Isotope preparations belonging to this group are generated with the (n, Y) nuclear reaction, followed by dissolution and chemical processing of the target. Radiochemical separation is needed only in those cases when other atoms in the compound besides the desired one are highly activated. The products typically con­tain carriers; for this reason, their specific activity is relatively low.

Among the production methods described in the following section, the first two technologies are very simple because, due to the homogeneous isotope composition and ideal chemical composition of the target, only the target nuclide is generated during irradiation without contaminating radionuclides, and so radiochemical sepa­ration is not needed.

The 90Y radionuclide (Table 8.5) with its energy belongs to the group of high — range beta-emitting radionuclides: its penetration in tissues of the living organ is 1—2 cm, so it is suitable for the therapeutic treatment of bone metastases of similar size. The organ-specific behavior of this radionuclide—e. g., penetration of 90Y radionuclide into bone metastases—is ensured by adding ethylene diamine methy­lene phosphonate (EDTMP) to the radionuclide at the treatment site and the formed

complex is intravenously injected to the patient. Typical activity of the injection is 17.5—37 MBq. The total activity of the production batches is approximately 370 MBq.

The 153Sm radionuclide (shown in the Table 8.6) with its energy belongs to the group of low-range beta-emitting radionuclides. Its penetration in tissues of the living organ is 1 —2 mm, so it is suitable for the therapeutic treatment of bone metastases of similar size. The organ-specific behavior of this radionuclide—e. g., penetration of 153Sm radionuclide into bone metastases—is ensured by adding EDTMP to the radionuclide on the treatment site, and the formed complex is intra­venously injected into the patient. The typical activity of the injection is 150—260 MBq. The total activity of the production batches is approximately 2600 MBq.

Other radionuclides belonging to the group that does not require isotope separa­tion are 186Re, 166Ho 169Yb, 165Dy, 177Lu, 89Sr, 59Fe, and 198Au (for medical appli­

The following two production procedures (51Cr and 82Br) are examples of hav­ing multiple chemical elements present in the target. Consequently, the activation of the target, in addition to the target isotope, results in contaminating radionuclide of significant activity, thus requiring subsequent radiochemical separation.

In medical applications, the typical injected activity of 51Cr administered to patient is 10—18.5 MBq, so typical batch activity of the production is around 370 MBq.

In industry, the 51Cr radioisotope (shown in Table 8.7) is widely used for tracer investigation of metallurgical processes and for studying corrosion processes due to the fact that chromium is an important component of the iron — and steel-based structures.

The 82Br radioisotope (see Table 8.8), as a halogen element, can be used as a tracer isotope for halogenation of various industrial components. It has high-energy gamma radiation; therefore, it can be detected outside industrial equipment or pipe­lines. Due to its short half-life, it decays rapidly after the investigation.

The most important industrial application of the 82Br radioisotope is the leakage test of oil pipelines. This 82Br-labeled methyl bromide with an activity of