# Activation Analyses of Disposal Options for Irradiated Be\({}_{12}\)Ti
## 4 Results of Activation Calculations
### Disposal Options for the Be\({}_{12}\)Ti
#### 4.2.3 Location Dependent Processing of the Irradiated Be\({}_{12}\)Ti Blocks  
The prismatic Be\({}_{12}\)Ti unit has a radial length of \(\sim\)42 cm in the outboard blankets in the reactor mid plane, Figure 1. Because of the block structure of this unit, there could be an opportunity to process the differently located Be\({}_{12}\)Ti blocks under the strict remote control. This enables the special treatment of the irradiated blocks located in the different radial positions in the Be\({}_{12}\)Ti assembly making use of a remote handling technique. Figure 11 displays the results for the \(\beta\)+\(\gamma\)-specific activity of the Be\({}_{12}\)Ti assembly (\"average\" material composition) arranged in the OBC blanket for two radial segments: a front zone (close to FW) of \(\sim\)26 cm length and a rear zone of \(\sim\)16 cm (close to back wall). The results averaged over the total volume of the Be\({}_{12}\)Ti in the OBC blanket (\"average\", Figure 9) are also presented for the comparison. One year after the reactor shutdown, the specific activity for the front zone is higher by \(\sim\)35% and that for the rear zone is lower by \(\sim\)70% compared to the \"average\" results. Due to the FW neutron wall-loading profile, the upper, central and bottom parts of the blanket are exposed to the different neutron fluxes; in the mid plane of the reactor, the neutron flux is at a maximum. To assess the difference of the results for these parts, the specific activity was calculated in the highest, central and lowest locations in the front zone of the Be\({}_{12}\)Ti assemblies (26 cm length). The \(\beta\)+\(\gamma\)-specific activity in the \"front\" part of the Be\({}_{12}\)Ti assemblies 1 year after the reactor shutdown in the upper and bottom parts of the blanket are lower compared to the central part by \(\sim\)15% and \(\sim\)23%, respectively. The results indicate a significant difference for the specific activity of the Be\({}_{12}\)Ti along the radial distance from the FW. The poloidal distribution of the activity along the blanket height is not so large. In case of the disposal possibility, the irradiated Be\({}_{12}\)Ti blocks could be processed separately using a \"layer by layer\" approach to find the best processing strategy. \begin{table}
\begin{tabular}{l c c c c} \hline \hline
**Radionuclide** & **Class A** & **Class B** & **Class C** & **Be\({}_{12}\)Ti** \\ \hline H-3 & \(1.5\times 10^{12}\) & (\({}^{1}\)) & (\({}^{1}\)) & - \\ Co-60 & \(2.6\times 10^{13}\) & (\({}^{1}\)) & (\({}^{1}\)) & 2.9 \(\times 10^{13}\) \\ Ni-63 in activated metal & \(1.3\times 10^{12}\) & \(2.6\times 10^{13}\) & \(2.6\times 10^{14}\) & 2.4 \(\times 10^{11}\) \\ Sr-90 & \(1.5\times 10^{9}\) & \(5.6\times 10^{12}\) & \(2.6\times 10^{14}\) & 1.2 \(\times 10^{10}\) \\ Cs-137 & \(3.7\times 10^{10}\) & \(1.6\times 10^{12}\) & \(1.7\times 10^{14}\) & \(2.6\times 10^{10}\) \\ \hline \hline \end{tabular} \({}^{1}\) There are no limits established for this radionuclide in Class B or C wastes. This waste shall be Class B unless the concentrations of other nuclides in this determine the waste to Class C independent of these nuclides.  
\end{table} 
Table 13: Specific activity (Bq/m\({}^{3}\)) of several _short-lived_ radionuclides in the Be\({}_{12}\)Ti compared to the limits for the different classes of LLW in the USA.