Dose distribution calculation with MCNP code in a research irradiator

By 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 irrad...

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Bibliographic Details
Published in:Radiation physics and chemistry (Oxford, England : 1993) England : 1993), 2020-02, Vol.167, p.108320, Article 108320
Main Authors: Leal-Acevedo, B., Gamboa-deBuen, I.
Format: Article
Language:English
Subjects:
Dose distribution
Flux density
Mathematical analysis
MCNP code calculations
Research irradiator
Simulation
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Summary:By 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. •A research irradiator dose uniformity ratio is analyzed.•Dose distribution measurements and calculations.•A comparison between experimental data and MC simulations with the MCNP code has been carried out.
ISSN:0969-806X
1879-0895
DOI:10.1016/j.radphyschem.2019.05.010