Reduction stripping of plutonium (IV) with hydroxylamine nitrate in the centrifugal contactor
Creators
- 1. Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy
Description
Reduction stripping of Pu(IV) with hydroxylamine nitrate under conditions of Purex 3B contactor is carried out with 16-stage mixer-centrifugal settler in laboratory scale. Results show that the apparent recovery of Pu is more than 99.9%. But there is a great difference in the concentration of plutonium of every stage in extraction equipment at different temperature. For example, plutonium concentrations in organic phase of several stages near the organic effluent at 45-50 deg C are lower than that at 20-24 deg C. Thus, recovery efficiency of plutonium can be assured only for the former. However, plutonium will probably be lost, if operating conditions are fluctuated. In addition, plutonium accumulated in the extraction equipment increased appreciably for the case of 20-24 deg C. Therefore, in order to ensure recovery efficiency of Pu, reduction stripping of Pu should be made at higher temperature
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 23
- Journal Issue
- 1
- Series
- At. Energy Sci. Technol.
- Journal Page Range
- 65-72
- ISSN
- 1000-6931
- CODEN
- YKJIE
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 21042471
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- CENTRIFUGATION; EXTRACTION APPARATUSES; HYDROXYLAMINE; NITRATES; PLUTONIUM; REACTION KINETICS; REDUCTION; SOLVENT EXTRACTION; TEMPERATURE CONTROL
- Descriptors DEC
- ACTINIDES; AMINES; CHEMICAL REACTIONS; CONTROL; ELEMENTS; EQUIPMENT; KINETICS; METALS; NITROGEN COMPOUNDS; ORGANIC COMPOUNDS; OXYGEN COMPOUNDS; SEPARATION EQUIPMENT; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS