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The computer code PARC was developed in Japan Atomic Energy Agency, in order to predict the behavior of uranium, plutonium, neptunium, and several fission products in a reprocessing plant for spent nuclear fuel. This code has several useful calculation functions, i.e., PARC can deal with both mixer settlers and pulsed columns simultaneously, and new equations for chemical reaction, reaction constant, and distribution ratio can be easily inputted to PARC without the recompilation of the program. Therefore, it is expected to be widely used for basic solvent extraction study, separation process design, plant management, and safety analysis for future reprocessing. In the present paper, the outlines of an extractor model and several chemical reaction models used in PARC are introduced, and results of calculations for uranium and plutonium behaviors in the U/Pu separation process in PUREX are shown, which enable the elucidation of the effect of the increase in Pu concentration in the feed solution and the importance of the selection of Pu oxidation/reduction reaction models.

Development of a Computer Code, PARC, for Simulation of Solvent Extraction Process in Reprocessing