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First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Thomas E. Blue
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 304-310
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT88-A34131
Articles are hosted by Taylor and Francis Online.
An accelerator-based 145Sm production method is described. A target of a natural samarium compound, for example, Sm2O3, is bombarded with protons in the 70-MeV energy range. The resulting nuclear reactions produce 145Eu as well as other europium isotopes that are chemically separated from the samarium target. If this separation is performed more than 15 min following the irradiation, then only 145Eu and europium isotopes with half-lives longer than the halflife of 145Eu remain in the europium fraction. Following the first separation, the separated europium undergoes radioactive decay until most of the 145Eu in the europium fraction has decayed into 145Sm. Then, a second chemical separation is performed in which the 145Sm is removed from the long-lived europium radioactivities that accompanied the 145Eu in the first separation. The result of the two chemical separations is a high-specific-activity 145Sm product with contaminations from europium radioactivities that depend on the efficiencies of the separations and the time of their performance. The 145Sm yield and purity for this production method for a high-current accelerator are compared with the yield and purity of 145Sm from a reactor-based production method for a high-flux reactor. The yield of 145Sm/day for the accelerator-based production method exceeds the yield per day for the reactor-based production method for reactor targets less than ∼1 g. For modest ratios of europium-to-samarium separation efficiencies for the first separation (∼10), the specific activity of the accelerator-produced 145Sm exceeds the specific activity of the reactor-produced 145Sm for reactor irradiation times <2 days. However, the activity of the 145Sm contaminants is larger for the accelerator-produced 145Sm than for the reactor-produced 145Sm, unless the ratio of europiumto-samarium separation efficiencies for the second separation is greater than ∼5000.