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Journal Articles

Production of no-carrier-added $$^{177}$$Lu via the $$^{176}$$Yb(n,$$gamma$$)$$^{177}$$Yb$$rightarrow$$$$^{177}$$Lu process

Hashimoto, Kazuyuki; Matsuoka, Hiromitsu; Uchida, Shoji*

Journal of Radioanalytical and Nuclear Chemistry, 255(3), p.575 - 579, 2003/03

https://doi.org/10.1023/A:1022557121351
 Times Cited Count：42 Percentile：91.79(Chemistry, Analytical)

The $$beta^{-}$$ emitter $$^{177}$$Lu is a promising therapeutic radioisotope for the treatment of cancer. It has a half-life of 6.73 days and maximum $$beta^{-}$$ energy of 498 keV, resulting in a short range of radiation in tissue. The decay is accompanied by the emission of low energy $$gamma$$-radiation with $$E_{gamma}$$ = 208 keV (11.0%) and 113 keV (6.4%) suitable for simultaneous imaging. Lutetium-177 can be usually produced at nuclear reactors with high yield and high specific radioactivity by the $$^{176}$$Lu(n,$$gamma$$)$$^{177}$$Lu reaction. However, radioisotopes with higher specific radioactivity are required in the field of radioimmunotherapy using labeled monoclonal antibodies. Thus, an alternative production route, namely the $$^{176}$$Yb(n,$$gamma$$)$$^{177}$$Yb $$rightarrow$$ $$^{177}$$Lu process was studied to produce no-carrier-added (nca) $$^{177}$$Lu in this work. The radiochemical separation of the nca $$^{177}$$Lu from the macroscopic ytterbium target was investigated by means of reversed-phase ion-pair HPLC. The nca $$^{177}$$Lu was obtained in radiochemical pure form with a separation yield of 80%.

Oral presentation

R&D on $$^{99}$$Mo/$$^{99m}$$Tc separation-concentration apparatus based on solvent extraction and column chromatography

Tsuchiya, Kunihiko; Suzuki, Yoshitaka; Nishikata, Kaori; Shibata, Akira; Nakamura, Natsuki; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kawabata, Masako*; Takeuchi, Nobuhiro*

no journal, , 

no abstracts in English

Oral presentation

Development of inorganic ion exchangers for separation of $$^{99}$$Mo/$$^{rm 99m}$$Tc

Hu, X.; Suzuki, Tatsuya*; Wang, X.*; Wang, H.*; Fujita, Yoshitaka; Tsuchiya, Kunihiko

no journal, , 

Technetium-99m ($$^{rm 99m}$$Tc) stands as the most widely employed radionuclide for nuclear medicine diagnostic imaging procedures. $$^{99m}$$Tc originates from the radioactive decay of molybdenum-99 ($$^{99}$$Mo). In present study, four inorganic ion exchangers were synthesized by combining SnCl$$_{4}$$ with SbCl$$_{5}$$, WO$$_{2}$$Cl$$_{2}$$, WO$$_{3}$$, and TiCl$$_{4}$$ in a one-to-one for application to the separation of $$^{rm 99m}$$Tc and $$^{99}$$Mo by column chromatography approach. We conducted comparing and evaluating their respective Kd (distribution coefficient) values. We utilized these synthesized inorganic ion exchangers for adsorption in a solution with a prepared concentration of 4 ppm of Mo/Re, where Re acted as a surrogate element to simulate Tc. Various pH environments ranging from 2 to 12 were prepared. Subsequently, we conducted adsorption experiments using batch testing and determined the Kd values. The results revealed that all four ion exchangers exhibit commendable selectivity and relatively high Kd values, with SnCl$$_{4}$$-TiCl$$_{4}$$ demonstrating the highest Kd.

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