thermal cycling growth is permanent dimensional change remaining after a temperature cycle; irradiation growth is a radiation-driven change of shape that need not require an applied load. Neither is simply the reversible increase in dimensions of a warm specimen.
For a crystal in its principal axes, a small unconstrained thermal strain is
anisotropic thermal expansion means that the principal components of differ. Adjacent crystal grains with different orientations therefore demand different strain tensors during the same temperature change. Their bonded boundaries impose compatibility and generate internal stresses. plasticity, creep, boundary motion or microcracking can accommodate this mismatch irreversibly; when the accommodation fails to cancel on cooling, a residual strain remains. Repeated cycles can accumulate directional thermal ratcheting, surface roughening or distortion. crystallographic texture, constraints, cycle amplitude and the temperature dependence of yielding and recovery determine the outcome.
Anisotropy alone is insufficient. A freely expanding single crystal under spatially uniform, fully reversible heating returns to its original dimensions. Even cyclic plasticity can settle into a stabilised response rather than ratchet indefinitely. Demonstrating thermal cycling growth means comparing dimensions at the same reference temperature after successive cycles, while controlling external loads, temperature gradients and phase changes. uranium dimensional instability under cycling was investigated directly in the early reactor-materials programme.[ref]
irradiation growth has a different source of irreversibility. displacement cascades create vacancies and self-interstitials; anisotropic migration, clustering and capture at oriented dislocations and boundaries can produce unequal strains along crystal directions. For approximately volume-conserving growth,
although a rod may elongate substantially in one direction. The effect can occur at constant temperature without an external stress. Distinguish it from void swelling, which increases volume through cavities, and irradiation creep, whose directional deformation is stress-dependent. Experiments should therefore measure axial and transverse dimensions, density and the applied stress rather than identifying every increase in length as one mechanism.
The characteristic growth phenomena require an asymmetric material response and a way to retain irreversible change. Low crystal symmetry and directional defect or deformation behaviour make uranium and zirconium important examples, whereas an ideal cubic material has isotropic linear thermal expansion and no symmetry-selected traceless single-crystal growth tensor in an otherwise isotropic environment.
alpha uranium is orthorhombic and has strongly anisotropic thermal response. In a textured polycrystalline material, incompatible crystal grain strains can be accommodated asymmetrically over a thermal cycle and leave macroscopic distortion. The same metal can also show irradiation growth through anisotropic irradiation-defect evolution. zirconium and its hexagonal close-packed alloys are major examples of irradiation growth; their basal and c-axis directions need not acquire the same strain.
Cubic austenitic steel does not exhibit the same intrinsic orientation-driven response merely because it is irradiated. It can nevertheless undergo void swelling, irradiation creep, thermal-stress plasticity or distortion under gradients. Thus absence of this growth mechanism does not imply dimensional stability under all reactor conditions. Conversely, a noncubic crystal is not guaranteed to grow during every thermal cycle: constraints, inelastic accommodation and the microstructure still matter.
crystal grain structure controls both the source of incompatibility and its conversion into a bulk dimensional change. Separate orientation distribution, grain size, crystal grain shape and defect structure rather than treating “fine grained” as a universal cure.
In thermal cycling, different crystal grain orientations rotate the thermal expansion tensor into different laboratory directions. Bonding prevents each crystal grain from following its independent free strain. Coarse crystal grains can produce larger surface relief and longer local mismatch distances; finer crystal grains can distribute the accommodation more uniformly. However, changing grain size also changes strength, boundary-mediated deformation and creep. A fine but strongly textured material can still show directional growth, and enhanced boundary accommodation can itself be irreversible. crystallographic texture and the way mismatch is accommodated must therefore be measured separately.
For irradiation growth, crystallographic texture determines whether directional single-grain changes reinforce or cancel. An illustrative independent-grain average is
where is a crystal grain volume fraction and its orientation. A random orientation average of a traceless growth tensor is zero, whereas crystallographic texture can retain a preferred bulk strain. For an ideal hexagonal crystal grain with principal growth strains , the strain along a direction making angle to the c-axis is
Random crystallographic texture has and cancels this ideal directional growth. This is an orientation model, not proof that real crystal grain constraints or volume-changing processes vanish.
grain boundaries also absorb mobile defects. Boundary spacing and aspect ratio change directional sink distances, while dislocation density, cold working and recrystallisation change competing sinks and residual stresses. These affect the single-grain response before it is averaged. In one model compared with zirconium-alloy experiments, increasing grain size, reducing aspect ratio or reducing dislocation density decreased predicted growth. That result is a useful counterexample to assuming that smaller crystal grains always reduce irradiation growth.[ref]

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