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Calculation of Activity for Irradiated 110 mAg Foil Using the Los Alamos MCNP5 Code
The main object of this study is the simulation, using the MCNP5 code, of the irradiator 226Ra-Be unit which is available at the physics department of the sciences faculty, Damascus University to calculate the neutron fluxes. The simulation results showed that neutron fluxes, in the energy ranges: thermal (10.9 MeV to 10.6 MeV), fast (0.11 MeV to 12.0 MeV), and medium (10.5 MeV to 10.1 MeV). Where flux percent was about (thermal 70.0%, fast 18.0% and medium 12.0%).
The calculation of activity for a silver foil, in a specific time after irradiation, was simulated and compared with the experimental results. The comparison shows good agreement between the simulated and measured activity.
Keywords
- Geiger KW, Hum R, Jarvis CJD, et al. Neutron spectrum of a Ra-Be source. Division of applied physics. National Research Council of Canada Ottawa. Canadian J Physics. 42:1964-99.
- Bechtel RD. Uranium-232 Berylide neutron source. A thesis presented to the faculty of the division of graduate studies, Georgia Institute of Technology (2007).
- David TW. Neutron activation analysis (NAA), Faculty of Science and Technology, Assumption University Bangkok. (2004);8:8-14.
- Peetermans S. Neutron activation analysis, faculty of engineering. Trainingship at the nuclear physics institute. (2009).
- Altaani A, Nahili M. Calculation of the photon production and photon dose for the neutron irradiator Ra-Be unit using the MCNP5-beta code. J Damascus University Basic Sci. (2015).
- Livin VE. Nuclear Physics and Nuclear Reactor. Atom is date Moscow. (1979);288.
- Radioactivity III: Measurement of half life, PHY192. Half Life. (2016).
- Shoji N. Measurement of the thermal neutron capture cross section and the resonance integral of the 109 Ag (n,γ)110 mAg Reaction. J nuclear sci technol. (2003);40;119-24.
- X-5 Monte Carlo Team. Diagnostics applications group. Los Alamos National Laboratory. MCNP-A General Monte Carlo, N-Particle Transport Code. (2003);5.
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