The work aims to conduct shielding design analysis on a transport cask for pressurized water reactor (PWR) related components, to ensure that the design meets the dose rate limits specified in the regulations for the transport of radioactive materials. The 3D shielding analysis code was used to perform shielding design optimization analysis for the related component transport cask. Dose rate monitoring was carried out at different circumferential and axial positions of the cask to identify the weak points in the shielding design, and key monitoring was performed under normal transport conditions and accident conditions. The analysis results showed that in the circumferential direction, the maximum dose rate occurred at -45° direction closest to the source rod; in the axial direction, the maximum dose rate was found at the rotating groove. Under normal transport conditions, the maximum dose rate on the cask surface was 2.43 mSv/h, which met the exclusive use limit of 10 mSv/h; the maximum dose rate at 2 m from the lower end surface of the cask was 0.081 mSv/h, satisfying the requirement that the dose rate at 2 m from the package should be less than 0.1 mSv/h. Considering that limiters need to be installed at the ends of the cask along with support skid and personnel barrier guards mounted on the exterior during normal transport conditions, the rotating grooves would be filled by the trunnions of the support skid, so the dose rate on surface and at 2 m from the cask would be further reduced. Under accident conditions, the maximum dose rate at 1 m from the cask surface was 7.42 mSv/h, which met the limit of 10 mSv/h. The analysis results of this paper provide a basis for the subsequent optimization of the shielding design of related components transport casks.
Key words
transport cask /
shielding design /
safety analysis /
pressurized water reactor (PWR)
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