Neutron irradiation effect of high-density MoO 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*; Takahashi, Yoshiyuki*; Zhang, J.*

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