The hot test of advanced Purex processing (Fig.1) based on organic reducing agent was carried out by using experimental reactor UO2 spent fuel with low burn-up in CRARL(China reprocessing and radiochemistry laboratory).
Fig. 1: The flow-sheet of advanced Purex process.
Several used fuel rods were chopped, dissolved and then separation processing was conducted. Various determination methods were used including K-edge and L-edge densimeter for U or Pu and U/Pu solution, time resolved laser fluorescence trace of U,and X-ray fluorescence or X-ray prediffraction of graphite crystal for low concentrate Pu,and so on. The results such as the recovery of U and Pu, separation factor of U and Pu, decontamination of U and Pu from fission products are satisfactory. During and after the experiment, radioactive discharges into the environment and internal exposure of the staff were monitored.