Extraction studies of gadolinium relevant to its use as neutron poison in the PUREX process

The extraction behavior of gadolinium into tri-n-butyl phosphate (TBP) (0.37–1.1M) in n-dodecane (n-DD) as diluent from different concentrations of nitric acid (1–13.5M) has been systematically investigated to establish the feasibility of using gadolinium as soluble neutron poison for ensuring nucle...

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Bibliographic Details
Published in:Progress in nuclear energy (New series) 2017-07, Vol.98, p.234-238
Main Authors: Ganesh, S., Desigan, N., Pandey, N.K., Mallika, C., Kamachi Mudali, U.
Format: Article
Language:English
Subjects:
Acidity
Decontamination
Distribution coefficient
Dodecane
Extraction
FBR fuel reprocessing
Feasibility
Gadolinium
Nitric acid
Nuclear energy
Nuclear engineering
Nuclear fuel reprocessing
Nuclear fuels
Nuclear safety
Soluble neutron poison
Solvent extraction
Solvent extraction processes
Spent nuclear fuels
Stress concentration
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Summary:The extraction behavior of gadolinium into tri-n-butyl phosphate (TBP) (0.37–1.1M) in n-dodecane (n-DD) as diluent from different concentrations of nitric acid (1–13.5M) has been systematically investigated to establish the feasibility of using gadolinium as soluble neutron poison for ensuring nuclear criticality safety during the processing of FBR spent fuel containing higher concentrations of fissile material. The effect of acidity, temperature, metal loading and gadolinium concentration on the distribution co-efficient of Gd(III) are established. The obtained results clearly indicate the feasibility to decontaminate Gd(III) under typical FBR fuel reprocessing conditions thereby enabling to qualify the final product to be pure from the point of view of nuclear poison impurity.
ISSN:0149-1970
1878-4224
DOI:10.1016/j.pnucene.2017.03.027