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Feasibility study of 99mTc production at HTTR using sublimation method

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 investigated the feasibility of direct 99m-Tc production at the high temperature engineering test reactor (HTTR), aimed to avoid using the high enriched uranium (HEU) target as in conventional method. With the high temperature at irradiation area, the 99m-Tc is separated directly from (n,$$gamma$$)99-Mo inside the reactor using a sublimation technique without external electric heating. The new design could simplify the post-processing and other handling procedures. The risk of nuclear proliferation is also kept to a minimum.

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