Optimizing irradiation conditions for natural molybdenum in WWR-K reactor
Sairanbayev D.S. Gizatulin S.K. Gurin A.N. Chakrova Y.T. Aitkulov M.T. Nessipbay A.Z. Ashibayev A.C. Shaimerdenov A.A.
September 2024Korean Nuclear Society
Nuclear Engineering and Technology
2024#56Issue 93566 - 3570 pp.
The production of the radioisotope molybdenum-99 in the WWR-K research reactor is achieved through the activation method 98Mo(n,γ)99Mo, utilizing a target of natural molybdenum trioxide irradiated under standard conditions (thermal neutron spectra and water environment). Under such conditions, the maximum specific activity of molybdenum-99 reaches (2.3 ± 0.3) Ci/g Mo after 7 d of irradiation. However, the escalating demand for molybdenum-99 and the need to reduce its production cost, necessitates urgent and increased productivity. This study aims to optimize the irradiation conditions for molybdenum powder in the WWR-K reactor to increase the specific activity of molybdenum-99. For this purpose, we evaluated various irradiation capsule designs comprised various neutron moderator materials and thicknesses. Through extensive modeling calculations, we obtained an optimal capsule design that increases the specific activity of molybdenum-99 to 3.31 Ci per 1 g of Mo.
Activation method , Beryllium , MCNP , Medical radioisotope , Molybdenum-99 , Research reactor WWR-K , Resonance neutrons
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