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Close-packed layers occupy one of three lateral registries, conventionally A, B and C. Hexagonal close packing has ABAB stacking, while face-centered cubic stacking is ABCABC. On a bulk-terminated (111) terrace the two kinds of threefold hollow differ by subsurface registry: an hcp hollow places an atom above a second-layer atom, while an fcc hollow continues the ABC sequence.

Compressing the top Au layer makes its registry drift relative to the unreconstructed layers. Parts of the cell occupy fcc hollows, others hcp hollows, and transition strips pass through less favorable bridge-like positions. Those registry changes are associated with partial-dislocation/domain boundaries. Varying local coordination and repulsion from the substrate cause vertical relaxation, producing the observed corrugation rather than an entirely flat shifted sheet.

The low-temperature zirconium matrix has a hexagonal close packing structure. Its crystallographic $a$ and $c$ directions therefore have different elasticity, thermal expansion and available slip systems. Producing tubing also develops a crystallographic texture, so averaging over grains does not necessarily remove these directional effects.

Different expansion along the crystal axes produces intergranular thermal stresses during temperature changes. Under load, easy dislocation glide modes may accommodate some strains much more readily than others; additional slip or crystal twinning is needed for general compatibility. Consequently strength and ductility can depend on the axial, circumferential and radial orientation of the tube.

Irradiation creates vacancies and self-interstitials that cluster into dislocation loops with different crystallographic orientations. Their anisotropic accumulation can produce irradiation growth even without external stress. Different directions can elongate or contract while the net volume change remains small. Texture turns these grain-scale strains into macroscopic length and diameter changes, bowing and stresses between constrained components. This mechanism is distinct from the added cavity volume of void swelling.

The crystallographic character of irradiation loops matters: atomistic calculations by Rory Hulse and Christopher P. Race examine several possible loop types and show that loop energy and shape depend on orientation and size. A single generic spherical-defect description therefore misses important aspects of zirconium's dimensional response.^[ref]

Hydrogen also produces direction-sensitive damage. Zirconium hydrides are brittle precipitates whose preferred orientation depends on crystal texture and stress history. Radially oriented hydrides can offer crack paths across a thin tube wall under circumferential tension. Controlling texture, hydrogen pickup and hydride orientation helps manage that risk; changing the hexagonal structure's orientation cannot by itself eliminate corrosion or irradiation damage.