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

被引:13
|
作者
Pillai, Maroor R. A. [1 ]
Dash, Ashutosh [2 ]
Knapp, Furn F. , Jr. [3 ]
机构
[1] Mol Grp Co, Cochin, Kerala, India
[2] Bhabha Atom Res Ctr, Isotope Prod & Applicat Div, Bombay 400085, Maharashtra, India
[3] Oak Ridge Natl Lab, Med Radioisotope Program, Oak Ridge, TN 27830 USA
关键词
Mo-99; Tc-99m; fission moly; reactor production; cyclotron production;
D O I
10.2967/jnumed.114.149609
中图分类号
R8 [特种医学]; R445 [影像诊断学];
学科分类号
1002 ; 100207 ; 1009 ;
摘要
This paper discusses the benefits of obtaining Tc-99m from non-fission reactor-produced low-specific-activity Mo-99. This scenario is based on establishing a diversified chain of facilities for the distribution of (99)mTc separated from reactor-produced Mo-99 by (n,Y) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of (99)mTc. Facilities can receive and process reactor-irradiated Mo targets then used for extraction of (99)mTc 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 Mo-99 once every 4 d can provide 1.48-3.33 TBq (40-90 Ci) of (99)mTc daily. This model can use research reactors operating in the United States to supply current Mo-99 needs by applying natural Mo-nat targets. Mo-99 production capacity can be enhanced by using Mo-98-enriched targets. The proposed model reduces the loss of Mo-99 by decay and avoids proliferation as well as waste management issues associated with fission-produced Mo-99.
引用
收藏
页码:159 / 161
页数:3
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