A series of three critical experiments containing 2 wt.% plutonium enriched fuel has been performed in the Plutonium Recycle Critical Facility. These experiments were performed to provide information on some of the physics characteristics of the batch core. Analytical Correlations were made with the data fran these experiments in order to test the accuracy of calculational methods in their application to plutonium enriched reactor cores. Two computational systems called HTH and HAMER were used in the study. Significant differences in HTH and HAMER calculated results were noted and these differences were determined to result mainly from different epithermal cross-section libraries. The results of this study do not indicate a clear-cut superiority of either HTH or HAMMER for plutonium fuelled cores.

A. The General Process o f Constructi ng I s o t o p i c Ratios. B. Q u a l i t i e s o f an Approach f o r Constructing I s o t o p i c Ratios f o r Safeguards A p p l i c a t i o n s .

Before the availability of isotopic data from chemical reprocessing of spent nuclear fuels, burnup code normalization was done using data from small burnup samples. Chemical reprocessing plant isotopic data are an additional source of burnup data reliably measured to permit normalization of calculational code processes to real data. By applying isotopic correlation techniques to this source of data and to data from burnup calculations, it appears that procedures are available a). to detect code input errors, b).to detect calculational biases in both U and Pu isotopes and c). to diagnose calculational weaknesses. A means whereby the maximum use ,of dissolution data is realized is given. 6 1 2 1 C o m. p a r i s o n , o f Y a n k e e Rowe C o r e V D i s s o l u t i on .Ba..tch Da.ta and C o r e V C a l c u l a t e d , D a t a S 3

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