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Journal Articles

Technical estimation for mass production of highly-concentrated $$^{rm 99m}$$Tc solution from $$^{99}$$Mo to be obtained by ($$n,gamma$$) reaction; A Preliminary study using inactive Re instead of $$^{rm 99m}$$Tc

Tanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*; Shiina, Takayuki*; Yamabayashi, Hisamichi*; Takeuchi, Nobuhiro*; Tsuchiya, Kunihiko; Kimura, Akihiro; Suzuki, Yoshitaka; Ishida, Takuya; et al.

Radioisotopes, 65(5), p.237 - 245, 2016/05

no abstracts in English

Journal Articles

SPECT imaging of mice with $$^{99m}$$Tc-radiopharmaceuticals obtained from $$^{99}$$Mo produced by $$^{100}$$Mo(n,2n)$$^{99}$$Mo and fission of $$^{235}$$U

Hashimoto, Kazuyuki; Nagai, Yasuki; Kawabata, Masako; Sato, Nozomi*; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji*; Ota, Masayuki; Konno, Chikara; Ochiai, Kentaro; et al.

Journal of the Physical Society of Japan, 84(4), p.043202_1 - 043202_4, 2015/04

 Times Cited Count:8 Percentile:53(Physics, Multidisciplinary)

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

$$^{99}$$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

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

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

Generation of radioisotopes with accelerator neutrons by deuterons

Nagai, Yasuki; Hashimoto, Kazuyuki; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji; Sonoda, Nozomi; Kawabata, Masako; Harada, Hideo; Kin, Tadahiro*; Tsukada, Kazuaki; et al.

Journal of the Physical Society of Japan, 82(6), p.064201_1 - 064201_7, 2013/06

 Times Cited Count:43 Percentile:85.02(Physics, Multidisciplinary)

Journal Articles

Development of $$^{rm 99m}$$Tc production from (n, $$gamma$$) $$^{99}$$Mo

Tanase, Masakazu*; Shiina, Takayuki*; Kimura, Akihiro; Nishikata, Kaori; Fujisaki, Saburo*; Ota, Akio*; Kobayashi, Masaaki*; Yamamoto, Asaki*; Kawauchi, Yukimasa*; Tsuchiya, Kunihiko; et al.

Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 9 Pages, 2012/10

$$^{rm 99m}$$Tc is used as a radiopharmaceutical and manufactured from the parent nuclide of $$^{99}$$Mo. Extraction method of $$^{rm 99m}$$Tc from (n, $$gamma$$) $$^{99}$$Mo have been developed, as a part of the industrial use expansion after JMTR will re-start. In this research, the method proposed would be applicable to a practical production of $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities. The method proposed would be applicable to a practical production of $$^{rm 99m}$$Tc obtained from (n, $$gamma$$) $$^{99}$$Mo in large quantities.

Journal Articles

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

Tsuchiya, Kunihiko; Tanase, Masakazu*; Takeuchi, Nobuhiro*; Kobayashi, Masaaki*; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Kaminaga, Masanori; Ishihara, Masahiro; Kawamura, Hiroshi

Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 10 Pages, 2012/10

As one of effective uses of the JMTR, JAEA has a plan to produce $$^{99}$$Mo by (n, $$gamma$$) method, a parent nuclide of $$^{rm 99m}$$Tc. In case of Japan, the supplying of $$^{99}$$Mo depends only on imports from foreign countries. The R&D on production method of $$^{99}$$Mo -$$^{rm 99m}$$Tc has been performed with Japanese industrial users under the cooperation programs. The main R&D items for the production are (1) Fabrication of irradiation target such as the sintered MoO$$_{3}$$ pellets, (2) Separation and concentration of $$^{rm 99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{rm 99m}$$Tc solution for a medicine, and (4) Mo recycling from Mo generator and solution. In this paper, the status of the R&D is introduced for the production of $$^{99}$$Mo -$$^{rm 99m}$$Tc.

Journal Articles

Successful labeling of $$^{rm 99m}$$Tc-MDP using $$^{rm 99m}$$Tc separated from $$^{99}$$Mo produced by $$^{100}$$Mo($textit{n}$,2$textit{n}$)$$^{99}$$Mo

Nagai, Yasuki; Hatsukawa, Yuichi; Kin, Tadahiro; Hashimoto, Kazuyuki; Motoishi, Shoji; Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Sato, Yuichi*; Kawauchi, Yukimasa*; et al.

Journal of the Physical Society of Japan, 80(8), p.083201_1 - 083201_4, 2011/08

 Times Cited Count:15 Percentile:65.33(Physics, Multidisciplinary)

We have for the first time succeeded to separate $$^{rm 99m}$$Tc from a Mo oxide sample irradiated by accelerator neutrons, and to formulate $$^{rm 99m}$$Tc-methylene diphosphonate ($$^{rm 99m}$$Tc-MDP). $$^{99}$$Mo, the mother nuclide of $$^{rm 99m}$$Tc, was produced by the $$^{100}$$Mo($textit{n}$,2$textit{n}$)$$^{99}$$Mo reaction using about 14 MeV neutrons provided at the Fusion Neutronics Source of Japan Atomic Energy Agency. The $$^{rm 99m}$$Tc was separated from $$^{99}$$Mo by the sublimation method, and its radionuclide purity was confirmed to be higher than 99.99%. The labeling efficiency of $$^{rm 99m}$$Tc-MDP was shown to be higher than 99%. These values exceed the United States Pharmacopeia requirements for a fission product, $$^{99}$$Mo. Consequently, a $$^{rm 99m}$$Tc radiopharmaceutical preparation formed by using the mentioned $$^{99}$$Mo can be a promising substitute for the fission product $$^{99}$$Mo. A longstanding problem to ensure a reliable and constant supply of $$^{99}$$Mo in Japan can be partially mitigated.

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

Status of $$^{99}$$Mo/$$^{99m}$$Tc production development by (n,$$gamma$$) reaction in JMTR

Tsuchiya, Kunihiko; Sozawa, Shizuo; Takeuchi, Nobuhiro*; Suzuki, Yasuaki*; Hasegawa, Yoshio*; Kakei, Sadanori*; Araki, Masanori

no journal, , 

Technetium-99m ($$^{99m}$$Tc) is one of commonly used radioisotopes in the field of nuclear medicine. JAEA has a plan to produce $$^{99}$$Mo by (n,$$gamma$$) method, a parent nuclide of $$^{99m}$$Tc in the Japan Material Testing Reactor (JMTR). In case of Japan, all of $$^{99}$$Mo are imported from foreign countries, therefore JAEA has been performed the R&D on production of $$^{99}$$Mo/$$^{99m}$$Tc in JMTR with Japanese industrial users under the cooperation programs. The R&D on $$^{99}$$Mo/$$^{99m}$$Tc production was adopted as new project in Tsukuba International Strategic Zone, last year. In this project, various devices for production of $$^{99m}$$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$$_{3}$$ pellets, (2) Separation and concentration of $$^{99m}$$Tc by the solvent extraction from Mo solution, (3) Examination of $$^{99m}$$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 $$^{99}$$Mo/$$^{99m}$$Tc production improvement.

Oral presentation

Development of irradiation targets for $$^{99}$$Mo/$$^{99m}$$Tc production by activation method

Tsuchiya, Kunihiko; Nishikata, Kaori; Kimura, Akihiro; Ishida, Takuya; Takeuchi, Nobuhiro*; Kobayashi, Masaaki*; Kawamura, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Production of $$^{99}$$Mo using accelerator neutrons and thermochromatographic separation of $$^{99m}$$Tc

Kawabata, Masako*; Nagai, Yasuki; Hashimoto, Kazuyuki; Hatsukawa, Yuichi; Motoishi, Shoji*; Saeki, Hideya*; Sato, Nozomi*; Ota, Akio*; Shiina, Takayuki*; Kawauchi, Yukimasa*; et al.

no journal, , 

no abstracts in English

Oral presentation

Recovery and purification of $$^{99m}$$Tc isolated from $$^{99}$$MoO$$_{3}$$3 using a thermal separation technique

Kawabata, Masako*; Hashimoto, Kazuyuki; Motoishi, Shoji*; Saeki, Hideya*; Shiina, Takayuki*; Ota, Akio*; Takeuchi, Nobuhiro*; Nagai, Yasuki

no journal, , 

no abstracts in English

Oral presentation

Research and development of $$^{99}$$Mo/$$^{99m}$$Tc production process by (n,$$gamma$$) reaction under Tsukuba International Strategic Zones

Tsuchiya, Kunihiko; Kawamata, Kazuo; Takeuchi, Nobuhiro*; Ishizaki, Hiroyuki*; Niizeki, Tomotake*; Kakei, Sadanori*; Fukumitsu, Nobuyoshi*; Araki, Masanori

no journal, , 

no abstracts in English

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.

Oral presentation

R&D on $$^{99}$$Mo/$$^{99m}$$Tc separation-concentration apparatus based on solvent extraction and column chromatography

Tsuchiya, Kunihiko; Suzuki, Yoshitaka; Nishikata, Kaori; Shibata, Akira; Nakamura, Natsuki; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kawabata, Masako*; Takeuchi, Nobuhiro*

no journal, , 

no abstracts in English

17 (Records 1-17 displayed on this page)
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