Monte Carlo studies of the Tunisian gamma irradiation facility using GEANT4 code

Area of Science:

• Nuclear Engineering
• Radiation Physics
• Computational Physics

Background:

• Accurate absorbed dose distribution is crucial for effective gamma irradiation processes.
• The Tunisian gamma irradiation facility (CNSTN) required optimization for enhanced efficiency and product quality.
• Monte Carlo simulations offer a powerful tool for modeling complex radiation transport phenomena.

Purpose of the Study:

• To conduct a comprehensive Monte Carlo study of the CNSTN gamma irradiation facility.
• To optimize the absorbed dose distribution within the irradiation cell, both with and without product.
• To validate simulation results against experimental data.

Main Methods:

• Utilized GEANT4 CERN's code for Monte Carlo simulations.
• Performed detailed dose measurements at 32 points in the source rack plane, 29 along the Z-axis, and 7 critical points using PMMA dosimeters.
• Employed boxes with "dummy" product to simulate realistic irradiation conditions and achieve a target bulk density.

Main Results:

• Achieved good agreement between simulated and experimental results, confirming the accuracy of the GEANT4 code.
• Demonstrated the capability of Monte Carlo simulations to predict absorbed dose distributions effectively.
• Showcased improved understanding of the irradiation process and calculation of dose uniformity within the product.

Conclusions:

• Monte Carlo simulation is a valuable tool for understanding and optimizing gamma irradiation facilities.
• The study successfully optimized the absorbed dose distribution at the CNSTN.
• GEANT4 simulations provide reliable predictions for absorbed dose and dose uniformity, enhancing process control and efficiency.