# Activation Analyses of Disposal Options for Irradiated Be\({}_{12}\)Ti
## 4 Results of Activation Calculations
### Disposal Options for the Be\({}_{12}\)Ti
#### 4.2.2 Radionuclide-Specific Limits
The entire or partial disposal in the El Cabril depository of the irradiated Be\({}_{12}\)Ti could be nevertheless feasible. \begin{table}
\begin{tabular}{c c c c c} \hline \multirow{2}{*}{**Radionuclide**} & **LLW Limit** & \multicolumn{3}{c}{**Be\({}_{12}\)ti Activity (bq/kg)**} \\  & **(Bq/kg)** & **1 Year** & **10 Years** & **100 Years** \\ \hline Sm-151 & \(4.50\times 10^{8}\) & \(3.39\times 10^{5}\) & \(3.16\times 10^{5}\) & \(1.58\times 10^{5}\) \\ \hline Ni-63 & \(3.20\times 10^{9}\) & \(1.06\times 10^{8}\) & \(9.93\times 10^{7}\) & \(5.34\times 10^{7}\) \\ \hline Sr-90 & \(6.00\times 10^{9}\) & \(5.30\times 10^{6}\) & \(4.27\times 10^{6}\) & \(4.89\times 10^{5}\) \\ \hline Eu-154 & \(5.80\times 10^{10}\) & \(2.15\times 10^{5}\) & \(1.04\times 10^{5}\) & \(7.36\times 10^{1}\) \\ \hline Eu-152 & \(7.50\times 10^{10}\) & \(5.24\times 10^{3}\) & \(3.30\times 10^{3}\) & \(3.28\times 10^{1}\) \\ \hline Ce-144 & \(8.80\times 10^{10}\) & \(3.55\times 10^{7}\) & \(1.21\times 10^{4}\) & - \\ \hline Ru-106 & \(1.20\times 10^{11}\) & \(3.78\times 10^{7}\) & \(8.36\times 10^{4}\) & - \\ \hline Ag-110m & \(1.20\times 10^{11}\) & \(7.37\times 10^{8}\) & \(8.15\times 10^{4}\) & - \\ \hline Na-22 & \(1.30\times 10^{11}\) & \(5.79\times 10^{6}\) & \(4.36\times 10^{5}\) & \(5.78\times 10^{-5}\) \\ \hline Co-60 & \(1.30\times 10^{11}\) & \(1.28\times 10^{10}\) & \(3.92\times 10^{9}\) & \(3.02\times 10^{4}\) \\ \hline Cs-134 & \(1.90\times 10^{11}\) & \(2.70\times 10^{6}\) & \(1.31\times 10^{5}\) & \(1.58\times 10^{-7}\) \\ \hline Mn-54 & \(3.60\times 10^{11}\) & \(1.42\times 10^{9}\) & \(9.64\times 10^{5}\) & - \\ \hline Sb-125 & \(5.10\times 10^{11}\) & \(3.31\times 10^{6}\) & \(3.46\times 10^{5}\) & \(1.38\times 10^{-4}\) \\ \hline Pm-147 & \(5.80\times 10^{11}\) & \(2.04\times 10^{7}\) & \(1.89\times 10^{6}\) & \(2.92\times 10^{-4}\) \\ \hline Zn-65 & \(6.00\times 10^{11}\) & \(1.95\times 10^{8}\) & \(1.75\times 10^{4}\) & - \\ \hline Sn-119m & \(1.40\times 10^{12}\) & \(6.77\times 10^{3}\) & \(2.86\times 10^{0}\) & - \\ \hline Tl-204 & \(3.30\times 10^{12}\) & \(2.453\times 10^{5}\) & \(4.88\times 10^{4}\) & \(4.42\times 10^{-3}\) \\ \hline Fe-55 & \(6.10\times 10^{12}\) & \(1.28\times 10^{10}\) & \(1.31\times 10^{9}\) & \(4.46\times 10^{-1}\) \\ \hline \end{tabular}
\end{table} 
Table 8: _Cont._Within a KONEKT research project [34], repository options for the irradiated beryllium were analyzed to assess possibilities of its storage in Germany. A total mass of the irradiated Be already disposed in different institutions and locations in Germany is estimated to be \(\sim\)3000 kg [34]. The assessment of the safety issues of the Be\({}_{12}\)Ti activation results produced in this report is performed making use of the facility limits available for the Konrad mine repository. Although this repository is big enough to arrange millions of tons of radioactive materials, its capacity for the storage of the radioactive Be is limited to 24.5 kg (Table 12 [35]) because of the potential danger of groundwater contamination. A theoretical option for the Be\({}_{12}\)Ti secure disposal in the steel container of Type I [35] with a useful volume of 3.9 m\({}^{3}\) was chosen for the comparison assuming the limits for the waste group APG03 (metal products, Tables 5 and 6 [35]). Presented in Table 11 are the results for the activity of the accumulated isotopes in the irradiated Be\({}_{12}\)Ti (\"average\") 1 year after the reactor shutdown compared to the Konrad facility limits. The available results for tritium accumulation are not included in Table 11 because the full tritium removal from the irradiated Be\({}_{12}\)Ti blocks is foreseen and expected in the HCPB blankets as it is pointed out above. The accumulated activities of \({}^{60}\)Co (produced from Co impurity) and \({}^{46}\)Sc (produced from the Ti irradiation) exceed the Konrad limits by the factor of \(\sim\)10. The results for \({}^{45}\)Ca and \({}^{57}\)Co slightly exceed the limits.