Diversification of 99Mo/99mTc Separation: Non-Fission Reactor Production of 99Mo as a Strategy for Enhancing 99mTc Availability

摘要

id="p-2">This paper discusses the benefits of obtaining 99mTc from non-fission reactor-produced low-specific-activity 99Mo. This scenario is based on establishing a diversified chain of facilities for the distribution of 99mTc separated from reactor-produced 99Mo by (n,?3) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of 99mTc. Facilities can receive and process reactor-irradiated Mo targets then used for extraction of 99mTc over a period of 2 wk, with 3 extractions on the same day. Estimates suggest that a center receiving 1.85 TBq (50 Ci) of 99Mo once every 4 d can provide 1.48-3.33 TBq (40-90 Ci) of 99mTc daily. This model can use research reactors operating in the United States to supply current 99Mo needs by applying natural natMo targets. 99Mo production capacity can be enhanced by using 98Mo-enriched targets. The proposed model reduces the loss of 99Mo by decay and avoids proliferation as well as waste management issues associated with fission-produced 99Mo.