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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
Tc is generated by decay of Mo. Production of 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,) method has lately attracted considerable attention. The (n,) 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 Tc with alumina column. In this paper, a practical production of Tc was tried by the method with 1Ci of Mo produced in MPR-30. The recovery yields were approximately 70%. Impurity of Mo was less than 4.010% and the radiochemical purity was over 99.2%.
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
JP, 2011-173260 Patent publication (In Japanese)This research is development of Tc production. Tc is generated by decay of Mo. The supply of Mo in Japan depends entirely on the import from foreign countries. Thus, it is needed to supply Mo stably by the domestic manufacturing. A practical production of Tc was tried by the method with 1 Ci of 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 was irradiated for 5 days in MPR-30. Impurity of Mo was less than 4.410%, 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.
Kawamura, Hiroshi
no journal, ,
no abstracts in English
Nishikata, Kaori; Kimura, Akihiro; Shiina, Takayuki*; Yamamoto, Asaki*; Ishida, Takuya; Ota, Akio*; Tanase, Masakazu*; Takeuchi, Nobuhiro*; Morikawa, Yasumasa*; Kobayashi, Masaaki*; et al.
no journal, ,
no abstracts in English
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*
【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。