Solidification behavior of the simulated oxide debris

酸化物系模擬デブリの凝固挙動

Sudo, Ayako; Mizusako, Fumiki*; Hoshino, Kuniyoshi*; Sato, Takumi; Nagae, Yuji; Kurata, Masaki

In order to obtain the knowledge on the phase relationship and stratification behavior of oxide debris under the slow solidification condition, liquefaction/solidification tests of simulated oxide debris were performed by using a high frequency induction furnace. As the oxides components from the core melt and structural materials, sintered pellets of UO $_{2}$ -ZrO $_{2}$ -sim-FPs and powder of FeO and B $_{4}$ C were prepared. The powder mixture and crashed sintered oxides were heated to 2600 $^{circ}$ C in Ar atmosphere in the first step (partial liquefaction), and then solidified at two different cooling rates; furnace cooling (No.1) and slow cooling (5 $^{circ}$ C /min, No.2). For the corium microstructure study, solidified samples were subjected to elemental analysis by SEM/EDX. Cross sectional images of both samples showed that the oxide layer and metallic layer were separately solidified. EDX analysis of oxide layer of No.1 sample revealed four phases; (U $_{0.6}$ Zr $_{0.31}$ Fe $_{0.09}$ )O $_{2}$ , (Zr $_{0.51}$ U $_{0.34}$ Fe $_{0.15}$ )O $_{2}$ , ZrO $_{2}$ and Fe metal. The tendency of re-distribution of oxide elements observed in No.2 was similar to that of No.1, however, the grain-growth of (Zr,U)O $_{2}$ phase occurred at the bottom region of the oxide layer. In these results, the phases detected in both samples were in reasonable accordance with those evaluated by the UO $_{2}$ -ZrO $_{2}$ -FeO phase diagram.

使用言語	:	English
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発表会議名	:	2nd TITECH-CRIEPI-JAEA Joint Workshop
開催年月	:	2018/07
開催都市	:	Tokyo
開催国	:	Japan
キーワード	:	oxide debris; slow solidification; stratification; 福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident

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