# Measurements and Assessments on Shielding Performance of FCTC10 60Co Transport Container

• Accepted : 2016.09.21
• Published : 2016.09.30

#### Abstract

Background: FCTC10 container is designed to transport $^{60}Co$ radioactive sources used in irradiation industry. It belongs to Type B(U) Category III (yellow) package when being loaded with a $^{60}Co$ source of $1.8{\times}10^5$ 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.

#### References

1. He SJ. Protection and safety of ionizing radiation utilization in industry (in Chinese). 1st Ed. Beijing China. Atomic energy press. 2009:12-13.
2. International Atomic Energy Agency. Regulations for the safe transport of radioactive material. IAEA Safety Standards Requirements. No.SSR-6. 2012;109-118.
3. International Atomic Energy Agency. Advisory material for the IAEA regulations for the safe transport of radioactive material. IAEA Safety Standards Requirements. No.SSG-6. 2012;157-174.
4. Chen YF, Chiou YF, Chang SJ. Effects of source and geometry modeling on the shielding calculation for a spent nuclear fuel dry storage cask (in Chinese). Nucl. technol. 2013;182(2):224-234. https://doi.org/10.13182/NT13-A16432
5. Tang ZQ, Li GQ, Su BY, Li ZQ. Numerical Simulation on Impacting Test of Industrial Irradiation Transport Package for Radioactive Material Under the Accident Condition (in Chinese). J. Tai-Yuan University of Technology. 2015;46(2):247-252.