Earticle

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

ABSTRACT
 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

키워드

저자

• Dajie Zhuang [ China Institute for Radiation Protection, Taiyuan, Shanxi ] Corresponding author
• Guoqing Zhang [ Shanghai Institute of Applied Physics, Jiading District, Shanghai, China ]
• Guoqiang Li [ China Institute for Radiation Protection, Taiyuan, Shanxi ]
• Renze Wang [ China Institute for Radiation Protection, Taiyuan, Shanxi ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  방사선방어학회지 [Journal of Radiation Protection and Research]

• 간기

  계간

• pISSN

  2508-1888

• 수록기간

  1976~2026

• 등재여부

  KCI 등재,SCOPUS

• 십진분류

  KDC 559 DDC 629