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

Ho, H. Q.; 石田 大樹*; 濱本 真平; 石井 俊晃; 藤本 望*; 高木 直行*; 石塚 悦男

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

This study proposed the new design concept of direct $$^{rm 99m}$$Tc production at the HTTR for domestic demand, aimed to avoid the use of $$^{99}$$Mo-$$^{rm 99m}$$Tc generator and HEU target. With the high temperature at the irradiation region, $$^{rm 99m}$$Tc is separated directly from $$(n,gamma$$)$$^{99}$$Mo inside the reactor by sublimation technique without external electric heating. The foremost advantage of this concept is that $$^{rm 99m}$$Tc is produced and separated continuously without pulling out the Mo target. It makes the design of post-processing facility and the other handing procedures become simpler. Also, the risk of nuclear proliferation is kept to a minimum. With 1 kg of natural MoO$$_{3}$$ target, the total activity of $$^{rm 99m}$$Tc in a year is about 6.8$$times$$10$$^{8}$$ MBq in comparison with 3.0$$times$$10$$^{8}$$ MBq of total $$^{rm 99m}$$Tc supplied in Japan in 2017.

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