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Orano Med inaugurates Pb-212 production facility in Indiana
Guillaume Dureau of Orano Group (left) and Orano Med’s Julien Dodet cut the ribbon on the new ATLabs Indianapolis. (Photo: Orano)
Orano Group subsidiary Orano Med, a developer of targeted alpha therapies for oncology, inaugurated its first ATLab (Alpha Therapy Laboratory) earlier this month. Located in Brownsburg, near Indianapolis, Ind., ATLab Indianapolis is an industrial-scale pharmaceutical facility dedicated to the production of lead-212–based radioligand therapies.
Targeted alpha therapy has shown to be effective in treating various oncological diseases, combining the natural ability of biological molecules to target cancer cells with the short-range cell-killing capabilities of alpha emissions generated by Pb-212. With a half-life of 10.64 hours, along with a decay product of the short-lived alpha-emitter bismuth-212, Pb-212 allows for the possible synthesis and purification of complex radiopharmaceuticals with minimum loss of radioactivity during preparation.
The development of radiopharmaceuticals has long been hampered by the difficulty of manufacturing and distribution on an industrial scale, Orano said, adding that the construction of ATLab Indianapolis is a major step toward making these new treatments available to cancer patients with high unmet needs in North America.
Jack D. Law, R. Scott Herbst, Dean R. Peterman, Rich D. Tillotson, Terry A. Todd
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 284-290
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3532
Articles are hosted by Taylor and Francis Online.
A chlorinated cobalt dicarbollide(CCD)/polyethylene glycol (PEG) based solvent extraction process is being developed for the separation of Cs and Sr from leached spent light water reactor (LWR) fuel as part of the Advanced Fuel Cycle Initiative (AFCI). The separation of Cs and Sr would significantly reduce the heat generation of spent nuclear fuel requiring geologic disposal. A solvent composition for this process has been verified, and the distribution coefficient acid dependency for Cs, Sr, Am, and Eu have been measured for the CCD/PEG solvent. Leached spent fuel simulant, traced with 137Cs, 85Sr, 241Am, and 154Eu, was used to perform batch contact flowsheet experiments for the extraction, scrub, and strip sections of the CCD/PEG process. Additionally, the effects of acetohydroxamic acid and its decomposition products, as well as the effects of the uranium extraction (UREX) process solvent, on the extraction of Cs and Sr with the CCD/PEG process were evaluated.