원문정보
초록
영어
Background: FCTC10 container is designed to transport 60Co radioactive sources used in irradiation industry. It belongs to Type B(U) Category III (yellow) package when being loaded with a 60Co source of 1.8 × 105 Ci. Materials and Methods: The container is constituted of shielding container, basket, protective cover and bracket. Shielding ability is provided mainly by stainless steel shells, tungsten alloy and lead among steel shells. Radiation level around the container has been calculated with both Monte Carlo simulations and measurements. Results and Discussion: It is proven that the shielding performance of the container fulfills the requirements in GB11806-2004 (Regulations for the safe transport of radioactive material, China Standard Press). Exposure doses to workers and to critical groups of public were calculated based on hypothetical exposure scene according to transport practice experience. Conclusion: The results show that doses to workers and public are less than the constraint dose considered in design, and the radiation level would be increased less than a factor of 2 under design basis accidents.
목차
Introduction
Materials and Methods
1. Structure of FCTC10 Container
2. Radiation Level
Results and Discussion
1. Dose to the workers
2. Dose to the public
Conclusion
Acknowledgements
References