Measurements and Assessments on Shielding Performance of FCTC10 60Co Transport Container |
Zhuang, Dajie
(China Institute for Radiation Protection)
Zhang, Guoqing (Shanghai Institute of Applied Physics) Li, Guoqiang (China Institute for Radiation Protection) Wang, Renze (China Institute for Radiation Protection) |
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. DOI |
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. |