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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

JAEA Reports

Establishment of experimental system for $$^{99}$$Mo/$$^{99m}$$Tc production by neutron activation method

Ishida, Takuya; Shiina, Takayuki*; Ota, Akio*; Kimura, Akihiro; Nishikata, Kaori; Shibata, Akira; Tanase, Masakazu*; Kobayashi, Masaaki*; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

JAEA-Technology 2015-030, 42 Pages, 2015/11

JAEA-Technology-2015-030.pdf:4.82MB

The research and development (R&D) on the production of $$^{99}$$Mo/$$^{99m}$$Tc by neutron activation method ((n, $$gamma$$) method) using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center. The specific radioactivity of $$^{99}$$Mo by (n, $$gamma$$) method is extremely low compared with that by fission method ((n,f) method), and as a result, the radioactive concentration of the obtained $$^{99m}$$Tc solution is also lowered. To solve the problem, we propose the solvent extraction with methyl ethyl ketone (MEK) for recovery of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n, $$gamma$$) method. We have developed the $$^{99}$$Mo/$$^{99m}$$Tc separation/extraction/concentration devices and have carried out the performance tests for recovery of $$^{99m}$$Tc from $$^{99}$$Mo produced by (n, $$gamma$$) method. In this paper, in order to establish an experimental system for $$^{99}$$Mo/$$^{99m}$$Tc production, the R&D results of the system are summarized on the improvement of the devices for high-recovery rate of $$^{99m}$$Tc, on the dissolution of the pellets, which is the high-density molybdenum trioxide (MoO$$_{3}$$) pellets irradiated in Kyoto University Research Reactor (KUR), on the production of $$^{99m}$$Tc, and on the inspection of the recovered $$^{99m}$$Tc solutions.

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

https://doi.org/10.7566/JPSJ.84.043202
 Times Cited Count：7 Percentile：51.13(Physics, Multidisciplinary)

Journal Articles

New phenomenon observed in thermal release of $$^{99m}$$Tc from molten $$^{100}$$MoO$$_{3}$$

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

Journal of the Physical Society of Japan, 84(2), p.023201_1 - 023201_4, 2015/02

https://doi.org/10.7566/JPSJ.84.023201
 Times Cited Count：6 Percentile：46.87(Physics, Multidisciplinary)

$$^{99m}$$Tc for medical use can be separated by thermochromatography from a molten $$^{99}$$MoO$$_{3}$$ sample. Effect of moist oxygen gas on the $$^{99m}$$Tc release from molten $$^{99}$$MoO$$_{3}$$ samples was investigated using a $$^{99}$$Mo/$$^{99m}$$Tc generator. $$^{99}$$Mo was produced with $$^{100}$$Mo(n,2n)$$^{99}$$Mo. A new phenomenon has been observed: release rate, separation- and recovery-efficiencies of $$^{99m}$$Tc were higher in the moist oxygen gas than those in the dry oxygen gas. The present result is a significant progress towards the stable production of a high quality $$^{99m}$$Tc from a molten MoO$$_{3}$$ sample with high separation efficiency. The result would also give us a new insight into the interaction between the moist oxygen gas and the molten MoO$$_{3}$$.

JAEA Reports

Fabrication technology development and characterization of irradiation targets for $$^{99}$$Mo/$$^{rm 99m}$$Tc production by (n,$$gamma$$) method

Nishikata, Kaori; Kimura, Akihiro; Ishida, Takuya; Shiina, Takayuki*; Ota, Akio*; Tanase, Masakazu*; Tsuchiya, Kunihiko

JAEA-Technology 2014-034, 34 Pages, 2014/10

JAEA-Technology-2014-034.pdf:3.26MB

As a part of utilization expansion after the Japan Material Testing Reactor (JMTR) re-start, research and development (R&D) on the production of medical radioisotope $$^{99}$$Mo/$$^{99m}$$Tc by (n, $$gamma$$) method using JMTR has been carried out in the Neutron Irradiation and Testing Reactor Center of the Japan Atomic Energy Agency. $$^{99}$$Mo is usually produced by fission method. On the other hand, $$^{99}$$Mo/$$^{99m}$$Tc production by the (n, $$gamma$$) method has advantages for radioactive waste, cost reduction and non-proliferation. However, the specific radioactivity per unit volume by the (n, $$gamma$$) method is low compared with the fission method, and that is the weak point of the (n, $$gamma$$) method. This report summarizes the investigation of raw materials, the fabrication tests of high-density MoO$$_{3}$$ pellets by the plasma sintering method for increasing of $$^{98}$$Mo contents and the characterization of sintered high-density MoO$$_{3}$$ pellets.

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

http://www.invap.com.ar/ismtr/images/stories/trabajos/Tsuchiya-Paper.pdf
http://www.invap.com.ar/ismtr/images/stories/trabajos/Tsuchiya-Presentation.pdf

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

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

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

https://doi.org/10.7566/JPSJ.82.064201
 Times Cited Count：41 Percentile：85.53(Physics, Multidisciplinary)

Journal Articles

Fabrication and characterization of high-density MoO$$_{3}$$ pellets

Nishikata, Kaori; Kimura, Akihiro; Shiina, Takayuki*; Ota, Akio*; Tanase, Masakazu*; Tsuchiya, Kunihiko

Proceedings of 2012 Powder Metallurgy World Congress & Exhibition (PM 2012) (CD-ROM), 8 Pages, 2013/02

The renewed Japan Materials Testing Reactor (JMTR) will be started from 2012, and it is expected to contribute to many nuclear fields. Especially, in case of Japan, the supplying of $$^{99}$$Mo depends on imports from foreign countries. Japan Atomic Energy Agency (JAEA) has a plan to produce $$^{99}$$Mo, which is the parent nuclide of radiopharmaceutical $$^{rm 99m}$$Tc, and JAEA has performed the R&D for $$^{99}$$Mo production by (n,$$gamma$$) method in JMTR. Generally, molybdenum oxide (MoO$$_{3}$$) is the most popular chemical form as irradiation target for the $$^{99}$$Mo production. However, the $$^{99}$$Mo production capacity is low because of low (n,$$gamma$$) cross section and isotope composition of $$^{98}$$Mo in Mo. Thus, it is necessary to fabricate the MoO$$_{3}$$ pellets with high density for the increase of the $$^{99}$$Mo production amount. In this study, MoO$$_{3}$$ pellets fabricated by a plasma activated sintering were developed and characterization of MoO$$_{3}$$ pellets was carried out.

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.

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.

Oral presentation

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

Tsuchiya, Kunihiko; Tanase, Masakazu*; Shiina, Takayuki*; Ota, Akio*; Kobayashi, Masaaki*; Morikawa, Yasumasa*; Yamamoto, Asaki*; Kaminaga, Masanori; Kawamura, Hiroshi

no journal, , 

no abstracts in English

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

High quality $$^{99m}$$Tc obtained from $$^{99}$$Mo produced by $$^{100}$$Mo(n,2n) using accelerator neutrons

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

no journal, , 

$$^{99m}$$Tc, the daughter nuclide of $$^{99}$$Mo, is widely used for medical diagnosis. In Japan, about 0.9 million diagnostic procedures are carried out using $$^{99m}$$Tc. $$^{99}$$Mo has been mostly produced using $$^{235}$$U in research reactors. Because of recent shortages of $$^{99}$$Mo, a variety of alternative production methods of $$^{99}$$Mo or $$^{99m}$$Tc were proposed. We proposed to produce $$^{99}$$Mo by $$^{100}$$Mo(n,2n) using neutrons from an accelerator. The route is characterized to produce a large quantity of high-quality $$^{99}$$Mo with a minimum level of radioactive wastes, since the cross section of the $$^{100}$$Mo(n,2n)$$^{99}$$Mo reaction at 11 $$<$$ En $$<$$ 18 MeV is large, and the cross sections of the (n,He), (n,n'p), and (n,p) reactions on $$^{100}$$Mo are quite small. Intense neutrons are available because of recent progresses of accelerator and target technologies. In the talk, we show our recent experimental results to obtain $$^{99m}$$Tc with high-quality using $$^{99}$$Mo produced by $$^{100}$$Mo(n,2n).

Oral presentation

Extraction Properties of $$^{99m}$$Tc from irradiated High-density MoO$$_{3}$$ Pellets Solution

Shibata, Akira; Ishida, Takuya; Shiina, Takayuki*; Kobayashi, Masaaki*; Tanase, Masakazu*; Kato, Yoshiaki; Kimura, Akihiro; Ota, Akio*; Yamamoto, Asaki*; Morikawa, Yasumasa*; et al.

no journal, , 

$$^{99m}$$Tc, a daughter nuclide of $$^{99}$$Mo, is commonly used as a radiopharmaceutical. In case of Japan, all of $$^{99}$$Mo are imported from foreign countries. R&D for domestic production of $$^{99}$$Mo by the (n, $$gamma$$) method has been being performed in JMTR from viewpoints of nuclear proliferation resistance and waste management. In this study, experiments of $$^{99}$$Mo/$$^{99m}$$Tc production were performed to enhance recovery yields of $$^{99m}$$Tc. High-density MoO$$_{3}$$ pellets were irradiated in the Kyoto University Reactor (KUR). Solvent extraction method with MEK was used to extract $$^{99m}$$Tc from $$^{99}$$Mo/$$^{99m}$$Tc solution and the maximum recovery yields as high as 80% was achieved. Quality tests were performed, and impurities in $$^{99m}$$Tc solution were evaluated and were efficiently low. It is concluded that $$^{99m}$$Tc solution produced by this method is suitable for a raw material of radiopharmaceutical.

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

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

Evaluation of $$^{99}$$Mo/$$^{99m}$$Tc production with irradiated MoO $$_{3}$$ pellets

Ishida, Takuya; Shiina, Takayuki*; Ota, Akio*; Suzuki, Yoshitaka; Shibata, Akira; Nishikata, Kaori; Kimura, Akihiro; Tanase, Masakazu*; Kobayashi, Masaaki*; Sano, Tadafumi*; et al.

no journal, , 

Technetium-99m ($$^{99m}$$Tc) is one of the radioisotopes which are used most as radiopharmaceuticals, and it is obtained from the parent nuclide of Molybdenum-99 ($$^{99}$$Mo). However, the specific radioactivity of $$^{99}$$Mo by (n, $$gamma$$) method is extremely low compared with that by fission method ((n,f) method), and as a result, the radioactive concentration of the extracted $$^{99m}$$Tc solution is also low. Thus, it is necessary for the high radioactive concentration of the $$^{99m}$$Tc solution to develop the $$^{99}$$Mo/$$^{99m}$$Tc separation/extraction/concentration method. In this study, the experiments of $$^{99}$$Mo/$$^{99m}$$Tc production were performed to enhance recovery yields of $$^{99m}$$Tc and to get a high quality of $$^{99m}$$Tc product. The procedures are described as follows. (1) High-density MoO$$_{3}$$ pellets were irradiated in the Kyoto University Research Reactor (KUR). (2) $$^{99m}$$Tc was extracted with MEK. (3) $$^{99m}$$Tc extracted in MEK was purified and concentrated with acidic alumina column. (4) Product of $$^{99m}$$Tc solution was checked in several factors such as radionuclidic and radiochemical purities. The irradiated MoO$$_{3}$$ pellets were dissolved in 6M-NaOH and the $$^{99}$$Mo/$$^{99m}$$Tc solution was treated with the devices. From the results, the $$^{99m}$$Tc recovery yields achieved 80$$pm$$5% of our goal. Finally, the extracted $$^{99m}$$Tc solution passed the quality inspection of six items.

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

21 (Records 1-20 displayed on this page)