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Evaluations of Molten Salt Breeder Reactors have pointed t h e direction of desirable design, research, and development f o r improving t h e economic and breeding performance of these systems, In design, t h e conventional concept of processing f u e l i n f a c i l i t i e s t h a t are separate from t h e reactor plant needs t o be abandoned i n favor of integrating t h e processing operations d i r e c t l y i n t o the reactor building. For the MSBR, only a small spaoe i s required adjacent t o the reactor c e l l s f o r processing c e l l s . This arrangement allows significant savings i n capital, operating;, shipping, and inventory costs.Research and development have shown t h a t i r r a d i a t e d MSBR f u e l can be decontaminated i n a f our-step process consisting of fluorination, UF6 sorption, vacuum d i s t f l l a t i o n , and reduction-reconstitution, These operations recover not only the uranium but a l s o the LiF-BeF2 c a r r i e r , Fluorination and sorption technologies are well developed f o r batchwise operation, having; advanced through the p i l o t plant stage. However, f o r MSBR application, these two steps, a s well a s d i s t i l l a t i o n and reduction-reconstituti~n~must be developed f o r continuous operation. These four unit processes a r e rather simple and straightforward; however, vacuum d i s t i l l a t i o n requires a higher temperature (-1000" C ) than has been encountered previously i n molten salt processing . DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. DISCLAIMERPortions of this document may be illegible in electronic image products. Images are produced from the best available original document. 1 2 I F e r t i l e stream processing s t e p s c o n s i s t of protactinium removal, f l u o r i n a t i o n , and UF6 sorption, Protactinium removal i s s i n g u l a r l y important because of t h e improved breeding performancewithlow protactinium concentrations i n t h e f e r t i l e stream. R e l a t i v e l y high processing r a t e s a r e required. Xenon poisoning i s kept low by i n j e c t i n g a purge gas d i r e c t l y i n t o t h e c i r c u l a t i n g f u e l stream. An i n -l i n e s t r i p p e r removes the gases, ...

NOTICE This document contains information of a preliminary nature. It is subject to revision or correction and therefore does not represent a .

S. H. Jury and M. E, Whatley ABSTOACT A set of eqxiations was written which allowed the calculation of equilibritim concentrations in the solvent phase of nitric acid and uranyl nitrate, given the initial TBP concentration in the solvent and the aqueous phase concentrations of acid and uranium. An ORACLE subroutine was written based on these equations which will calcxolate a set of equilibrium values in about 55 milliseconds. The subroutine was incorporated into a short program to calculate equilibrium points. A set of calcTilated points are presented in graphical form for 5, 20, 50, kO, ahd 100^ TBP for nitric acid concentrations up to 7 M and uranyl nitrate concentrations iip to 0.6 M in the aqueous pha¥e. Since these calculations were based on limited data, it is the purpose of this memo to invite comment on their accuracy. The equations were reworked from a Russian paper by A. M. Rozen and L. P. Khorkhorina, using en^terical polynomial fits for some poorly defined paramsters, and were based principally on data from J. W. Codding. This project was undertaken to provide a subroutine to calculate equilibria in a general purpose (BACLE program to calculate the performance of multistage compound extraction cascades with more than one significant solute. NOTICEThis document contains information of a preliminary nature and was prepared primarily for internal use at the Oak Ridge National Laboratory. It is subject to revision or correction and therefore does not represent a final report. The Information is not to be abstracted, reprinted or otherwise given public dissemination without the approval of the ORNL patent branch. Legal and Information Control Department.