Radiation Shielding Analysis of CANDU Spent Fuel Transport Cask

J Radiat Prot > Volume 18(2); 1993 > Article

Journal of Radiation Protection 1993;18(2):27-0.

CANDU 사용후핵연료 수송용기 방사선차폐 영향평가

최종락;윤정현;강희영;이흥영;정성환;

Radiation Shielding Analysis of CANDU Spent Fuel Transport Cask

Choi, Jong-Rak;Yoon, Jung-Hyun;Kang, Hee-Young;Lee, Heung-Young;Chung, Sung-Whan;

ABSTRACT

A shielding analysis of the shipping cask for transporting the CANDU spent fuel bundles has been studied. Radiation source term has been calculated on spent fuel with burn-up of 7,800 MWD/MTU and 5 years cooling time by ORIGEN2 code. The shielding calculation for the cask capable of transporting 378 bundles of CANDU spent fuel has been made by use of 1-D ANISN and 2-D DOT 4.2 codes. As a result of analysis, the optimum shield thickness of cask was obtained. And it is proved that the safety in radiation shielding under normal transport and hypothetical accident conditions is confirmed to satisfy the allowable values specified in IAEA Safety Series No. 6 and the Korean Atomic Law.