13-18 May 2018
Casino Conference Centre
Europe/Prague timezone

Hot test of advanced Purex process and its results

15 May 2018, 13:30
Marble Hall (Casino Conference Centre)

Marble Hall

Casino Conference Centre

Reitenbergerova 4/95, Mariánské Lázně, Czech Republic
Invited Chemistry of Nuclear Fuel Cycle, Radiochemical Problems in Nuclear Waste Management NFC 3


guoan ye


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.
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.

Primary authors

guoan ye Zheng Weifang (China Institute of Atomic Energy) He Hui (China Institute of Atomic Energy) Chcnag Zhiyuan (China Institute of Atomic Energy)

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