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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

https://doi.org/10.3769/radioisotopes.65.237

no abstracts in English

Journal Articles

Development for production of $$^{177}$$Lu and $$^{186}$$Re, $$^{188}$$Re using a research reactor

Hashimoto, Kazuyuki; Fujisaki, Saburo*

Hoshasen To Sangyo, (136), p.17 - 21, 2014/06

http://ci.nii.ac.jp/naid/40020125230

no abstracts in English

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

http://www.murr.missouri.edu/ismtr/papercall/Papers/Chiyoda%20Technol/Tanase_M=PAPER_Dev%20of%20Tc99m%20Prod%20from%20n-g%20Mo99.pdf

$$^{rm 99m}$$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

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

https://doi.org/10.1143/JPSJ.80.083201
 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.

JAEA Reports

Feasibility study of sublimation type $$^{99m}$$Tc master-milker; Comparison with PZC based wet method

Ishitsuka, Etsuo; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Norihito*; Hori, Naohiko; Awaludin, R.*; Gunawan, A. H.*; Lubis, H.*; Mutalib, A.*

JAEA-Technology 2011-019, 18 Pages, 2011/06

JAEA-Technology-2011-019.pdf:2.61MB

Feasibility study of sublimation type $$^{99m}$$Tc master-milker was carried out as a $$^{99}$$Mo/$$^{99m}$$T production development with the JMTR. As the feasibility study, the experimental equipment for sublimation method and wet method with PZC based $$^{99m}$$Tc solution were tentatively manufactured, and their properties as the master-milker were investigated by comparing two methods with each other. As a result, it was found that the $$^{99m}$$Tc recovery rate and process time of the sublimation method were about 80% and 1.5 hour, respectively, and the similar values were observed with the wet method. Superior points of the sublimation method are easier operation and reusability of the used MoO$$_{3}$$ comparing with the wet method. On the other hand, disadvantageous point is that the $$^{99m}$$Tc recovery rate decreases with the increase of treating amount of MoO$$_{3}$$.

Journal Articles

$$^{99}$$Mo production plan from $$^{98}$$Mo by (n,$$gamma$$) reaction in JMTR

Izumo, Hironobu; Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Tanase, Masakazu*; Fujisaki, Saburo*; Ota, Akio*

Proceedings of 1st Asian Symposium on Material Testing Reactors (ASMTR 2011), p.77 - 82, 2011/02

no abstracts in English

JAEA Reports

Development of $$^{rm 99m}$$Tc extraction techniques from $$^{99}$$Mo by (n,$$gamma$$) reaction

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Yuichi*

JAEA-Review 2010-053, 23 Pages, 2010/11

JAEA-Review-2010-053.pdf:2.52MB

Production techniques of $$^{99}$$Mo, parent nuclide of $$^{rm 99m}$$Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,$$gamma$$) method is proposed in JMTR because of low-amount radioactive wastes and easy $$^{rm 99m}$$Tc production process. In this study, the production of the high-density MoO$$_{3}$$ pellet and concentration techniques of $$^{rm 99m}$$Tc solution were developed. As the trial test, the MoO$$_{3}$$ pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate $$^{rm 99m}$$Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the $$^{rm 99m}$$Tc concentrating device with more than 80% concentration efficiency, was performed successfully.

Oral presentation

Refurbishment and restart of JMTR, 10; Technology development for attractive irradiation tests, 4; Extraction of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n,$$gamma$$) method

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Tanase, Masakazu*; Yamabayashi, Hisamichi*; Fujisaki, Saburo*; Sato, Yuichi*

no journal, , 

JP, 2009-264740   Patent publication (In Japanese)

To expand industrial utilization of JMTR to be reconstructed, JAEA has a plan to produce $$^{99}$$Mo (half life 65.9h), a parent nuclide of $$^{99m}$$Tc (half life 6.01h) which is used widely as radiopharmaceuticals. There are two methods for $$^{99}$$Mo production; the one is based on nuclear fission of $$^{235}$$U, and the other on neutron irradiation of natural Mo compounds. JAEA has proposed the latter method. On the other hand, the latter method also has some drawbacks that the specific activity of $$^{99}$$Mo and the concentration of $$^{99m}$$Tc in the product solution are very low. And so, to enhance the concentration of the $$^{99m}$$Tc, a method involving a process that the $$^{99m}$$Tc is extracted in methyl ethyl ketone (MEK) has proposed. In this paper, a fundamental study by using Re instead of $$^{99m}$$Tc is presented. Result, developed device can increase the concentration of $$^{99m}$$Tc solution by 20 times.

Oral presentation

Development of $$^{99m}$$Tc extraction techniques from $$^{99}$$Mo by (n,$$gamma$$) reaction

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Yuichi*

no journal, , 

Production techniques of $$^{99}$$Mo, parent nuclide of $$^{99m}$$Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,$$gamma$$) method is proposed in JMTR because of low-amount radioactive wastes and easy $$^{99m}$$Tc production process. In this study, the production of the high-density MoO$$_{3}$$ pellet and concentration techniques of $$^{99m}$$Tc solution were developed. As the trial test, the MoO$$_{3}$$ pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate $$^{99m}$$Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the $$^{99m}$$Tc concentrating device with more than 80% concentration efficiency, was performed successfully.

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.

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。

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