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Journal Articles

$$^{99}$$Mo-$$^{rm 99m}$$Tc production process by (n,$$gamma$$) reaction with irradiated high-density MoO$$_{3}$$ pellets

Tsuchiya, 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

Oral presentation

Development of extraction and concentration system of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n,$$gamma$$) method

Tanase, 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 $$^{99m}$$Tc from, (n,$$gamma$$)$$^{99}$$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 $$^{99m}$$Tc, a method was proposed for extracting $$^{99m}$$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 $$^{99m}$$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 $$^{99m}$$Tc production was assembled.

Oral presentation

Development of $$^{99}$$Mo-$$^{99m}$$Tc domestic production with high-density MoO$$_{3}$$ pellets by (n,$$gamma$$) reaction

Tsuchiya, Kunihiko; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kobayashi, Masaaki*; Morikawa, Yasumasa*; Yamamoto, Asaki*; Kaminaga, Masanori; Kawamura, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Preliminary experiments for $$^{99}$$Mo/$$^{99m}$$Tc production using irradiated MoO$$_{3}$$ pellets

Nishikata, 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

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.

Oral presentation

R&D on separation, concentration and recovery of $$^{99m}$$Tc from $$^{99}$$Mo for commercial production

Shiina, 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 $$^{99}$$Mo/$$^{99m}$$Tc generator and $$^{99m}$$Tc injections ($$^{99m}$$Tc labeled pharmaceuticals) continues to account for approximately 80% of the entire in-vivo supply in Japan. Furthermore, the number of $$^{99m}$$Tc injection supplies is approximately four times larger than that of the $$^{99}$$Mo/$$^{99m}$$Tc generator. Therefore, Chiyoda Technol Co. have performed a research and development (R&D) for the domestic production of $$^{99m}$$Tc in cooperation with the Japan Atomic Energy Agency (JAEA) and FUJIFILM RI pharma Co., Ltd. to ensure a constant and reliable supply of $$^{99m}$$Tc. CTC therefore has a plan to stably produce $$^{99m}$$Tc from $$^{99}$$Mo, which can be produced by the $$^{98}$$Mo(n,$$gamma$$) reaction using the Japan Materials Testing Reactor (JMTR) and by the $$^{100}$$Mo(n,2n) reaction using some new cyclotrons, and thereby to meet the Japanese demand for $$^{99m}$$Tc together with pharmaceutical companies in Japan. These production methods of $$^{99}$$Mo were selected from viewpoints of safety, nuclear proliferation resistance and waste management. The specific activity of $$^{99}$$Mo produced by these methods, however, is very low compared with that of (n,f)$$^{99}$$Mo. Therefore, it is essential to develop some techniques for separation, concentration and recovery of $$^{99m}$$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 $$^{99}$$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 $$^{99m}$$Tc.

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