摘要

The specific activities of the SAMRT primary coolant due to fission products were evaluated and they will be used as the source terms of the BOP shielding design. The level of a specific radioactivity is also one of the important factors for determining the RCS volume. SMART reactor which is in the process of being developed consists of 69 fuel assemblies with a 660Mw thermal output. The reactor core has 2 batch fuel assemblies with a 30 month cycle and the effective full power days of the equilibrium cycle are 822 days. The specific activities of the SMART reactor primary coolant due to fission products were evaluated by using the SAEP code. The SAEP code can be applied to an integral reactor such as SMART as well as the current commercial PWRs in existence. The ORIGEN2 code is integrated into the SAEP as a subroutine, to solve the inhomogeneous differential equations which are used to determine the coolant activities. From the evaluation results, the specific activities of the SMART primary coolant due to fission products were compared with those of UCN 5&6 primary coolant with the same purification rate condition; they are averagely 25% of those of UCN 5&6. They are also inversely proportional to the RCS volume for almost all radioisotopes except the isotopes with a long half-life. Therefore, it is found that there is a possibility of reducing the RCS volume.

  • 出版日期2008-6