# 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
\begin{table}
\begin{tabular}{c c c c c} \hline  & **LLW Limit** & \multicolumn{3}{c}{**Be\({}_{12}\)H Activity (bg/kg)**} \\
**Radionuclide** & **(Bq/kg)** & **1 Year** & **10 Years** & **100 Years** \\ \hline Sn-126 & \(2.70\times 10^{3}\) & \(1.07\times 10^{2}\) & \(1.07\times 10^{2}\) & \(1.07\times 10^{2}\) \\ \hline Cl-36 & \(5.00\times 10^{3}\) & \(2.94\times 10^{1}\) & \(2.94\times 10^{1}\) & \(2.94\times 10^{1}\) \\ \hline Nb-94 & \(1.20\times 10^{5}\) & \(5.76\times 10^{2}\) & \(5.76\times 10^{2}\) & \(5.74\times 10^{2}\) \\ \hline Th-232 & \(1.10\times 10^{6}\) & \(6.50\times 10^{-6}\) & \(6.50\times 10^{-6}\) & \(6.50\times 10^{-6}\) \\ \hline Ag-108m & \(1.40\times 10^{6}\) & \(3.73\times 10^{6}\) & \(3.68\times 10^{6}\) & \(3.17\times 10^{6}\) \\ \hline I-129 & \(1.40\times 10^{6}\) & \(5.16\times 10^{0}\) & \(5.16\times 10^{0}\) & \(5.16\times 10^{0}\) \\ \hline Be-10 & \(5.10\times 10^{6}\) & \(4.81\times 10^{5}\) & \(4.81\times 10^{5}\) & \(4.81\times 10^{5}\) \\ \hline Zr-93 & \(1.80\times 10^{7}\) & \(8.99\times 10^{2}\) & \(8.99\times 10^{2}\) & \(8.99\times 10^{2}\) \\ \hline Mo-93 & \(3.80\times 10^{7}\) & \(1.17\times 10^{5}\) & \(1.13\times 10^{5}\) & \(1.11\times 10^{5}\) \\ \hline Tc-99 & \(4.40\times 10^{7}\) & \(1.13\times 10^{4}\) & \(1.13\times 10^{4}\) & \(1.04\times 10^{4}\) \\ \hline Se-79 & \(5.50\times 10^{7}\) & \(9.47\times 10^{0}\) & \(9.47\times 10^{0}\) & \(9.46\times 10^{0}\) \\ \hline C-14 & \(9.20\times 10^{7}\) & \(1.78\times 10^{7}\) & \(1.78\times 10^{7}\) & \(1.78\times 10^{7}\) \\ \hline Ni-59 & \(1.10\times 10^{8}\) & \(7.98\times 10^{5}\) & \(7.98\times 10^{5}\) & \(7.88\times 10^{5}\) \\ \hline H-3 & \(2.00\times 10^{8}\) & - & - & - \\ \hline Cs-135 & \(2.60\times 10^{8}\) & \(1.75\times 10^{2}\) & \(1.75\times 10^{2}\) & \(1.75\times 10^{2}\) \\ \hline Ca-41 & \(3.00\times 10^{8}\) & \(3.72\times 10^{3}\) & \(3.72\times 10^{3}\) & \(3.72\times 10^{3}\) \\ \hline Pd-107 & \(3.00\times 10^{8}\) & \(2.69\times 10^{1}\) & \(2.69\times 10^{1}\) & \(2.69\times 10^{1}\) \\ \hline Cs-137 & \(3.30\times 10^{8}\) & \(1.13\times 10^{7}\) & \(9.20\times 10^{6}\) & \(1.15\times 10^{6}\) \\ \hline Sn-121m & \(3.70\times 10^{8}\) & \(1.62\times 10^{4}\) & \(1.40\times 10^{4}\) & \(3.39\times 10^{3}\) \\ \hline \end{tabular}
\end{table} 
Table 8: Accumulated activity of various radioactive isotopes in the central OB blanket compared to the French nuclear waste regulations. The Spanish national regulator also applies the radionuclide-specific criteria but it splits them into three subgroups: VLLW--very low-level waste and LILW--low-intermediate-level waste group 1 and 2. Presented in Table 9 are the waste acceptance limits for several isotopes adopted for the El Cabril disposal facility [25; 26; 32]. The LILW-1 level needs verification of a waste container resistance to compression and immersion with a certification for a possible diffused liquid release. The LILW-2 level must satisfy limits to leaching and thermal cycles. Both LILW levels assume homo- and heterogeneous waste incorporated or immobilized in a solid matrix. The specific activity of \({}^{60}\)Co and \({}^{137}\)Cs accumulated in the irradiated Be\({}_{12}\)Ti could be an issue for the long-term storage in the El Cabril depository in case of the use of the container certified for the LILW-1 limit. In case of the Be12 Timax composition, Table 2, the specific activities of these isotopes also do not exceed the El Cabril LILW-2 limits: 2.5\(\cdot 10^{10}\) and 5.7\(\cdot 10^{7}\) Bq/kg for \({}^{60}\)Co and \({}^{137}\)Cs, respectively. The total activity accumulated in the Be\({}_{12}\)Ti of the HCPB breeder blankets 1 year after the shutdown compared to the installed capacity of the El Cabril facility [33] is presented in Table 10. The total activity of \({}^{14}\)C accumulated in the HCPB tokamak is about a half of the total capacity of the El Cabril facility for this radionuclide and it seems to be too high for the disposal there.