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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 石田 卓也椎名 孝行太田 朗生木村 明博西方 香緒里柴田 晃棚瀬 正和小林 正明佐野 忠史藤原 靖幸土谷 邦彦
- Publication Date
- 2015-11
- Publication Date (W3CDTF)
- 2015
- Alternative Title
- Establishment of experimental system for 99Mo/99mTc production by neutron activation method
- Periodical title
- JAEA-Technology 2015-030
- Target Audience
- 一般
- Note (General)
- 出版タイプ: NA照射試験炉センターでは、材料試験炉(JMTR)を用いた中性子放射化法((n,$\gamma$)法)によるモリブデン-99($^{99}$Mo)製造に関する技術開発を行っている。(n,$\gamma$)法による$^{99}$Moは、核分裂法((n,f)法)と比べると比放射能が低く、得られるテクネチウム-99m($^{99m}$Tc)溶液の放射能濃度も低くなる。この課題を解決するため、(n,$\gamma$)法で製造した$^{99}$Moから$^{99m}$Tcを回収する手法として、メチルエチルケトン(MEK)を用いた溶媒抽出法に着目し、開発した$^{99}$Mo/$^{99m}$Tc分離・抽出・濃縮試験装置による性能試験を行っている。本報告書は、$^{99}$Mo/$^{99m}$Tc製造の試験体系の確立に貢献するため、高い$^{99m}$Tc回収率を得ることができるよう装置の改良を行い、京都大学研究用原子炉(KUR)で照射した高密度三酸化モリブデン(MoO$_{3}$)ペレットを用いて、MoO$_{3}$ペレット溶解及び$^{99m}$Tcの抽出を行い、得られた$^{99m}$Tc溶液の品質試験を行った結果をまとめたものである。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.
- Source
- /JAEA-Technology-2015-030.pdf (fulltext)