remaining wastes were used fuels reactor. also implemente...