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Fast reactor spent fuel reprocessing plants should be designed for inherent criticality safety due to high plutonium content. Addition of soluble neutron poison is one way to do that. Gadolinium is the best choice based on neutron absorption cross section and chemical compatibility. In this work, using classical thermodynamic approach, the distribution coefficient of gadolinium in tributyl phosphate...
The present work describes the mathematical basis of a computer code for the analysis of PUREX flowsheet. The model equations have been developed on the basis of the idealized model for mixer settlers. The distribution coefficients relations for U(VI), U(IV), Pu(IV), Pu(III), Ru & Zr and the redox reactions rates of the species involved in U/Pu partitioning are incorporated. The validity of the...
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