4.7 Article

Microstructural and mechanical property evolution of a nuclear zirconium-4 alloy fabricated via laser powder bed fusion and annealing heat treatment

Journal

VIRTUAL AND PHYSICAL PROTOTYPING
Volume 18, Issue 1, Pages -

Publisher

TAYLOR & FRANCIS LTD
DOI: 10.1080/17452759.2023.2189597

Keywords

Zirconium alloy; Zr-4; additive manufacturing; laser powder bed fusion; annealing

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This study investigated the printability, microstructure, and mechanical properties of Zr-4 alloy additively manufactured by laser powder bed fusion (LPBF) for the first time. The optimized printing parameters resulted in a Zr-4 alloy with a high relative density of 99.77%. Increasing the annealing temperature led to a microstructural change in the alloy, resulting in a high compressive strength of 2130 MPa and compressive strain of 36%. Precipitation of Zr (x) (Fe2Cr) compounds at annealing temperatures exceeding 700 degrees C strengthened the alloy by pinning effect. These findings provide valuable guidance for the manufacture of geometrically complex Zr alloy parts for nuclear power applications.
Zirconium (Zr) alloys are widely used in nuclear energy because of their excellent mechanical properties and low thermal neutron absorption cross-section. This work investigated the printability, microstructure, and mechanical properties of Zr-4 alloy additively manufactured by laser powder bed fusion (LPBF) for the first time. The effect of annealing temperature on the microstructural and the mechanical property evolution of the printed Zr-4 alloy was studied. The results exhibited that the Zr-4 alloy with a high relative density of 99.77% was obtained using optimised printing parameters. With an increase in the annealing temperature, the formed alpha phase of the Zr-4 alloy changed from an acicular shape to a coarse-twisted shape, and finally to an equiaxed shape. Such microstructure change endowed the alloy with a high compressive strength of 2130 MPa and compressive strain of 36%. When the annealing temperature exceeded 700 degrees C, Zr (x) (Fe2Cr) compounds were precipitated, strengthening the alloy by pinning effect. These findings provide valuable guidance for the manufacture of geometrically complex Zr alloy parts for nuclear power applications.

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