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Journal Articles

Development of $$^{99m}$$Tc production from (n,$$gamma$$)$$^{99}$$Mo based on solvent extraction

Kimura, Akihiro; Awaludin, R.*; Shiina, Takayuki*; Tanase, Masakazu*; Kawauchi, Yukimasa*; Gunawan, A. H.*; Lubis, H.*; Sriyono*; Ota, Akio*; Genka, Tsuguo; et al.

Proceedings of 3rd Asian Symposium on Material Testing Reactors (ASMTR 2013), p.109 - 115, 2013/11

JP, 2011-173260   Patent publication (In Japanese)

$$^{99m}$$Tc is generated by decay of $$^{99}$$Mo. Production of $$^{99}$$Mo is carried out by (n,f) method with high enriched uranium targets, and the production are currently producing to meet about 95% of global supply. Recently, it is difficult to carry out a stable supply for some problems such as aging of reactors etc. Furthermore, the production has difficulties in nuclear proliferation resistance etc. Thus, (n,$$gamma$$) method has lately attracted considerable attention. The (n,$$gamma$$) method has several advantages, but the extremely low specific activity makes its uses less convenient than (n,f) method. We proposed a method based on the solvent extraction, followed by adsorption of $$^{99m}$$Tc with alumina column. In this paper, a practical production of $$^{99m}$$Tc was tried by the method with 1Ci of $$^{99}$$Mo produced in MPR-30. The recovery yields were approximately 70%. Impurity of $$^{99}$$Mo was less than 4.0$$times$$10$$^{-5}$$% and the radiochemical purity was over 99.2%.

Journal Articles

Development of $$^{99m}$$Tc production from (n,$$gamma$$)$$^{99}$$Mo based on solvent extraction and column chromatography

Kimura, Akihiro; Awaludin, R.*; Shiina, Takayuki*; Tanase, Masakazu*; Kawauchi, Yukimasa*; Gunawan, A. H.*; Lubis, H.*; Sriyono*; Ota, Akio*; Genka, Tsuguo; et al.

Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 7 Pages, 2013/10

http://www.invap.com.ar/ismtr/images/stories/trabajos/Ohta-Paper.pdf
http://www.invap.com.ar/ismtr/images/stories/trabajos/Ohta-Presentation.pdf
JP, 2011-173260   Patent publication (In Japanese)

This research is development of $$^{99m}$$Tc production. $$^{99m}$$Tc is generated by decay of $$^{99}$$Mo. The supply of $$^{99}$$Mo in Japan depends entirely on the import from foreign countries. Thus, it is needed to supply $$^{99}$$Mo stably by the domestic manufacturing. A practical production of $$^{99m}$$Tc was tried by the method with 1 Ci of $$^{99}$$Mo produced in MPR-30. The results showed that the recovery yields were approximately 70%. The concentration of the product obtained was estimated to be corresponding to about 30 GBq (800 mCi)/ml when 150g of MoO$$_{3}$$ was irradiated for 5 days in MPR-30. Impurity of $$^{99}$$Mo was less than 4.4$$times$$10$$^{-5}$$%, which was lower than that of Japanese tentative regulation criteria. The radiochemical purity was higher than 99.8% that cleared the tentative regulation (95%) of Japan.

Journal Articles

Development of $$^{rm 99m}$$Tc extraction-recovery by solvent extraction method

Kimura, Akihiro; Nishikata, Kaori; Tanase, Masakazu*; Fujisaki, Saburo*; Izumo, Hironobu; Tsuchiya, Kunihiko; Shiina, Takayuki*; Ota, Akio*; Takeuchi, Nobuhiro*; Ishihara, Masahiro

JAEA-Conf 2011-003, p.147 - 150, 2012/03

https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2011-003.pdf
JP, 2011-173260   Patent publication (In Japanese)

$$^{rm 99m}$$Tc is used as a radiopharmaceutical in the medical field for the diagnosis, and manufactured from $$^{99}$$Mo, the parent nuclide. In this study, the solvent extraction with MEK was selected, and preliminary experiments were carried out using Re instead of $$^{99m}$$Tc. Two tests were carried out in the experiments; the one is the Re extraction test with MEK from Re-Mo solution, the other is the Re recovery test from the Re-MEK. As to the Re extraction test, and it was clear that the Re extraction yield was more than 90%. Two kinds of Re recovery tests, which are an evaporation method using the evaporator and an adsorption/elution method using the alumina column, were carried out. As to the evaporation method, the Re concentration in the collected solution increased more than 150 times. As to the adsorption/elution method, the Re concentration increased in the eluted solution more than 20 times.

Patent

高濃度かつ高放射能をもつテクネチウム-99m溶液の製造方法

木村 明博; 西方 香緒里; 土谷 邦彦; 石原 正博

棚瀬 正和*; 藤崎 三郎*; 太田 朗生*

JP, 2011-173260  Patent licensing information  Patent publication (In Japanese)

【課題】これまでの時間当たりに製造される99mTc溶液の量及び濃度を格段に超え、実用に供することができる、高濃度かつ高放射能をもつ99mTc溶液を得るための製造方法を提供すること。 【解決手段】99MoO3ペレットとアルカリ溶液を撹拌して、99MoO3をアルカリ溶液に溶解させ、溶解した99Moに比較的少量のMEKを供給し、撹拌することにより、99Moから生成する 99mTcを抽出した後、99mTc含有MEK相と水相に分離させ、分離した99mTc含有MEK相を、塩基性アルミナカラムを介して精製し、次いで酸性アルミナカラムにおいて99mTc含有ケトンMEKから99mTcを酸性アルミナカラムに吸着濃縮させ、比較的少量の生理食塩水を用いて酸性アルミナカラムから溶離する。

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

Development for domestic production of $$^{99}$$Mo/$$^{rm 99m}$$Tc with (n,$$gamma$$) method at JMTR

Kawamura, Hiroshi

no journal, , 

JP, 2011-173260   Patent publication (In Japanese)

no abstracts in English

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