Published December 1975 | Version v1
Report

Tritium leakage from recycling path

  • 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)

Description

An idea of liquid waste recycling was studied on the basis of wet treatments in an attempt to reduce tritium release from a spent fuel reprocessing plant by the purex method. In this system, tritium leakage from a recycling path is one of the most important items determining the decontamination factor. The co-decontamination process in a recycling path was approximated by extraction system with five components, i.e., UO2(NO3)2-TBP-Dodecane-H2O-HNO3, and tritiated water leaked into organic phase was estimated from the amount of dissolved water. As the result, the leakage of tritiated water from co-decontamination process was found to be about 0.4%, using the liquid composition of the purex method based on the PNC reprocessing flowsheet. In conclusion, the practical decontamination factor of tritium is estimated to be below 50. (auth.)

Additional details

Publishing Information

Imprint Title
Semi-annual progress report of Power Reactor and Nuclear Fuel Development Corporation, Tokai Works
Journal Page Range
p. 127-132.
Report number
PNCT--831-75-02