Microstructural evolution investigation of irradiated oxide fuels by means of electron backscattered diffraction
Source abstract
Abstract
In this paper, both irradiated UO 2, together with a fresh UO 2.001 sample from the same batch as a reference, and irradiated FR-MOX U 0.55Pu 0.45O 1.99 (TRABANT 2/3) fuel were studied using Electron Back Scattered Diffraction (EBSD). Irradiation of both oxide fuels was carried out at the High Flux Reactor (HFR) Petten, the UO 2 at a moderate maximum Linear Heat Rate (LHR) of 200 W/cm to a burn-up of 5.4 % FIMA (fission per initial metal atom) or 50 MWd/kgUO 2, and the MOX at a high maximum Linear Heat Rate (LHR) of 374 W/cm to a burn-up of 1.7% FIMA. In the irradiated UO 2, the grain growth was observed in the fuel centre. The irradiated MOX (U, Pu)O 2 showed the typical FBR fuel microstructure zones, i.e. as-fabricated (at the fuel edge), equi-axed and columnar grains as observed from the fuel-clad region towards fuel central hole. The LAGB (Low Angle Grain Boundary), 3° < θ < 15°, as an initial state for the HBS structure was observed on both UO 2 and MOX. This restructuring mechanism for both oxide fuels is proposed to follow the well-known polygonization mechanism in which an arrangement of dislocations at the grain boundaries occurs.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering
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References (31)
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