| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1729580 | Annals of Nuclear Energy | 2009 | 6 Pages |
A shielding analysis was performed which included a source term analysis of an Advanced Voloxidation Process where a spent oxide fuel is oxidized at a high temperature and vacuum condition by removing from it some volatile and semi-volatile elements such as tritium, krypton, xenon, and cesium. The source terms were estimated based on a spent PWR fuel using the ORIGEN-ARP calculation by considering the removal rate of the specific isotopes in the Advanced Voloxidation Process. The shielding problem was constructed by using a simple concrete box containing the spent fuel source which was processed by the Advanced Voloxidation Process, and the surface dose rates were estimated by Monte Carlo calculations. In order to quantify the advantage of the Voloxidation Process, the thicknesses of the concrete wall before and after the Advanced Voloxiation Process were compared. It was found that the Advanced Voloxidation Process provided a slight reduction in the burden on the radiation shielding.
