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Dissolution behavior of (U,Zr)O$$_{2}$$-based simulated fuel debris in nitric acid

(U,Zr)O$$_{2}$$をベースとする模擬燃料デブリの硝酸中での溶解挙動

池内 宏知  ; 石原 美穂; 矢野 公彦 ; 鍛治 直也; 中島 靖雄  ; 鷲谷 忠博 

Ikeuchi, Hirotomo; Ishihara, Miho; Yano, Kimihiko; Kaji, Naoya; Nakajima, Yasuo; Washiya, Tadahiro

To explore the possibility of dissolving fuel debris as a potential pre-treatment for waste treatment, dissolution tests of U$$_{1-}$$$$_{x}$$Zr$$_{x}$$O$$_{2}$$ and (U,Pu)$$_{1-}$$$$_{x}$$Zr$$_{x}$$O$$_{2}$$ were carried out in 6 M HNO$$_{3}$$ at 353 K. While the U and Zr indicated congruent leaching from the simulated debris with U-rich compositions, a preferential leaching of U was observed with Zr-rich compositions. Taking into account these different dissolution phenomena, the dissolution rate analysis was carried out using surface-area model to calculate the instantaneous dissolution rate (IDR). From these findings, dissolution with HNO$$_{3}$$ is expected to be only applicable in U-rich compositions ($$x$$ $$<$$ 0.3) if the dissolution in 6 M HNO$$_{3}$$ at 353 K is assumed. Application of complexing acids such as mixture of HNO$$_{3}$$ and HF should be considered to increase the dissolution rate of the phases with Zr-rich compositions.

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パーセンタイル:47.62

分野:Nuclear Science & Technology

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