background: the characteristics of secondary neutrons in a high energy radiation therapy room were studied using the mcnpx monte carlo (mc) code. materials and methods: two mc models including a model with full description of head components and a simplified model used in previous studies were implemented for mc simulations. results: results showed 4-53% difference between full and with the sim...

The well-known inputs for determining the reaction cross section are nuclear level density (NLD) and -ray strength functions. In this work, effects of functions NLD models on photoneutron reactions 76,77,78Se isotopes analyzed by using latest version TALYS computer code. For functions, macroscopic microscopic options which available in TALYS, used calculations. Kopecky-Uhl Brink Axel function a...

The bremsstrahlung flux-averaged cross sections for the photoneutron reactions $^{\text{93}}$Nb($\gamma $,xn;x=1-5)$^{\text{(93-x)m,g}}$Nb were measured in range of boundary energies $\gamma $-quanta $E_{\gamma \text{max}}$=33-93 MeV with a step $\Delta E_{\gamma \text{max}}\approx $ 2 MeV. isomeric ratios average cross-sections products $^{\text{93}}$Nb ($\gamma ,4n)$^{\text{89m,g}}$Nb and $,5...