Evaluation of the irradiation-averaged fission yield for burnup determination in spent fuel assays

Open Access

Fig. 3.

Distribution of the ²³⁸U relative contribution to fissions for all cases from the assessment database. A non-negligible amount of fissions originate from ²³⁸U, as the low cross-section is somewhat balanced by the large ²³⁸U content in low-enriched uranium fuels.

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