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Report No.

Numerical study on holdup of low-decontaminated MOX powder in proposed confinement box

Suzuki, Mitsutoshi; Namekawa, Takashi; Asano, Takashi ; Niita, Koji*

The advanced MOX fabrication process in FaCT project has been studies to investigate an overall characteristic of nuclear material accounting of Pu in the proposed confinement box. Flow field induced by a forced convection inside the box is numerically simulated to evaluate the MOX particle behavior and a radiation field due to the spontaneous and induced neutrons emitted from Cm and Pu is calculated using PHITS code. The possibility of remote-monitoring techniques using non-destructive assay to apply to a future safegurads measure is invetigated.



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