Cesium and strontium extraction from a synthetic mixed fission product solution using crown compounds in a matrix solution of dinonylnaphthalene sulfonic acid, tributyl phosphate and kerosene
The distributions of cesium and strontium between a synthetic fission product solution in 3M HNO/sub 3/ and a matrix solution of dinonylnaphthalene sulfonic acid (NNS), tributylphosphate (TBP), and kerosene containing crown compounds were studied. The distribution coefficients (org/aq) of all fifteen fission products were measured between 3M HNO/sub 3/ and an equal volume of 5 vol % NNS, 27 vol % TBP, and 68 vol % kerosene containing one of several crown compounds of varying molarity. Bis 4,4'(5')(1-hydroxyheptyl)cyclohexo 18-crown-6 (Crown XVI) was the most effective crown compound in strontium extraction. A 0.02M Crown XVI solution extracted strontium (initially 0.003M Sr+/sup 2/) from the synthetic fission product solution with a distribution coefficient of 1.98. Bis 4,4'(5')(1-hydroxy2-ethylhexyl)benzo 18-crown-6 (Crown XVII) was the most effective crown in cesium extraction. A 0.05M Crown XVII solution extracted cesium (initially 0.006M Cs/sup +/) from the synthetic fission product solution with a distribution coefficient of 1.59. Distribution coefficients of both cesium and strontium decreased from 1.59 to 1.04 and from 1.98 to 1.56, respectively, as the system exposure was increased to 1.0 x 10/sup 7/ rad in a 0.4 x 10/sup 7/ rad/h source. Zirconium was extractable by the NNS, TBP, kerosene matrix solution alone and extractable to a lesser extent when Crown XVI or Crown XVII was present in the matrix solution. As the system exposure to gamma radiation was increased, the distribution coefficient of zirconium increased from about 2.0 to about 3.0 depending on the organic phase under study.
- Research Organization:
- South Carolina Univ., Columbia (USA). Coll. of Engineering
- DOE Contract Number:
- AS09-81SR10714
- OSTI ID:
- 6228085
- Report Number(s):
- DOE/SR/10714-T1; ON: DE85005140
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Thesis
- Country of Publication:
- United States
- Language:
- English
Similar Records
Extraction of cesium and strontium from acidic high activity nuclear waste using a Purex process compatible organic extractant
Experimental measurement of distribution coefficients of Pd and Sr from a synthetic mixed fission product solution
Related Subjects
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
CESIUM
DISTRIBUTION FUNCTIONS
SOLVENT EXTRACTION
STRONTIUM
ZIRCONIUM
CESIUM COMPLEXES
CHEMICAL RADIATION EFFECTS
EXPERIMENTAL DATA
FISSION PRODUCTS
GAMMA RADIATION
HIGH-LEVEL RADIOACTIVE WASTES
KEROSENE
NITRIC ACID
ORGANIC SOLVENTS
POLYETHYLENE GLYCOLS
PUREX PROCESS
STRONTIUM COMPLEXES
SULFONIC ACIDS
TBP
ZIRCONIUM COMPLEXES
ALCOHOLS
ALKALI METAL COMPLEXES
ALKALI METALS
ALKALINE EARTH METAL COMPLEXES
ALKALINE EARTH METALS
BUTYL PHOSPHATES
CHEMISTRY
COMPLEXES
DATA
ELECTROMAGNETIC RADIATION
ELEMENTS
ESTERS
EXTRACTION
FUELS
FUNCTIONS
GLYCOLS
HYDROGEN COMPOUNDS
HYDROXY COMPOUNDS
INFORMATION
INORGANIC ACIDS
IONIZING RADIATIONS
ISOTOPES
LIQUID FUELS
MATERIALS
METALS
NUMERICAL DATA
ORGANIC ACIDS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC POLYMERS
ORGANIC SULFUR COMPOUNDS
PETROLEUM PRODUCTS
PHOSPHORIC ACID ESTERS
POLYMERS
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REPROCESSING
SEPARATION PROCESSES
SOLVENTS
TRANSITION ELEMENT COMPLEXES
TRANSITION ELEMENTS
WASTES
052001* - Nuclear Fuels- Waste Processing
400105 - Separation Procedures