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nsuf-17-cinr-12976

NSUF 17-CINR-12976: Study of the Irradiation Behavior of Fast Reactor Mixed Oxide Annular Fuel with Modern Microstructural Characterization to Support Science Based Model Validation

The objective of this work is to grow the available database of post irradiation data available for annular mixed-oxide (MOX) fuel irradiated in fast spectrum reactors. The key...

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