Dose distribution calculation with MCNP code in a research irradiator

Publication date: Available online 6 May 2019Source: Radiation Physics and ChemistryAuthor(s): B. Leal-Acevedo, I. Gamboa-deBuenAbstractBy comparing the data obtained experimentally, the flux density calculations and simulation results using MCNP we can correlate all the results to ensure that the dose imparted to industrial products is appropriate. We have characterized the 3 fields of the irradiator to maximize the volume of irradiation. Percentage discrepancies below 15%, between the data, are due to parameters such as activity per unit length and by comparing line sources (theoretical calculation) and volume sources (simulations). The results allow us to evaluate the dose uniformity ratio (DUR) in the simulation of material with densities from 0.1 to 1.0 g/cm3.

Source: Radiation Physics and Chemistry - May 7, 2019 Category: Physics Source Type: research