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Mo-
Tc production process by (n,
) reaction with irradiated high-density MoO
pelletsTsuchiya, Kunihiko; Nishikata, Kaori; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kobayashi, Masaaki*; Yamamoto, Asaki*; Morikawa, Yasumasa*; Takeuchi, Nobuhiro*; Kaminaga, Masanori; et al.
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 9 Pages, 2013/10
no abstracts in English
Tc from Mo produced by (n,) methodTanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Fujisaki, Saburo*; Kawauchi, Yukimasa*; Kimura, Akihiro; Nishikata, Kaori; Yonekawa, Minoru; Ishida, Takuya; Kato, Yoshiaki; et al.
no journal, ,
Preliminary studies for obtaining Tc from, (n,)Mo produced in JMTR has been carried out, as a part of the industrial use expansion after JMTR will re-start. In order to obtain high specific-volume of Tc, a method was proposed for extracting Tc with MEK, followed by purification and concentration with acidic and basic alumina. In this study, preliminary tests, aiming construction of production system, were carried out using Re instead of Tc because Re and Tc are homologous elements. The average recovery yield of Re was very high to be 98%. Based on the result, an apparatus for Tc production was assembled.
Mo-Tc domestic production with high-density MoO pellets by (n,) reactionTsuchiya, Kunihiko; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kobayashi, Masaaki*; Morikawa, Yasumasa*; Yamamoto, Asaki*; Kaminaga, Masanori; Kawamura, Hiroshi
no journal, ,
no abstracts in English
Tc from Mo for commercial productionShiina, Takayuki*; Tsuchiya, Kunihiko; Nagai, Yasuki; Morikawa, Yasumasa*; Takeuchi, Nobuhiro*
no journal, ,
According to statistical data reported by the Japan Radioisotope Association (JRIA) in 2014, the Mo/Tc generator and Tc injections (Tc labeled pharmaceuticals) continues to account for approximately 80% of the entire in-vivo supply in Japan. Furthermore, the number of Tc injection supplies is approximately four times larger than that of the Mo/Tc generator. Therefore, Chiyoda Technol Co. have performed a research and development (R&D) for the domestic production of Tc in cooperation with the Japan Atomic Energy Agency (JAEA) and FUJIFILM RI pharma Co., Ltd. to ensure a constant and reliable supply of Tc. CTC therefore has a plan to stably produce Tc from Mo, which can be produced by the 
Mo(n,) reaction using the Japan Materials Testing Reactor (JMTR) and by the 
Mo(n,2n) reaction using some new cyclotrons, and thereby to meet the Japanese demand for Tc together with pharmaceutical companies in Japan. These production methods of Mo were selected from viewpoints of safety, nuclear proliferation resistance and waste management. The specific activity of Mo produced by these methods, however, is very low compared with that of (n,f)Mo. Therefore, it is essential to develop some techniques for separation, concentration and recovery of Tc, and it will be necessary to choose the best methods such as a wet method by solvent extraction and a dry method by sublimation, finally. In future, we aim to provide to about 20% of the domestic demand for Mo using the JMTR and cyclotrons, 100-200 6-day Ci per week at the end of irradiation, and will carry out empirical studies for the commercial production of Tc.
Mo/Tc production using irradiated MoO pelletsNishikata, Kaori; Kimura, Akihiro; Shiina, Takayuki*; Yamamoto, Asaki*; Ishida, Takuya; Ota, Akio*; Tanase, Masakazu*; Takeuchi, Nobuhiro*; Morikawa, Yasumasa*; Kobayashi, Masaaki*; et al.
no journal, ,
JP, 2011-173260 
Patent publication (In Japanese)
no abstracts in English
Tc from irradiated High-density MoO Pellets SolutionShibata, Akira; Ishida, Takuya; Shiina, Takayuki*; Kobayashi, Masaaki*; Tanase, Masakazu*; Kato, Yoshiaki; Kimura, Akihiro; Ota, Akio*; Yamamoto, Asaki*; Morikawa, Yasumasa*; et al.
no journal, ,
Tc, a daughter nuclide of Mo, is commonly used as a radiopharmaceutical. In case of Japan, all of Mo are imported from foreign countries. R&D for domestic production of Mo by the (n, ) method has been being performed in JMTR from viewpoints of nuclear proliferation resistance and waste management. In this study, experiments of Mo/Tc production were performed to enhance recovery yields of Tc. High-density MoO pellets were irradiated in the Kyoto University Reactor (KUR). Solvent extraction method with MEK was used to extract Tc from Mo/Tc solution and the maximum recovery yields as high as 80% was achieved. Quality tests were performed, and impurities in Tc solution were evaluated and were efficiently low. It is concluded that Tc solution produced by this method is suitable for a raw material of radiopharmaceutical.
