Elution properties of cesium contained within irradiated fast neutron reactor fuel in water and diluted nitric acid solution

Nakahara, Masaumi; Kaji, Naoya; Nomura, Kazunori  

In terms of preventing the formation of Pu and Cs compound, Cs in the feed solution should decrease in the U crystallization process. In order to separate Cs contained within irradiated nuclear fuel, the immersion experiments were carried out with the pure water and diluted HNO solution. The elusion ratio of Cs within the powdered fuel in the pure water and 0.1 mol/dm HNO solution after 67 h was 33.8 and 38.3%, respectively. The experimental results suggest a possible beneficial effect of Cs elusion by immersion of the powdered fuel in the pure water and diluted HNO solution before the fuel dissolution process.