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Oral presentation

Status of $$^{99}$$Mo/$$^{99m}$$Tc production development by (n,$$gamma$$) reaction in JMTR

Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori

no journal, , 

Technetium-99m ($$^{99m}$$Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce $$^{99}$$Mo by (n,$$gamma$$) method, a parent nuclide of $$^{99m}$$Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of $$^{99}$$Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of $$^{99}$$Mo/$$^{99m}$$Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on $$^{99}$$Mo/$$^{99m}$$Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of $$^{99m}$$Tc solution will be equipped the hot cell in the JMTR Hot laboratory and the following R&D items will be carried out for the production improvement. (1) Fabrication of irradiation target such as the sintered MoO$$_{3}$$ pellets, (2) Separation and concentration of $$^{99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{99m}$$Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this symposium, the status of the R&D and construction of the PIE devices under this project will be introduced for the production of $$^{99}$$Mo/$$^{99m}$$Tc production improvement.

Oral presentation

Current status and developments of post irradiation examination techniques in JMTR Hot laboratory

Shibata, Akira; Taguchi, Taketoshi; Aoyagi, Tatsuhiko; Ito, Masayasu; Kato, Yoshiaki; Yonekawa, Minoru; Kawamata, Kazuo

no journal, , 

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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