NEUP CINR-17-12976: 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 by examining irradiated fuel from the FO-2 irradiation. The data collected in this project would be used to validate models currently being developed at the Japanese Atomic Energy Agency (JAEA) for fuel performance models that seek to simulate MOX fuel behavior and will be implemented in BISON.

Additional Info

Field	Value
Awarded Institution	Idaho National Laboratory
PI	Jason Harp