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
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8340119
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- DECONTAMINATION; EFFICIENCY; HEAVY WATER; LEAKS; ORGANIC SOLVENTS; PUREX PROCESS; RADIOACTIVE WASTE PROCESSING; SOLVENT EXTRACTION; TRITIUM; TRITIUM COMPOUNDS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLEANING; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; NONAQUEOUS SOLVENTS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; REPROCESSING; SEPARATION PROCESSES; SOLVENTS; WASTE MANAGEMENT; WASTE PROCESSING; WATER; YEARS LIVING RADIOISOTOPES