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Journal Articles

Development of $$^{rm 99m}$$Tc production from (n, $$gamma$$) $$^{99}$$Mo

Tanase, Masakazu*; Shiina, Takayuki*; Kimura, Akihiro; Nishikata, Kaori; Fujisaki, Saburo*; Ota, Akio*; Kobayashi, Masaaki*; Yamamoto, Asaki*; Kawauchi, Yukimasa*; Tsuchiya, Kunihiko; et al.

Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10

http://www.murr.missouri.edu/ismtr/papercall/Papers/Chiyoda%20Technol/Tanase_M=PAPER_Dev%20of%20Tc99m%20Prod%20from%20n-g%20Mo99.pdf

$$^{rm 99m}$$Tc is used as a radiopharmaceutical and manufactured from the parent nuclide of $$^{99}$$Mo. Extraction method of $$^{rm 99m}$$Tc from (n, $$gamma$$) $$^{99}$$Mo have been developed, as a part of the industrial use expansion after JMTR will re-start. In this research, the method proposed would be applicable to a practical production of $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities. The method proposed would be applicable to a practical production of $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities.

Oral presentation

Extraction Properties of $$^{99m}$$Tc from irradiated High-density MoO$$_{3}$$ Pellets Solution

Shibata, Akira; Ishida, Takuya; Shiina, Takayuki*; Kobayashi, Masaaki*; Tanase, Masakazu*; Kato, Yoshiaki; Kimura, Akihiro; Ota, Akio*; Yamamoto, Asaki*; Morikawa, Yasumasa*; et al.

no journal, , 

$$^{99m}$$Tc, a daughter nuclide of $$^{99}$$Mo, is commonly used as a radiopharmaceutical. In case of Japan, all of $$^{99}$$Mo are imported from foreign countries. R&D for domestic production of $$^{99}$$Mo by the (n, $$gamma$$) method has been being performed in JMTR from viewpoints of nuclear proliferation resistance and waste management. In this study, experiments of $$^{99}$$Mo/$$^{99m}$$Tc production were performed to enhance recovery yields of $$^{99m}$$Tc. High-density MoO$$_{3}$$ pellets were irradiated in the Kyoto University Reactor (KUR). Solvent extraction method with MEK was used to extract $$^{99m}$$Tc from $$^{99}$$Mo/$$^{99m}$$Tc solution and the maximum recovery yields as high as 80% was achieved. Quality tests were performed, and impurities in $$^{99m}$$Tc solution were evaluated and were efficiently low. It is concluded that $$^{99m}$$Tc solution produced by this method is suitable for a raw material of radiopharmaceutical.

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