Combining Monte Carlo simulations and dosimetry measurements for process control in the Tunisian Cobalt-60 irradiator after three half lives of the source

• Published in: Nuclear science and techniques Vol. 28; no. 9; pp. 119 - 128
• Main Authors: Ounalli, Leila, Bhar, Maroua, Mejri, Arbi, Manai, Kais, Bouabidi, Ammar, Abdallah, Shayma Mohamed, Reguigui, Nafaa
• Format: Journal Article
• Language: English
• Published: Singapore Springer Singapore 01-09-2017; Laboratory on Energy and Matter for Nuclear Sciences Development, Technopark Sidi Thabet, 2020 Ariana, Tunisia%Tunisian Higher Institute of Medical Technologies, 9 Rue Zouhair Essafi 1006 TUNIS, 1006 Tunis, Tunisia%Tunisian Center for Nuclear Sciences and Technology,Technopark Sidi Thabet, 2020 Ariana, Tunisia%Faculty of Sciences of Tunis, Technopark Sidi Thabet,2020 Ariana, Tunisia; College of Science and Arts, University of Bisha, Bisha,Kingdom of Saudi Arabia%Tunisian Center for Nuclear Sciences and Technology,Technopark Sidi Thabet, 2020 Ariana, Tunisia; Tunisian Center for Nuclear Sciences and Technology,Technopark Sidi Thabet, 2020 Ariana, Tunisia; Faculty of Sciences of Tunis, Technopark Sidi Thabet,2020 Ariana, Tunisia%Faculty of Sciences of Tunis, Technopark Sidi Thabet,2020 Ariana, Tunisia
• Subjects: Energy; Geant4; Hadrons; Heavy Ions; Nuclear Energy; Nuclear Physics; 剂量测量; 半衰期; 突尼斯; 蒙特卡洛; 辐照模拟; 过程控制; 钴-60; Medical devices; Dose mapping; Monte Carlo calculation; PMMA dosimeter; Sterilization; Dose rate; Uniformity; Cobalt-60
• ISSN: 1001-8042; 2210-3147
• DOI: 10.1007/s41365-017-0289-5

To check the dose uniformity and to determine the efficiency of medical devices sterilization by gamma irradiation after three half lives of the source, calculations of the absorbed dose were carried out. Monte Carlo sim- ulations and dosimetry measurements, were established to study the radiation processing quality control. An isodose chart was created by GEANT4 Monte Carlo code to evaluate the absorbed dose rate uniformity inside the irra- diation room from the year of the installation until the year of the source reload. The dose uniformity ratio （DUR） is deduced from maximum and minimum experimental doses in medical devices after three half lives of the source.