Shielding Analysis of a Transport and Storage Cask for Spent BWR Fuel Applicability of the Code SAS4 and Discussion of Results

Year
2004
Author(s)
Franz Hilbert - Nuclear Cargo + Service GmbH (DAHER-NCS)
Makoto Morishima - Mitsubishi Heavy Industries, Ltd.
Hiroki TAMAKI - Mitsubishi Heavy Industries, Ltd.
File Attachment
3-12_014.pdf483.48 KB
Abstract
For the shielding analysis of transport and storage casks for spent fuel the use of computer codes is state of the art. However, in most applications the computer models used for the analysis are simplified to circular geometries to save modelling effort and calculation time. Furthermore, the active zone of the fuel is modelled as homogeneous zone with a uniform average burn-up. In the first part of the present paper it is shown that an exact model is feasible and the effect of the geometrical shape on the dose rates is illustrated. The second part of the paper shows the comparison of the dose rates calculated with 5 different fuel models. Finally, the accuracy of the calculations is discussed.