Accuracy Evaluation of Reactor Records based on Solution Analyses Data of Spent Fuels at JNC Tokai Reprocessing Plant

A series of 235U residual enrichment of reactor records, which affects reactivity of individual fuel assembly directly, were compared with solution analyses data as an example of reactor records validation. The validation was based on solution analyses data of spent fuels at JNC(Japan Nuclear Fuel Cycle Development Institute) Tokai reprocessing plant. A large majority of the difference data between reactor records and solution analyses data about 235U residual enrichment were within ±0.1wt%, it could be concluded that the error of 235U residual enrichment of reactor records were within ±0.1wt%. The initial enrichment tolerance of a fuel is within ±0.1wt% also. It was concluded that the accuracy of 235U residual enrichment of reactor records may be same as the initial enrichment tolerance from the study based on solution analyses data at the Tokai reprocessing plant.