Study on the radiological assessment of the vitrified form container of ILLW

Many studies and investment on vitrification technology development for the treatment of radioactive wastes have been accomplished both abroad and domestically due to its economical advantage and remarkable volume reduction effect. In Korea, the feasibility study on vitrification technology for ILLW has been started since 1994, and the related research is ongoing with the purpose of operating the world first commercial facility in 2007. In this study, the radiological assessment of the vitrified forms container was carried out. First, the foreign and domestic regulations on the packaging and transport of radioactive wastes were reviewed and the dose limits were also analyzed. Second, the dose rates were calculated by MCNP code in cases when the vitrified forms are packed in the existing container DOT-17H. The results showed that DOT-17H was not satisfied as an acceptable container because of exceeding of the dose limits. Therefore, to derive the design modifications of DOT-17H necessary to satisfy the regulatory requirements, the radiological safety was evaluated with the changes of thickness, diameter, and height of DOT-17H