A study was undertaken to test the adequacy of current theoretical models used to predict 238U reaction rates in uniform lattice cells containing U0 2 rods in a light water moderator. Calculations were made 28 with two analytical models on data for 26 lattices for which p28 and 025 had been measured. Larqe discrepancies were observed between the measured and calculated results which could be attributed to systematic experimental errors and/or biases in the analytical models.The influence that the typical discrepancies observed would have on the calculated eigenvalue was demonstrated to be appreciable and would generally lead to an underprediction of this quantity, especially for undermoderated lattices. It is recommended that a more detailed study be undertaken to determine the cause of the differences observed between theory and experiment.iii
As a result of the Batch Core Experiment which was conducted in the Plutonium Recycle Test Reactor, a large amount of burnup data and gammaray data was made available for analysis. The data represented plutonium recycle fuel in that the fuel composition was initially U0 2 -2 wt% Pu0 2 .A maximum burnup of 9485 MWD/MTM was determined from the fuel samples The gamma-ray data were analyzed to determine power distributions and effects of fission product migration. The results indicated localized regions of fission product concentrations due to the migrations of 106Ru _ 106 Rh , 134 Cs and 137 Cs .• . .
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techniques. Equations used i n t h e code are described and d e t a i l e d i n p u t i n s t r u c t i o n s are provided. Use o f the code i s i l l u s t r a t e d w i t h a t e s t case, and both p r i n t e d and p l o t t e d ( o p t i o n a l ) output are described.
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