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Kimura, Akihiro; Niizeki, Tomotake*; Kakei, Sadanori*; Chakrova, Y.*; Nishikata, Kaori; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Chakrov, P.*; Tsuchiya, Kunihiko
JAEA-Technology 2013-025, 40 Pages, 2013/10
Neutron Irradiation and Testing Reactor Center has developed the production of a medical isotope of Mo, the parent nuclide of Tc by the (n,) method using JMTR. The (n,) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of Tc is remaining as an issue. Therefore, PZC and PTC have been developed as adsorbent of molybdenum. Meanwhile, it is necessary to recycle the absorbent and Mo for the reduction of the radioactive waste of used-adsorbent and the effective use of limited resources, respectively. This report summarizes results of the synthesis of Mo adsorbents such as PZC and PTC, and the performance tests.
Kakei, Sadanori*; Kimura, Akihiro; Niizeki, Tomotake*; Ishida, Takuya; Nishikata, Kaori; Kurosawa, Makoto; Yoshinaga, Hideo*; Hasegawa, Yoshio*; Tsuchiya, Kunihiko
Proceedings of 6th International Symposium on Material Testing Reactors (ISMTR-6) (Internet), 7 Pages, 2013/10
The Japan Materials Testing Reactor (JMTR) is expected to contribute to the expansion of industrial utilization, such as the domestic production of Mo for the medical diagnosis medicine Tc. Production by the (n, ) method is proposed as domestic Mo production in JMTR because of the low amount of radioactive wastes and the easy Mo/Tc production process. Molybdenum oxide (MoO) pellets, poly zirconium compounds (PZC) and poly titanium compounds (PTC) are used as the irradiation target and generator for the production of Mo/Tc by the (n, ) method. However, it is necessary to use the enriched MoO, which is very expensive, to increase the specific activity of Mo. Additionally, a large amount of used PZC and PTC is generated after the decay of Mo. Therefore, this recycling technology of used PZC/PTC has been developed to recover molybdenum (Mo) as an effective use of resources and a reduction of radioactive wastes. The total Mo recovery rate of this process was 95.8%. From the results of the hot experiments, we could demonstrate that the recovery of MoO and the recycling of PZC are possible. In the future, the equipment of recovering Mo will be installed in JMTR-Hot Cell, and this recycling process will be able to contribute to the reduction of production costs of Tc and the reduction of radioactive wastes.
Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori
no journal, ,
Technetium-99m (Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce Mo by (n,) method, a parent nuclide of Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of Mo/Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on Mo/Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of 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 pellets, (2) Separation and concentration of Tc by the solvent extraction from Mo solution, (3) Examination of 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 Mo/Tc production improvement.
Tsuchiya, Kunihiko; Kawamata, Kazuo; Takeuchi, Nobuhiro*; Ishizaki, Hiroyuki*; Niizeki, Tomotake*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Araki, Masanori
no journal, ,
no abstracts in English
Suzuki, Yoshitaka; Namekawa, Yoji*; Kitagawa, Tomoya*; Kakei, Sadanori*; Matsukura, Minoru*; Yoshinaga, Hideo*; Mimura, Hitoshi*; Tsuchiya, Kunihiko
no journal, ,
no abstracts in English
Nishikata, Kaori; Kimura, Akihiro; Kato, Yoshiaki; Kurosawa, Makoto; Ishida, Takuya; Tsuchiya, Kunihiko; Kakei, Sadanori*; Yoshinaga, Hideo*; Niizeki, Tomotake*; Hasegawa, Yoshio*
no journal, ,
no abstracts in English
Nishikata, Kaori; Kimura, Akihiro; Kakei, Sadanori*; Niizeki, Tomotake*; Ishida, Takuya; Yoshinaga, Hideo*; Hasegawa, Yoshio*; Tsuchiya, Kunihiko
no journal, ,
Every year in Japan, nuclear medical of about 900,000 cases are carried out using technetiume-99m (Tc). It is ranked as the second in the world. But all of the Tc is imported from the other countries. Therefore, we are developing the (n, ) method for Mo production, as part of "increase of industrial use" in resumed operations after restart of Japan Materials Tasting Reactor (JMTR). In the study to establish the Mo production method through the (n, ) process domestically using the JMTR, three different MoO powders such as fresh, recycled and Mo enriched ones were selected, and characterized as in SEM and sintering. As a result, the high dense MoO pellet manufactured by the fresh powder attained over 90%T. D. at the sintering temperature of 500C. On the other hand, pellets manufactured by the other powders needs sintering temperature above 580C to attain over 90%T.D., resulting in an influence on the particle size and shape dependences for the sintering property.
Yoshinaga, Hideo*; Kakei, Sadanori*; Tanimoto, Masataka; Kimura, Akihiro; Tsuchiya, Kunihiko
no journal, ,
no abstracts in English
Tsuchiya, Kunihiko; Shibata, Tokushi*; Uno, Tsuyoshi*; Hasegawa, Yoshio*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Kusunoki, Tsuyoshi; Kaminaga, Masanori
no journal, ,
no abstracts in English
Nishikata, Kaori; Kimura, Akihiro; Kato, Yoshiaki; Kurosawa, Makoto; Ishida, Takuya; Tsuchiya, Kunihiko; Kakei, Sadanori*; Yoshinaga, Hideo*; Niizeki, Tomotake*; Hasegawa, Yoshio*
no journal, ,
no abstracts in English