Investigation of ⁹⁹Mo potential production via UO₂SO₄ liquid target irradiation in a 5 MW nuclear research reactor

The activation method for ⁹⁹Mo production in comparison to fissionable target irradiation in research reactors is less preferable. Therefore, ⁹⁹Mo yield using UO₂SO₄ samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for ⁹⁹Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g ²³⁵U produced 57Ci⁹⁹Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation.