<p>^99mTc is the most widely used radionuclide in medical diagnostics and typically obtained from high-specific-activity (HSA) ⁹⁹Mo produced in nuclear reactors. However, recent reactor shutdowns have led to supply shortages and prompted efforts to implement alternative production methods. One promising approach is neutron activation of ⁹⁸Mo, which yields low-specific-activity (LSA) ⁹⁹Mo. Since conventional Al₂O₃-based ⁹⁹Mo/^99mTc generators are designed for HSA ⁹⁹Mo, adaptations are required for LSA ⁹⁹Mo usage. In this study, we evaluated the feasibility of modifying existing Al₂O₃-based ⁹⁹Mo/^99mTc generators for use with LSA ⁹⁹Mo, anticipating production at the planned high brilliance neutron source (HBS) at Forschungszentrum Jülich. Key modifications included adjustments to the amount of Al₂O₃ on the column and the elution volume of ^99mTc to enhance ⁹⁹Mo adsorption and ^99mTc elution efficiency. The performance of the modified “mock-up” system was compared with a standard clinical generator. The results demonstrated that only minor modifications are required for LSA ⁹⁹Mo to be effectively utilized in a future generator, with elution efficiencies remaining comparable to conventional generators, while maintaining parameters like size, form, number, activity of the individual generator comparable. However, ⁹⁹Mo breakthrough levels exceeded regulatory limits, highlighting the need for further optimization. Nevertheless, these findings support the feasibility of using LSA ⁹⁹Mo in clinical applications with minimal changes to existing infrastructure.</p>