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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：8 Percentile：51.63(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：43.98(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$$_{3}$$.

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

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：45 Percentile：85.36(Physics, Multidisciplinary)

Journal Articles

Fabrication development of high-density MoO$$_{3}$$ pellets for (n, $$gamma$$) $$^{99}$$Mo production

Nishikata, Kaori; Kimura, Akihiro; Tsuchiya, Kunihiko; Suzuki, Kunihiko*; Akiyama, Hiroaki*; Nagakura, Masaaki*; Kawauchi, Yukimasa*; Tanase, Masakazu*

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

http://www.murr.missouri.edu/ismtr/papercall/Papers/Ecodesign/Suzuki_K_PAPER=Fabrication%20Dev%20of%20High%20Dens%20MoO3%20Pellets.pdf

In this study, experimental fabrication tests of the high-density MoO$$_{3}$$ pellets were carried out by the Plasma Activated Sintering (PAS) method, which requires relatively lower temperature and shorter time to fabricate the pellets. From the results, the PAS method combined with oxidation process, prior to dissolution into sodium hydroxide solution, is a useful measure to fabricate high-density MoO$$_{3}$$ Pellets for the future domestic production of $$^{rm 99m}$$Tc. The irradiation tests and characterization with these pellets will be carried out under the international cooperation.

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：64.51(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

Development of $$^{192}$$Ir radiation sources for intravascular irradiation

Kogure, Hiroto; Sorita, Takami; Iwamoto, Seikichi; Nagata, Yasushi*; Hiraoka, Masahiro*; Iwata, Kazuro*; Kawauchi, Yukimasa*; Suzuki, Kazutoshi*

JAERI-Tech 2003-003, 26 Pages, 2003/03

JAERI-Tech-2003-003.pdf:4.83MB

Intravascular brachytherapy is a novel therapy for preventing the restenosis of coronary artery by use of low-dose irradiation. JAERI and Kyoto University have been developing $$^{192}$$Ir radiation sources by the cooperative research project entitled as "The research on safety and effectiveness of the intravascular brachytherapy for preventing restenosis of the coronary artery disease" since 1998. The radiation source was introduced into the stenosis through a catheter (a guide-tube to insert directly into vascular) to irradiate the diseased part. Ten $$^{192}$$Ir seed sources ($$phi$$0.4 mm $$times$$ 2.5 mm) were positioned between nylon spacers ($$phi$$0.3 mm $$times$$ 1.0 mm) in a flexible covering tube and the tube was plugged with a core-wire; the tube was shrunk to fix the inside materials and the size is 0.46 mm in diameter and 3 m in length. The physically optimal design was determined to insert the radiation source easily into vascular and to get the dose uniformity in the diseased part. The production method of the radiation source, which is practical to use in the clinics was also established.

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

Evaluation of Lu-177 production in the research reactor JRR-3

Fujino, Shunsuke; Hashimoto, Kazuyuki; Saeki, Hideya*; Kawauchi, Yukimasa*; Kawabata, Masako*; Chiba, Yusuke

no journal, , 

Lutetium-177 (Lu-177)is a medical radioisotope used in approved radiopharmaceutical "Lutathera" to treat neuroendocrine tumours. And it is one of the promising radionuclides for new therapeutic radiopharmaceuticals. However, Lu-177 is dependent on imports from overseas, and there are concerns that transportation problems etc. may affect domestic distribution and development of new pharmaceuticals. In order to confirm whether JAEA can produce a portion of the Lu-177 for research, we conducted a production test of Lu-177 using JRR-3.

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

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

13 (Records 1-13 displayed on this page)
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