Evaluation and prediction of thermophysical properties of radiochemical solutions and effluents in waste management
- B.A.R.C., Kalpakkam (India). Nuclear Waste Management Group
- B.A.R.C., Trombay (India). Nuclear Waste Management Group
The radiochemical solutions which have to be concentrated by evaporation are generated in the reprocessing of the nuclear fuel. These radiochemical solutions mainly contain nitric acid and sodium carbonate. The radioactive effluent solutions are generated in the decontamination of the active equipment using nitric acid and regeneration of ion-exchangers using sodium-hydroxide and sulfuric acid, and the steam decontamination of sodium and other radionuclides from the nuclear fuel pins of the Fast Breeder Reactor. The radionuclides are generally in trace quantities and do not effect the hydrodynamics and heat transfer in the evaporation process. The temperature of boiling of aqueous electrolytic solutions increases with concentration, thus reducing the effective temperature gradient between the solution and the steam used for heating. Similarly the density and viscosity changes with increase in concentration and temperature of the solution during boiling is of special relevance, as these also influence the flow dynamics and heat transfer. It is imperative that the accurate data of the transport properties such as density, viscosity, surface tension, heat capacity, thermal conductivity etc. are available. The experimental measurements of density, viscosity and boiling point rise for pure and mixture of chemical solutions are made and results are plotted in graphical forms, and polynomial equations have been fitted into the data. The results of new equations for prediction of the thermophysical properties as a function of composition, concentration and temperature of the solutions have been compared with the experimental values. Similarly methods to estimate and predict the thermal conductivity, heat capacity, surface tension, latent heat of vaporization for mixture of aqueous chemical solutions of interest are discussed in this paper.
- OSTI ID:
- 113160
- Report Number(s):
- CONF-930906--; ISBN 0-7918-0691-X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CHEMICAL EFFLUENTS
EXPERIMENTAL DATA
FBR TYPE REACTORS
FORECASTING
FUEL REPROCESSING PLANTS
PHYSICAL PROPERTIES
PROCESS SOLUTIONS
RADIOACTIVE EFFLUENTS
RADIOACTIVE WASTE PROCESSING
SODIUM CARBONATES
SODIUM CHLORIDES
SODIUM NITRATES
SODIUM SULFATES
SPENT FUELS
THERMODYNAMIC PROPERTIES