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Journal Articles

Conceptual design of direct $$^{rm 99m}$$Tc production facility at the high temperature engineering test reactor

Ho, H. Q.; Ishida, Hiroki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Takaki, Naoyuki*; Ishitsuka, Etsuo

Nuclear Engineering and Design, 352, p.110174_1 - 110174_7, 2019/10

 Times Cited Count:1 Percentile:10.81(Nuclear Science & Technology)

Journal Articles

Development of $$^{99}$$Mo/$$^{99m}$$Tc generator for the $$^{99}$$Mo/$$^{99m}$$Tc domestic production

Fukumitsu, Nobuyoshi*; Tsuchiya, Kunihiko; Ariga, Katsuhiko*; Yamauchi, Yusuke*

Isotope News, (742), p.20 - 24, 2016/02

no abstracts in English

Journal Articles

Neutron irradiation effect of high-density MoO$$_{3}$$ pellets for Mo-99 production, 2

Nishikata, Kaori; Ishida, Takuya; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

KURRI Progress Report 2014, P. 109, 2015/07

As one of effective applications of the Japan Materials Testing Reactor (JMTR), JAEA has a plan to produce $$^{99}$$Mo by (n,$$gamma$$) method ((n,$$gamma$$)$$^{99}$$Mo production), a parent nuclide of $$^{99m}$$Tc. In this study, preliminary irradiation test was carried out with the high-density molybdenum trioxide (MoO$$_{3}$$) pellets in the hydraulic conveyer (HYD) of the Kyoto University Research Reactor (KUR) and the $$^{99m}$$Tc solution extracted from $$^{99}$$Mo was evaluated. After the irradiation test of the high-density MoO$$_{3}$$ pellets in the KUR, $$^{99m}$$Tc was extracted from the Mo solution and the recovery rate of $$^{99m}$$Tc achieved the target values. The $$^{99m}$$Tc solution also got the value that satisfied the standard value for $$^{99m}$$Tc radiopharmaceutical products by the solvent extraction method.

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

Status of domestic production of medical radioisotope (technetium-99m) in Japan

Tsuchiya, Kunihiko

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

Feasibility study of 99mTc production at HTTR using sublimation method

Ho, H. Q.; Ishida, Hiroki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Takaki, Naoyuki*; Ishitsuka, Etsuo

no journal, , 

Oral presentation

Proposal of direct $$^{rm 99m}$$Tc production facility at high temperature engineering test reactor

Ho, H. Q.; Ishida, Hiroki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Takaki, Naoyuki*; Ishitsuka, Etsuo

no journal, , 

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