Evaluation of the Permissible <sup>99</sup>Mo Activity in the KL-15 Container in the Design of Transportation and Process Scheme
Demand for the use of radioactive isotopes in medicine is increasing with each coming year necessitating the increased output of radionuclide products. One of the most widely spread radionuclides used in medicine is technetium-99m (<sup>99m</sup>Тс). The very short <sup>99m</sup>Тс life (6-hour half-life) requires its production directly on the site of medical treatment. This is achieved using molybdenum-technetium generators loaded with molybdenum-99 (<sup>99</sup>Мо), which uninterruptedly decays (half-life of 66 hours) yielding <sup>99m</sup>Tc. Close attention must be paid in the course of production of molybdenum-technetium generators to radiation safety during transportation of <sup>99</sup>Мо on the territory of the manufacturing facility. The main measure for ensuring radiation safety during transportation of <sup>99</sup>Мо is the application of special packaging kits. The Karpov Institute of Physical Chemistry JSC uses a wide range of packaging kits of types A and B for transportation of radioactive materials on the territory of the manufacturer with design features providing the required level of radiation safety. In particular, the KL-15 container loaded/unloaded from the top is used for on-site transportation of <sup>99</sup>Мо for charging molybdenum-technetium generators. Maximum permissible activity of <sup>99</sup>Мо is not specified in the passport of KL-15 container. Planned construction of radionuclide production shop in accordance with GMP requirements will require the increase of output of target radionuclides by several times. The above considerations necessitated the evaluation of the maximum permissible activity of <sup>99</sup>Мо planned to be transported in KL-15 containers. No other type of standard containers can be used because of their outside dimensions prohibiting the unloading of <sup>99</sup>Мо inside the "hot" chamber. Calculation and experimental evaluation of permissible <sup>99</sup>Мо activity during transportation inside the KL-15 container was performed. The paper presents the calculated evaluation of the maximum permissible activity of <sup>99</sup>Мо in a KL-15 container to ensure the radiation exposure of personnel of group A working with the container not exceeding the established level at the enterprise (80 μSv per shift) and not requiring the use of additional measures and means of protection. The results of the work allow us drawing the conclusion that the KL-15 container ensures the required level of radiation safety with up to 241 Ki of <sup>99</sup>Мо loaded in the container.