Plutonium Trifluoride as a Fuel for Molten Salt Reactors-Solubility Studies

D. D. Sood; P. N. Iyer; R. Prasad; V. N. Vaidya; K. N. Roy; V. Venugopal; Z. Singh; M. V. Ramaniah

doi:dx.doi.org/10.13182/NT75-A24314

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Plutonium Trifluoride as a Fuel for Molten Salt Reactors-Solubility Studies

D. D. Sood, P. N. Iyer, R. Prasad, V. N. Vaidya, K. N. Roy, V. Venugopal, Z. Singh, M. V. Ramaniah

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 411-415

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24314

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The feasibility of using plutonium as a fuel in a molten salt reactor has been evaluated by the determination of the solubility of PuF₃ in a number of salt compositions containing LiF, BeF₂, and ThF₄ in the temperature range of interest for such a reactor. An empirical correlation for the solubility of PuF₃ as a function of salt composition has been obtained from the solubility data to calculate the solubility of PuF₃ in other salt compositions of interest. These data indicate that PuF₃ has adequate solubility in salt compositions of interest for a molten salt reactor of either the converter or the breeder type.